ATF Tensile Tests Research Report EK-FRL-2023-120-1-4-M0
Radionuclide concentrations in mussels collected from the southern coast of Bangladesh.csv
ATF SEM Cr Coated Zr EK-FRL-2021-161-1-1-M0
Total (radiative+convective) Heat Flux form Cladding Surface (W/m) : Qloss_09125 at 912.5 mm, etc.
IFA-650.10 (PWR fuel) - Total Heat Flux from Cladding Surface
ATF SEM CNL Samples Research Report EK-FRL-2023-120-1-6-M0
ATF SEM Oxidised Samples Research Report EK-FRL-2023-1-11-M0
In the framework of the IAEA CRP “Testing and Simulation for Advanced Technology and Accident Tolerant Fuels (ATF-TS)” project the open sources material properties for FeCrAl and Cr-coated Zr cladding were collected.
ATF Open Sources Material Properties Database Developed by IAEA CRP “ATF-TS” Partners
Natural radionuclide of Po210 in the edible seafood affected by coal-fired power plant industry in Kapar coastal area of Malaysia
Natural radionuclide of Po210 in the edible seafood affected by coal-fired power plant industry in Kapar coastal area of Malaysia.csv
IFA-650.10 (PWR fuel) - Coolant Temperatures
The dataset is provided by JAEA (Japan) in the framework of IAEA CRP T12031” FUEL MATERIALS FOR FAST REACTORS (FMFR) (2019-2023)”. The B5D-2 test was the power-to-melt (PTM) experiment in Joyo. By using Un-instrumented Fuel Irradiation Subassembly -B (UNIS-B), B5D-2 was irradiated at the position 000 for 0.17 EFPD in the 24th cycle of Joyo Mk-II in 1992. The rate of reactor power rise from 50 MWt was 0.45 MWt/min and the reactor power was maintained at 98.5 MWt for 10 min. The fuel melting during experiment was confirmed in PIE. The experiment parameters in B5D-2 experiment were O/M ratio, pellet density, and plenum gas composition, which was either He gas or He-4%Kr-4%Xe simulating "Tag Gas" composition to detect the rod failure in Monju. The UNIS-B consisted of 6 compartments including 4 fuel rods. Total of 24 fuel rods were irradiated in B5D-2 experiments. The PTM of B5D-2 fuel rods were estimated in the range of ~600-700 W/cm. The effect of O/M ratio on PTM was observed, but that of plenum gas composition was not clearly observed. Axial incipient melting positions were defined by considering a molten fuel axial movement behaviour. The experiment results from the bottom and top incipient melting extent and the fissile column centre in B5206 rod, of which O/M ratio, pellet density, and plenum gas composition was 1.97, 95 %T.D. and He gas, respectively, including fabrication, irradiation and PIE data is provided.
Irradiation Histories Axial Node7 325mmBFC
The CORA-15 bundle test was performed under transient conditions typical for many CORA-PWR tests with bundle containing two Ag-In-Cd neutron absorber rods. Unlike other CORA bundles, all heated and unheated fuel rod simulators (16 + 7 correspondingly) were filled with helium and pressurized to 6.0 MPa before transient. During the transient, all rods underwent ballooning and burst. Ballooning progressed for about 100 s. Bursts occurred within 150 s (between 3500 and 3650 s) in the temperature bandwidth between about 700 and 800 °C. The mostly probable burst elevation for the bundle was at 750 mm (which was the hottest elevation during the burst period). During further heat-ups, temperature escalation due to the zirconium-steam reaction starts at elevations of 550 to 950 mm at temperature of about 1100 °C. In presence of PWR absorber rods, the sequence of failure starts with the release, relocation, and re-solidification of the (Ag, In, Cd) melt. The melt release occurred between 1290 and 1350 °C at elevations between 750 and 800 mm. Most of the melt reacted with the cladding and guide tube by liquefying the zirconium components, forming a metallic melt of the type (Ag, In, Zr). This melt was capable of dissolving Zircaloy as low as 1250 °C, i.e., clearly below the melting point of Zircaloy (1760 °C). During the temperature escalation above 1800 °C, Zr melt formed in the gap between ZrO2 and UO2 was relocated partially inside the gap to lower bundle elevations and partially penetrated through the failed ZrO2 layer into the space between its neighbouring elements. The resulting melt of the fuel rod interaction, containing mainly U, Zr and O relocated downwards as a slug and solidified between 400 and 550 mm according to its solidus temperature as a large lump of porous structure. The maximum bundle blockage (almost 100%) was observed at the top of the Inconel grid spacer (at about 500 mm). The (Ag, In, Cd) absorber melt with the much lower solidus temperature solidified down at the lower elevation of about 150 mm. Post-test investigations showed negligible oxidized cladding up to elevation of about 350 mm. The claddings were completely oxidized between elevations 480 and 1000 mm. The maximum hydrogen release rate of 210 mg/s was measured on the end of the transient (4800 s). The total hydrogen release was 145 ± 15 g
This international compilation of radionuclide and stable isotope soil-plant concentration ratio values for tropical environments is an output of [IAEA’s Modelling and Data for Radiological Impact Assessments II (MODARIA II) programme (2016–2019)](https://www-ns.iaea.org/projects/modaria/modaria2.asp) and is based on the Köppen-Geiger climate classification ([BECK et al. 2018](https://www.nature.com/articles/sdata2018214)). The IAEA’s MODARIA II tropical dataset is associated with [IAEA’s TECDOC-1979: Soil-Plant Transfer of Radionuclides in Non-Temperate Environments (2021)](https://www-pub.iaea.org/MTCD/Publications/PDF/TE-1979web.pdf). Information in the dataset is organized into 41 fields, with individual lines in ascending order of their source reference. These headline fields are described in the associated ‘Explanatory Information’ file, while a description of the dataset content can be found in the ‘Dataset content’ file. Note that some of the records contain empty fields due to missing information in the reference source.
ATF SEM FeCrAl Sample Research Report EK-FRL-2023-120-1-9-M0
ATF Ring Compression Tests Research Report EK-FRL-2023-120-1-5-M1
IFA-650.9 (PWR fuel) - Coolant Temperatures
Irradiation Histories Axial Node11 525mmBFC
Irradiation Histories Axial Node10 475mmBFC
Cladding Surface Temperatures (C) : Tcl_09125 at 912.5 mm, Tcl_09375 at 937.5 mm, etc.
IFA-650.11 (VVER fuel) - Cladding Surface Temperatures
Irradiation Histories Axial Node4 175mmBFC
QUENCH-L0 was the commissioning test for the QUENCH-L1 bundle experiment with Zircaloy-4 cladding tubes, defined as reference test for the QUENCH-LOCA test series. The overall objective of this bundle test series is the investigation of ballooning, burst and secondary hydrogen uptake of the cladding under representative design-based accident conditions, as well as to check the embrittlement criteria by means of detailed mechanical post-test investigations.
Heavy elements concentrations, physiochemical characteristics and natural radionuclides levels along the Saudi coastline of the Gulf of Aqaba.csv
ATF-TS Database Research Report EK-FRL-2024-120-1-1-M0
ATF SEM BSU Samples Research Report EK-FRL-2023-120-1-10-M0
A series of six out-of-reactor LOCA simulation tests were performed from 2011 to 2012 by Studsvik Nuclear AB, Sweden, under contract with the U.S. Nuclear Regulatory Commission (U.S. NRC). The tests were done on fuel pellets that had been sampled from full-length elements with average burnups ranging from 55 to 72 MWd/kgU. All the fuel elements were of Westinghouse PWR design, with UO2 fuel pellets and first generation ZIRLO (Zr-1.03Nb-0.98Sn by wt%) cladding. The tests were designed to assess the mechanical performance of ballooned and ruptured high burnup fuel rods under typical LWR LOCA conditions; useful information on fuel fragmentation, axial relocation and dispersal were achieved from these tests.
Irradiation Histories Axial Node9 425mmBFC
Distribution of radionuclides from anthropogenic activities has been intensively studied due to the accumulation of radionuclides in marine ecosystem. Manjung area is affected by rapid population growth and socio-economic development such as heavy industrial activities including coal fired power plant, iron foundries, port development and factories, agricultural runoff, waste and toxic discharge from factories.It has radiological risk and toxic effect when effluent from the industries in the area containing radioactive materials either being transported to the atmosphere and deposited back over the land or by run off to the river and flow into coastal area and being absorbed by marine biota. Radionuclides presence in the marine ecosystem can be adversely affect human health when it enters the food chain. This study is focusing on the radionuclides [thorium (Th), uranium (U), radium-226 (226Ra), radium-228 (228Ra) and potassium-40 (40K)] content in marine biota and sea water from Manjung coastal area. Five species of marine biota including Johnius dussumieri (Ikan Gelama), Pseudorhombus malayanus (Ikan Sebelah), Arius maculatus (Ikan Duri), Portunus pelagicus (Ketam Renjong) and Charybdis natator (Ketam Salib) were collected during rainy and dry seasons. Measurements were carried out using Inductively Coupled Plasma Mass Spectrometer (ICPMS). The results show that the concentration of radionuclides varies depends on ecological environment of respective marine biota species. The concentrations and activity concentrations are used for the assessment of potential internal hazard index (Hin), transfer factor (TF), ingestion dose rate (D) and health risk index (HRI) to monitor radiological risk for human consumption. View on MARIS: * https://maris.iaea.org/explore/type/2/ref/502
Accumulation of radionuclides in selected marine biota from Manjung coastal area
Irradiation Histories Axial Node3 125mmBFC
Irradiation Histories Axial Node1 25mmBFC
IAEA - CRP SFR fuels - CEA - Santenay_1_Input_data oct 2021.xlsx
A study on 137Cs, 40K, 226Ra, 228Ra, and 238U was carried out along the EEZ of Qatar. Results serve as the ﬁrst ever baseline data. The level of 137Cs (mean value 1.6 ± 0.4 Bq m-3) in water ﬁlters was found to be in the same order of magnitude as reported by others in worldwide marine radioactivity studies. Results are also in agreement with values reported from other Gulf regions. The computed values of sediment–water distribution coefﬁcients Kd, are lower than the values given by IAEA. Measurements were carried out for bottom sediments, biota samples like ﬁsh, oyster, sponge, seashell, mangrove, crab, shrimp, starﬁsh, dugong and algae. The ‘concentration factors’ reported for biota samples are below the levels published by IAEA and cause no signiﬁcant impact on human health for seafood consumers in Qatar. View on MARIS: * Seawwater: https://maris.iaea.org/explore/type/1/ref/403 * Biota: https://maris.iaea.org/explore/type/2/ref/403
Radioactivity levels in the marine environment along the Exclusive Economic Zone (EEZ) of Qatar
FBTR MOX pin results summary and 62 mm location
ATF SEM AEOI Samples Research Report EK-FRL-2023-120-1-8-M0
Phenix SANTENAY This experimental irradiation was performed to study the behavior of a SUPERPHENIX 1 (SPX-1) fuel element with annular fuel pellets operating at high Linear Heat Rate. The KCI 6703 PHENIX capsule, alias SANTENAY, (Fig. 1) included six fuel pins close to the standard SPX-1 external core and one inert pin, filled with alumina pellets (pin Nb. 4). Fig. 1 SANTENAY : arrangement of the seven wire-spaced pins in the KCI 6703 capsule Main characteristics of the fuel pin Nb.1 Table 1 and Fig. 2 describes the pin n°1 with the description of the pin design, the fuel composition and geometry and the clad material. Main irradiation conditions Capsule KCI 6703 (SANTENAY) was irradiated inside the carriage sub-assembly DCC 2143 in the 1st row of the PHENIX core. During 487 Equivalent Full Power Days (EFPD) from the 33rd to the 38th cycles, the fuel reached a maximum burn-up of 9 at.% and a maximum cladding damage of 74 dpa NRT. The Linear Heat Rate (LHR) at Peak Power Position (PPP) of the pin Nb. 1 has always been between 400 and 585 W/cm and the maximal cladding temperature between 610 and 640 °C. Table -1 SANTENAY : pin characteristics Fig. 2 SANTENAY : pin design Dataset provided by CEA (France) in the framework of CRP T12031” FUEL MATERIALS FOR FAST REACTORS (FMFR) (2019-2023)”. The data and accompanying documentation are supplied with the understanding that any utilization of these resources sourced from the IAEA fuel database or locally adapted versions thereof, leading to a publication (be it a journal article, conference proceeding, laboratory report, book, etc.), requires the acknowledgment in said publication of both the IAEA fuel database and the data’s respective authors or originating laboratories. Disclaimer Neither the IAEA, nor any of its Member States, nor any person acting either on behalf of the IAEA or its Member States, nor otherwise in furtherance of the activities of the IAEA, assume any liabilities with respect to the use of, or for damage resulting from the use of, any information, method or process disclosed in the distributed material. This applies also to non-Member States and Organizations that have contributed to the distributed information.
Measurements of fallout radioactivity in the North Atlantic region including Faroe Islands and Greenland are reported. Strontium-90, cesium-137 and cesium-134 were determined in samples of precipitation, sea water, vegetation, various foodstuffs (including milk in the FaroesX and drinking water. Estimates are given of the mean contents of 90Sr and 137Cs in human diet in the Faroes and Greenland in 1990 and 1991. 99Tc data on marine samples, in particular sea water from the Greenland Sea, are reported. View on MARIS: * https://maris.iaea.org/explore/type/1/ref/41
Environmental radioactivity in the North Atlantic Region including the Faroe Islands and Greenland. 1990 and 1991
IFA-650.10 (PWR fuel) - Cladding Surface Temperatures
Transfer parameter data are essential inputs to models for radiological environmental impact assessment and are used to quantify the extent of movement of radionuclides from one environmental compartment to another, relevant for estimating the transfer of radionuclides through food chains to humans. International data compilations (i.e. transfer parameter data for temperate environments from the [IAEA Technical Reports Series No. 472](https://www-pub.iaea.org/mtcd/publications/pdf/trs472_web.pdf)) have been frequently used by regulators and professionals in radiological impact assessment for dose estimations when site-specific data are not available. ##Description of Dataset Content This international compilation of radionuclide and stable isotope soil-plant concentration ratio values for tropical environments is an output of [IAEA’s Modelling and Data for Radiological Impact Assessments II (MODARIA II) programme (2016–2019)](https://www-ns.iaea.org/projects/modaria/modaria2.asp) and is based on the Köppen-Geiger climate classification ([BECK et al. 2018](https://www.nature.com/articles/sdata2018214)). The IAEA’s MODARIA II tropical dataset is associated with [IAEA’s TECDOC-1979: Soil-Plant Transfer of Radionuclides in Non-Temperate Environments (2021)](https://www-pub.iaea.org/MTCD/Publications/PDF/TE-1979web.pdf). The dataset contains over 7000 records. Each record includes a concentration ratio value and/or plant and soil concentrations, provided in a consistent way, from which a concentration ratio value can be calculated. Where available, environmentally relevant information is included with each record to allow categorization of the plant and soil data into more refined subsets. The dataset includes information for over 100 plant species, including many that are common crops and staple foods in tropical environments. Data are included for all measured plant compartments, including both the edible and inedible parts of the plant. Information in the dataset is organized into 41 fields, with individual lines in ascending order of their source reference. These headline fields are described in the associated ‘Explanatory Information’ file, while a description of the dataset content can be found in the ‘Dataset content‘ file. ##Use of Data The IAEA’s MODARIA II tropical dataset is freely available for all external users, without prejudice to the applicable [IAEA’ Terms and Conditions.](https://nucleus.iaea.org/Pages/Others/Disclaimer.aspx) Any use of the tropical dataset shall contain appropriate acknowledgement of the data source(s) and the IAEA’s Data Platform [online]. The preferred form of citation of IAEA’s MODARIA II tropical dataset is: INTERNATIONAL ATOMIC ENERGY AGENCY, IAEA’s MODARIA II Soil-Plant Transfer Parameter Dataset for Tropical Environments. In: IAEA Data Platform [online], IAEA, Vienna (2021). https://ckan.iaea.production.datopian.com/dataset/modaria ##Acknowledgement The IAEA wishes to express its gratitude to C. Doering (Australia) for compiling this comprehensive dataset as part of the activities of Working Group 4 of the MODARIA II programme, led by B. Howard (UK). The IAEA also gratefully acknowledges the valuable contributions of J. Twining (Australia) and S. Rout (India). ##How do I Search for Data? The ‘Explore’ tab, on the right corner of the first page, allows users to explore the data online (by selecting the ‘Preview’ tab or by accessing the CSV-type file under ‘Data and Resources’) or to retrieve the whole dataset as a CSV-type file by selecting the ‘Download’ tab. To search for data in the online preview mode, use the filter control panel on the left of the ‘Data Explorer’ page. Click ‘Download’ at the top right of the page to download the data as a CSV file. ##Get Involved Would you like to learn more about the IAEA’s MODARIA II tropical dataset, or do you have questions related to data compilation? Get in touch with the IAEA’s team at the Terrestrial Environmental Radiochemistry Laboratory and at the Assessment and Management of Environmental Releases Unit by accessing the ‘Contact dataset maintainer’ tab. We will get back to you soon.
IAEA’s MODARIA II Soil-Plant Transfer Parameter Dataset for Tropical Environments
Assessment of Contamination in Agriculture
This database is the IAEA’s information system on incidents of illicit trafficking and other unauthorized activities and events involving nuclear and other radioactive material outside of regulatory control. The ITDB was established in 1995 to help participating States and selected international organizations to combat illicit nuclear trafficking and strengthen nuclear security. It facilitates information exchange and provides material that can be used to analyze patterns and trends, thereby helping identify potential security threats and vulnerabilities. The ITDB is also an essential component of the information platform supporting the IAEA’s Nuclear Security Plan 2022-2025. The scope of the information provided through the database is broad. States are encouraged to report a variety of incidents, including those – whether successful, unsuccessful or thwarted – involving the illegal trade and movement of nuclear or other radioactive material across national borders. The ITDB information also covers incidents involving the unauthorized acquisition – for instance through theft, supply, possession, use, transfer or disposal (intentional or unintentional) of nuclear and other radioactive material, with or without crossing international borders. Additionally, the ITDB includes information on the loss of material and the discovery of uncontrolled material, as well as incidents involving the intentional offering for sale of benign material that is purported to be nuclear or otherwise radioactive (in other words, scams). __Groupings of Incident Types__ The ITDB’s Terms of Reference (ToR) require the ITDB to be an authoritative source of information for States and, when appropriate, the media. For this purpose, three groups (Groups I, II and III) are used in order to facilitate the analysis of incidents. Each group is related to Trafficking and Malicious Use. * __GROUP I__ - Confirmed or likely act of Trafficking/Malicious Use or Scam/Fraud (including attempts thereof). Incidents included are those for which sufficient information is provided in the reporting State’s Incident Notification Form (INF) to determine that the incident is, or is likely to be, connected, with Trafficking or Malicious Use. * __GROUP II__ - Undetermined act of Trafficking/Malicious Use (including attempts thereof). Incidents included are those for which there is insufficient information provided in the reporting State’s INF to determine that the incident is, or is likely to be, either connected or unconnected with Trafficking or Malicious Use. * __GROUP III__ - Confirmed or likely absence of an act of Trafficking/Malicious Use (including attempts thereof). Incidents included are those for which sufficient information is provided in the reporting States’ INF, to determine that the incident is not, or is unlikely to be, connected, with Trafficking or Malicious Use.
Incident and Trafficking Database (ITDB)
Measurements of fallout radioactivity in the North Atlantic region including Faroe Islands and Greenland are reported. Strontium-90, cesium-137 and cesium-134 were determined in samples of precipitation, sea water, vegetation, various foodstuffs (including milk in the Faroes), and drinking water. Estimates are given of the mean contents of 90Sr and 137Cs in human diet in the Faroes and Greenland in 1987. 99Tc data on marine samples are reported. Data on plutonium and americium in sediments and biota collected at Thuk in 1984 are presented. 1987 View on MARIS: * https://maris.iaea.org/explore/type/1/ref/44
Environmental Radioactivity in the North Atlantic Region including the Faroe Islands and Greenland 1987
Irradiation Histories Axial Node6 275mmBFC
Thermohydraulic Boundary Conditions for Simulation were developed in the framework of IAEA Coordinated Research Project (CRP) “Fuel Modelling in Accident Conditions” (FUMAC, IAEA-TECDOC-1889) project partner for three Halden LOCA tests: • IFA-650.9 (PWR fuel) • IFA-650.10 (PWR fuel) • IFA-650.11 (VVER fuel) and calculated by the integral code SOCRAT/V3
Thermohydraulic Boundary Conditions for Simulation
#Cases from the AEKI Database proposed for the FUMAC exercise Tests with unirradiated, unoxidised Zircaloy-4 tubes will be simulated by the interested participants. These tests can be found in the report and in the database under the name PUZRY. The present zip file includes, apart from this document, * the report describing the entire database (E110_database_2012.pdf), * the on-line measurements for the 31 Zircaloy-4 tests (folder EXP), * the pictures of the samples after the tests (folder PICS). All 31 tests are included. The pressure increase rate during a large break LOCA is nowadays between 2 and 4 bar/s, but the highest pressure increase rates in the tests were 1 order of magnitude lower. We would therefore recommend to simulate the tests with the highest pressure increase rates, one every 100 °C, which would also help avoid the effect of creep. These are * PUZRY-26 (700 °C, 0.119 bar/s), * PUZRY-30 (800 °C, 0.263 bar/s), * PUZRY-18 (900 °C, 0.115 bar/s), * PUZRY-8 (1000 °C, 0.076 bar/s), * PUZRY-10 (1100 °C, 0.071 bar/s), * PUZRY-12 (1200 °C, 0.072 bar/s). The report and the file EXP\PUZRY.PRN include the summary of the tests (geometry, temperature, pressure increase rate). These are sufficient to prepare the input. The on-line measurements can also be used, but care must be taken with the interpretation of the burst time as the tests start from vacuum and not from atmospheric pressure. Caution! * The given pressure values (including burst pressures) are overpressures. * Time to burst is measured from the point where the rod internal pressure reaches the outer pressure (interpolated to find the exact instant). * The files with the extension exp contain the detailed measured data, however, these also include wrong measurements (negative absolute pressures, non-realistic pressure drops, etc.), so some pre-processing is required. * The measured tangential deformation includes the slit at the burst, the pictures can be used to determine the actual deformation of the cladding. If anything is unclear or you need more information, please don’t hesitate to contact kulacsy.katalin@energia.mta.hu The data and accompanying documentation are supplied with the understanding that any utilization of these resources sourced from the IAEA fuel database or locally adapted versions thereof, leading to a publication (be it a journal article, conference proceeding, laboratory report, book, etc.), requires the acknowledgment in said publication of both the IAEA fuel database and the data’s respective authors or originating laboratories. Disclaimer Neither the IAEA, nor any of its Member States, nor any person acting either on behalf of the IAEA or its Member States, nor otherwise in furtherance of the activities of the IAEA, assume any liabilities with respect to the use of, or for damage resulting from the use of, any information, method or process disclosed in the distributed material. This applies also to non-Member States and Organizations that have contributed to the distributed information.
The Halden Reactor test series IFA-650 was part of the joint international programme of the Halden Reactor Project. These tests addressed the LOCA performance of high burnup fuel irradiated in commercial nuclear power plants. IFA-650.11 (VVER fuel): little ballooning and fuel fragmentation were indicated. The fuel, manufactured by JSC TVEL, was supplied by Fortum Nuclear Services Ltd (Finland). The VVER-440 fuel segment had been irradiated in the Finnish Loviisa NPP to a burnup of 56.0 MWd/kgU. The LOCA test was performed at a rod heat rating of 24 W/cm for a target peak cladding temperature (PCT) of 1273 K. The rod failed in 207 s after the start of blow-down.
This study aims to assess the committed effective dose due to the intake of 210Po from the consumption of ﬁsh in Arabian Gulf countries. Twenty different kinds of ﬁsh, which represent the most common ﬁsh species consumed in the Arabian Gulf countries, were analyzed using alpha spectrometer technique. 210Po activity concentrations in ﬁsh samples were found to vary over a wide range from 0.1 to 14.7 Bq kg-1 fresh weight. This variation of 210Po concentrations between various type of ﬁsh samples might be attributed to the feeding type pattern and the size of ﬁsh. The annual committed effective dose due to ingestion of 210Po in ﬁsh species for adults in the Arabian Gulf countries was estimated and found to vary from 38 μSv in Bahrain to 85 μSv in Oman with an average value of 59 μSv. These values are considered relatively high compared to those reported in some other regions. However, it is still much lower than the world average ingestion dose due to natural radiation sources. View on Maris: * https://maris.iaea.org/explore/type/2/ref/500
Assessment of the committed effective dose due to the 210Po intake from fish consumption for the Arabian Gulf population
METAPHIX-1 pin 1 data for IAEA FMFR rev1.xlsx
Outline of the METAPHIX program and the post-irradiation examination data described below are published in Refs. [1-10]. METAPHIX is the collaborative program between CRIEPI and the European Commission Joint Research Centre - Karlsruhe (JRC-Karlsruhe) being conducted to understand the irradiation behavior of fast reactor metal fuel containing minor actinides (MAs: Np, Am, Cm) and demonstrate the MA transmutation performance in fast reactors. In this program, metallic fuel pins that contain U-Pu-Zr-MA alloys were fabricated at JRC - Institute for Transuranium Elements (JRC-ITU, currently JRC Karlsruhe) and irradiated in the Phénix fast reactor up to three different burnups, approximately 2.5at.% (METAPHIX-1), 7at.% (METAPHIX-2) and 10at.% (METAPHIX-3), with the support of the Commissariat a l´Energie Atomique et aux Energies Alternatives (CEA, France). Since the MAs to be recovered pyrometallurgically from spent fuels entrain comparable amounts of rare earth fission products due to their chemical affinities, the effect of the contamination of MAs with REs should be examined. The characterization of U-Pu-Zr alloys containing MAs and rare earth elements (REs) indicated that practically homogeneous fuel alloys can be prepared provided that the total content of REs is limited to 5 wt.% or less. Based on this characterization result, three MA-bearing fuel alloys, U-19Pu-10Zr-2MA-2RE, U-19Pu-10Zr-5MA-5RE and U-19Pu-10Zr-5MA (wt.%), were selected along with a standard ternary fuel alloy, U-19Pu-10Zr, for the irradiation experiment. In the METAPHIX program, Np, Am and Cm were used as MAs, and Y, Ce, Nd and Gd were used as REs. Three metal fuel pins, two of which include MA-containing alloy segments of 100mm length in the U-19Pu-10Zr fuel stacks, were fabricated. The total length of the active fuel was 485mm. The cladding material was 15-15Ti austenitic steel and the fuel-cladding gap was filled with sodium for thermal bonding. ## References [1] Paxton, M.M., et al., Comparison of the in-reactor creep of selected ferritic, solid solution strengthend, and precipitation hardened commercial alloys. Journal of Nuclear Materials, 1979. 80(1): p. 144-151. [2] Paxton, M.M., B.A. Chin, and E.R. Gilbert, The in-reactor creep of selected ferritic, solid solution strengthened, and precipitation hardened alloys. Journal of Nuclear Materials, 1980. 95(1–2): p. 185-192. [3] Straalsund, J.L., R.W. Powell, and B.A. Chin, An overview of neutron irradiation effects in LMFBR materials. Journal of Nuclear Materials, 1982. 108–109(0): p. 299-305. [4] Straalsund, J.L. and D.S. Gelles, Assessment of the Performance of the Martensitic alloy HT-9 for Fast Breeder Reactor Applications. Topical Conference On Ferritic Alloys For Use In Nuclear Energy Technologies, 1983. [5] Puigh, R.J. and G.L. Wire, In-reactor Creep Behavior of Selected Ferritic Alloys. Preceedings of Topical Conference on Ferritic Alloys for Use in Nuclear Energy Technologies, 1984. [6] Chin, B.A., Analysis of the Creep Properties of a 12Cr-1 Mo-W-V Steel. 1984: p. 593-599. [7] Huet, J.-J., et al., Swelling of ferritic steels irradiated in fast reactors. Irradiation Behavior of Metallic Materials for Fast Reactor Core Components, 1979: p. 5-9. [8] Puigh, R.J. and F.A. Garner, Irradiation Creep Behavior of the Fusion Heats of HT-9 and Modified 9Cr-1Mo. Effects of Radiation Materials: Fourteenth International Symposium. [9] Garner, F.A. and R.J. Puigh, Irradiation creep and swelling of the fusion heats of PCA, HT9 and 9Cr-1Mo irradiated to high neutron fluence. Journal of Nuclear Materials, 1991. 179–181, Part 1(0): p. 577-580. [10] Toloczko, M.B., et al. Variability of Irradiation Creep and Swelling of HT9 irradiated to high Neutron Fluence at∼400°C to 600°C, Effects of Radiation Materials: Eighteenth International Symposium 1999, 765. Dataset provided by CRIEPI (Japan) and the European Commission Joint Research Centre - Karlsruhe (JRC-Karlsruhe) in the framework of IAEA CRP T12031” FUEL MATERIALS FOR FAST REACTORS (FMFR) (2019-2023)”.
QL1_rod15_clad strain with opening consideration.xlsx
This paper represents the ﬁrst work on the concentrations of heavy elements, physiochemical characteristics and activity levels of the naturally occurring radionuclides in the Saudi Arabian coastline of the Gulf of Aqaba. Concentrations of 19 heavy elements were measured, namely: Ag, Al, As, Ba, Be, Cd, Co, Cr, Cu, Fe, Hg, Mn, Mo, Ni, Pb, Sb, Se, V and Zn. The radioactivity levels of 238U, 232Th and 40K were estimated to be: 17 ± 1.7, 22.5 ± 3.7 and 649.6 ± 64.2 Bq kg-1, respectively. The measurements were carried out using inductively coupled plasmamass spectrometry (ICP-MS). In addition, physiochemical characteristics of 19 sediment samples (i.e., saturation percentage, pH, electrical conductivity, organic matter, cation exchange capacity and content of clay, silt and sand) have been determined. Indications for high correlation between most heavy elements are found. The correlation between heavy elements and the radionuclides 238U, 232Th and 40K was generally signiﬁcant. View on MARIS: * https://maris.iaea.org/explore/type/3/ref/429
Heavy elements concentrations, physiochemical characteristics and natural radionuclides levels along the Saudi coastline of the Gulf of Aqaba
The dataset provided by IGCAR (India) in the framework of IAEA CRP T12031” FUEL MATERIALS FOR FAST REACTORS (FMFR) (2019-2023)”. Datasets of the irradiation test carried out in FBTR to study the performance of MOX fuel composition and pin dimensions with shorter length. For the test, configuration was chosen with a 37-fuel pin bundle cluster in a FBTR Subassembly. The MOX fuel pin was irradiated at a peak Linear Heat Rating (LHR) of 450 W/cm and the peak burn-up was 112 GWd/t. Fuel used is having 29% PuO2 & U in UO2 is enriched with 53.5% U-233 to simulate the LHR. The fuel pin clad OD was 6.6 mm and ID was 5.7 mm. The fuel pellets were 5.56 mm in OD with a central hole diameter of 1.8 mm. Active fuel column length was 240 mm as against 320 mm for FBTR fuel column. Top of the fissile column of the test pin was in level with the top of the FBTR core. Pin No.: 0041 is selected for the benchmark analysis in the CRP FMFR.
Ausgewählte Messstellen-Liste: C:\MST_Liste\QUENCH_L1.mst Start neue Messung:02.02.2012 11:00:00Uhr Aufzeichnungsfrequenz: 1.000000 Hz
210Po in the daily diet in Korea was analyzed and the ingestion dose from an intake of 210Po was estimated by considering the dietary habit of a Korean person. The 210Po concentrations of a leafy vegetable (0.36 Bq·kg−1 for lettuce) in the terrestrial food were higher than those of grain, whereas Chinese cabbage had a lesser 210Po concentration (0.019 Bq·kg−1). The 210Po concentration of the animal product was similar to those detected in the grain and vegetable. The 210Po concentrations in the shell and crustaceous were high from 19.1 to 33.0 Bq·kg−1, however, its value fell in the overall range of the reported values. The effective dose from 210Po for an adult from the Korean population was about 269.4 μSv·y−1. Nearly 80% of the ingestion dose from the intake of 210Po was attributed to the consumption of seafood. It suggests that the marine food ingestion is a critical pathway for natural 210Po to the Korean population. View on MARIS: * https://maris.iaea.org/explore/type/2/ref/257
Assessment of 210Po in foodstuffs consumed in Korea
Radionuclide concentration in commercial fish species of Kuwait has been determined primarily with the intention of creating the baseline for ²¹⁰Po, ¹³⁷Cs, ⁴⁰K, ²²⁶Ra, ²²⁴Ra, ²²⁸Ra, and ⁹⁰Sr. This baseline information can be useful for issuing food advisories and determining annual intakes and radiation doses due to fish consumption. The highest fresh weight concentration of ²¹⁰Po and ⁹⁰Sr was in Battan and the lowest in Sobaity. Highest fresh weight ⁴⁰K concentration was observed in Meid and the lowest in Battan. The ²²⁴Ra, ²²⁶Ra and ²²⁸Ra concentrations were highest in Meid, whereas the lowest was in Nuwaibi. In all the collected fish samples, ¹³⁷Cs was below the detection limit. View on MARIS: * https://maris.iaea.org/explore/type/2/ref/241
Baseline radionuclide specific activity in commercial fishes of Kuwait
Measurements of fallout radioactivity in the North Atlantic region including Faroe Islands and Greenland are reported. Strontium-90, cesium-137 and cesium-134 were determined in samples of precipitation, sea water, vegetation, various foodstuffs (including milk in the Faroes), and drinking water. Estimates are given of the mean contents of 90Sr and 137Cs in human diet in the Faroes and Greenland in 198S and 1989. 99Tc data on marine samples, in particular sea wate from the Greenland Sea, are reported. 1988, 1989 View on MARIS: * https://maris.iaea.org/explore/type/1/ref/31
Environmental radioactivity in the North Atlantic Region including the Faroe Islands and Greenland. 1988 and 1989
ATF Open Sources Material Properties Database
IFA-650.11 (VVER fuel) - Coolant Temperatures
Concentrations of Ra, Th, U, K and Cs were determined in whole soft tissues (WST) and shells of groups of di!erent size of marine mussel Perna viridis L. and estuarine mussel Modiolus striatulus H. and water samples which were collected from the southern coast of Bangladesh. Correlation analysis showed that the concentrations of radionuclides vary with mussel size. A positive correlation existed for U and K and a negative one for Th between the radionuclide concentration and mussel size; Th concentrations in WST and shells of the mussels showed an inverse relationship with those of U and K, while U showed positive correlation with K. The concentration factors (CF) for Ra, Th and U in both P. viridis and M. striatulus were higher than those for K. The contents of Cs in both mussels were below the detection limit. 1999 Elsevier Science Ltd. All rights reserved. View on MARIS: * https://maris.iaea.org/explore/type/1/ref/486 * https://maris.iaea.org/explore/type/2/ref/486
Radionuclide concentrations in mussels collected from the southern coast of Bangladesh
IFA-650.11 (VVER fuel) - Total Heat Flux from Cladding Surface
Journal of Nuclear Materials 323 (2003) 108–122
In the framework of the IAEA CRP “Testing and Simulation for Advanced Technology and Accident Tolerant Fuels (ATF-TS)” project testing of different cladding materials was carried out in order to characterize the behaviour of candidate materials and compare the new measured data with the parameters of traditional cladding alloys. The database includes the results of following separate effect tests: • ballooning and burst, • oxidation in high temperature steam, • tensile tests with ring samples, • ring compression tests, • mandrel tests, • SEM examinations.
Database of separate effect tests carried out at HUN-REN EK with cladding samples provided by IAEA CRP “ATF-TS” partners
MADB is a bibliographic database on physico-chemical properties of selected Minor Actinide compounds and alloys. The materials and properties are selected based on their importance in the advanced nuclear fuel cycle options. This list is updated up to 2008.
Marine organism samples were collected from different regions of India. The edible portions after drying and homogenizing kept for 1 month to achieve equilibrium between Radium and its daughter products, were analysed by gamma spectrometry using 50 % HPGe. 226Ra activity was found to be in the range of <0.07–0.736 Bq kg-1 (wet) and 228Ra in the range of <0.082–2.5 Bq kg-1. 228Ra and 226Ra concentrations in different species of organism were different even in the same marine environment. To assess the impact of this activity to human, ingestion dose due to consumption of organisms was calculated and the maximum dose of 2.8 μSv year-1 due to 226Ra and 25.24 μSv year-1 due to 228Ra was observed. View on MARIS: * https://maris.iaea.org/explore/type/2/ref/263
226Ra and 228Ra in consumable marine organisms from different coastal regions of India
Background: Po210 can be accumulated in various environmental materials, including marine organisms, and contributes to the dose of natural radiation in seafood. The concentration of this radionuclide in the marine environment can be influenced by the operation of a coal burning power plant but existing studies regarding this issue are not well documented. Therefore, the aim of this study was to estimate the Po210 concentration level in marine organisms from the coastal area of Kapar, Malaysia which is very near to a coal burning power plant station and to assess its impact on seafood consumers. Methods: Concentration of Po210 was determined in the edible muscle of seafood and water from the coastal area of Kapar, Malaysia using radiochemical separation and the Alpha Spectrometry technique. Results: The activities of Po210 in the dissolved phase of water samples ranged between 0.51 ± 0.21 and 0.71 ± 0.24 mBql-1 whereas the particulate phase registered a range of 50.34 ± 11.40 to 72.07 ± 21.20 Bqkg-1. The ranges of Po210 activities in the organism samples were 4.4 ± 0.12 to 6.4 ± 0.95 Bqkg-1 dry wt in fish (Arius maculatus), 45.7 ± 0.86 to 54.4 ± 1.58 Bqkg-1 dry wt in shrimp (Penaeus merguiensis) and 104.3 ± 3.44 to 293.8 ± 10.04 Bqkg-1 dry wt in cockle (Anadara granosa). The variation of Po210 in organisms is dependent on the mode of their life style, ambient water concentration and seasonal changes. The concentration factors Background: Po210 can be accumulated in various environmental materials, including marine organisms, and contributes to the dose of natural radiation in seafood. The concentration of this radionuclide in the marine environment can be influenced by the operation of a coal burning power plant but existing studies regarding this issue are not well documented. Therefore, the aim of this study was to estimate the Po210 concentration level in marine organisms from the coastal area of Kapar, Malaysia which is very near to a coal burning power plant station and to assess its impact on seafood consumers. Methods: Concentration of Po210 was determined in the edible muscle of seafood and water from the coastal area of Kapar, Malaysia using radiochemical separation and the Alpha Spectrometry technique. Results: The activities of Po210 in the dissolved phase of water samples ranged between 0.51 ± 0.21 and 0.71 ± 0.24 mBql-1 whereas the particulate phase registered a range of 50.34 ± 11.40 to 72.07 ± 21.20 Bqkg-1. The ranges of Po210 activities in the organism samples were 4.4 ± 0.12 to 6.4 ± 0.95 Bqkg-1 dry wt in fish (Arius maculatus), 45.7 ± 0.86 to 54.4 ± 1.58 Bqkg-1 dry wt in shrimp (Penaeus merguiensis) and 104.3 ± 3.44 to 293.8 ± 10.04 Bqkg-1 dry wt in cockle (Anadara granosa). The variation of Po210 in organisms is dependent on the mode of their life style, ambient water concentration and seasonal changes. The concentration factors calculated for fish and molluscs were higher than the recommended values by the IAEA. An assessment of daily intake and received dose due to the consumption of seafood was also carried out and found to be 2083.85 mBqday-1person-1 and 249.30 μSvyr-1 respectively. These values are comparatively higher than reported values in other countries. Moreover, the transformation of Po210 in the human body was calculated and revealed that a considerable amount of Po210 can be absorbed in the internal organs. The calculated values of life time mortality and morbidity cancer risks were 24.8 × 10-4 and 34 × 10-4 respectively which also exceeded the recommended limits set by the ICRP. Conclusions: The findings of this present study can be used to evaluate the safety dose uptake level of seafood as well as to monitor environmental health. However, as the calculated dose and cancer risks were found to cross the limit of safety, finding a realistic way to moderate the risk is imperative. View on MARIS: * https://maris.iaea.org/explore/type/2/ref/259
A series of single rod tests (S1 to S13) and 3x3 bundle tests (B1 to B7) with three types of fuel claddings (Zircaloy 4, Opt. ZIRLO, and E110) coated with Cr or Cr/CrN were inductively heated under conditions simulating DEC LOCA scenarios using an induction heating furnace at the DEGREE facility of CRIEPI, Japan, in the framework of the IAEA CRP ATF-TS project [1-3]. The boundary conditions were not adiabatic due to absence of surrounding heat insulation, what caused noticeable radial temperature gradient in the bundle. The peak cladding temperatures reached were either 1350°C, 1500°C or 1600°C. Several rods were pressurized to 6 MPa, the rest was not pressurized. The test scenario included four stages: pre-heating to 500 °C, conditioning at 500 °C, heat-up in steam/Ar mixture to the pre-determined temperatures with heating rate 3-5 K/s, and cool-down in Ar. Post-test analysis was conducted to reveal interdiffusion layer structure formed at the interface between the coating and Zr alloy substrate containing Cr, Zr, oxygen, and hydrogen, radial profile of micro-Vickers hardness, and ballooning and bursting behaviour. Datasets are provided here for one single rod test (S3) and one bundle test (B3), in which 20 µm Cr-coated Zircaloy-4 cladding tubes were pressurized to 6 MPa and heated in an Ar/Steam atmosphere to a maximum temperature of 1350 °C.
CRIEPI - DEGREE Single Rod and Bundle Tests
IFA-650.9 (PWR fuel) - Cladding Surface Temperatures
METAPHIX-2 #1 data for IAEA FMFR ver1.xlsx
ATF-TS Burst Test Research Report EK-FRL-2024-120-1-1-M0
Outline of the METAPHIX program and the post-irradiation examination data described below are published in Refs. [1-10], METAPHIX is the collaborative program between CRIEPI and the European Commission Joint Research Centre - Karlsruhe (JRC-Karlsruhe) being conducted to understand the irradiation behavior of fast reactor metal fuel containing minor actinides (MAs: Np, Am, Cm) and demonstrate the MA transmutation performance in fast reactors. In this program, metallic fuel pins that contain U-Pu-Zr-MA alloys were fabricated at JRC - Institute for Transuranium Elements (JRC-ITU, currently JRC Karlsruhe) and irradiated in the Phénix fast reactor up to three different burnups, approximately 2.5at.% (METAPHIX-1), 7at.% (METAPHIX-2) and 10at.% (METAPHIX-3), with the support of the Commissariat a l´Energie Atomique et aux Energies Alternatives (CEA, France). Since the MAs to be recovered pyrometallurgically from spent fuels entrain comparable amounts of rare earth fission products due to their chemical affinities, the effect of the contamination of MAs with REs should be examined. The characterization of U-Pu-Zr alloys containing MAs and rare earth elements (REs) indicated that practically homogeneous fuel alloys can be prepared provided that the total content of REs is limited to 5 wt.% or less. Based on this characterization result, three MA-bearing fuel alloys, U-19Pu-10Zr-2MA-2RE, U-19Pu-10Zr-5MA-5RE and U-19Pu-10Zr-5MA (wt.%), were selected along with a standard ternary fuel alloy, U-19Pu-10Zr, for the irradiation experiment. In the METAPHIX program, Np, Am and Cm were used as MAs, and Y, Ce, Nd and Gd were used as REs. Three metal fuel pins, two of which include MA-containing alloy segments of 100mm length in the U-19Pu-10Zr fuel stacks, were fabricated. The total length of the active fuel was 485mm. The cladding material was 15-15Ti austenitic steel and the fuel-cladding gap was filled with sodium for thermal bonding. The specification of METAPHIX-2#1 fuel pin is identical to that of METAPHIX-1#1 fuel pin. References [1] Paxton, M.M., et al., Comparison of the in-reactor creep of selected ferritic, solid solution strengthend, and precipitation hardened commercial alloys. Journal of Nuclear Materials, 1979. 80(1): p. 144-151. [2] Paxton, M.M., B.A. Chin, and E.R. Gilbert, The in-reactor creep of selected ferritic, solid solution strengthened, and precipitation hardened alloys. Journal of Nuclear Materials, 1980. 95(1–2): p. 185-192. [3] Straalsund, J.L., R.W. Powell, and B.A. Chin, An overview of neutron irradiation effects in LMFBR materials. Journal of Nuclear Materials, 1982. 108–109(0): p. 299-305. [4] Straalsund, J.L. and D.S. Gelles, Assessment of the Performance of the Martensitic alloy HT-9 for Fast Breeder Reactor Applications. Topical Conference On Ferritic Alloys For Use In Nuclear Energy Technologies, 1983. [5] Puigh, R.J. and G.L. Wire, In-reactor Creep Behavior of Selected Ferritic Alloys. Preceedings of Topical Conference on Ferritic Alloys for Use in Nuclear Energy Technologies, 1984. [6] Chin, B.A., Analysis of the Creep Properties of a 12Cr-1 Mo-W-V Steel. 1984: p. 593-599. [7] Huet, J.-J., et al., Swelling of ferritic steels irradiated in fast reactors. Irradiation Behavior of Metallic Materials for Fast Reactor Core Components, 1979: p. 5-9. [8] Puigh, R.J. and F.A. Garner, Irradiation Creep Behavior of the Fusion Heats of HT-9 and Modified 9Cr-1Mo. Effects of Radiation Materials: Fourteenth International Symposium. [9] Garner, F.A. and R.J. Puigh, Irradiation creep and swelling of the fusion heats of PCA, HT9 and 9Cr-1Mo irradiated to high neutron fluence. Journal of Nuclear Materials, 1991. 179–181, Part 1(0): p. 577-580. [10] Toloczko, M.B., et al. Variability of Irradiation Creep and Swelling of HT9 irradiated to high Neutron Fluence at∼400°C to 600°C, Effects of Radiation Materials: Eighteenth International Symposium 1999, 765. Dataset provided by CRIEPI (Japan) and the European Commission Joint Research Centre - Karlsruhe (JRC-Karlsruhe) in the framework of IAEA CRP T12031” FUEL MATERIALS FOR FAST REACTORS (FMFR) (2019-2023)”. The data and accompanying documentation are supplied with the understanding that any utilization of these resources sourced from the IAEA fuel database or locally adapted versions thereof, leading to a publication (be it a journal article, conference proceeding, laboratory report, book, etc.), requires the acknowledgment in said publication of both the IAEA fuel database and the data’s respective authors or originating laboratories. Disclaimer Neither the IAEA, nor any of its Member States, nor any person acting either on behalf of the IAEA or its Member States, nor otherwise in furtherance of the activities of the IAEA, assume any liabilities with respect to the use of, or for damage resulting from the use of, any information, method or process disclosed in the distributed material. This applies also to non-Member States and Organizations that have contributed to the distributed information.
The Halden Reactor test series IFA-650 was part of the joint international programme of the Halden Reactor Project. These tests addressed the LOCA performance of high burnup fuel irradiated in commercial nuclear power plants. IFA-650.9 (PWR fuel): considerable ballooning, fuel fragmentation and relocation, when subjected to LOCA were indicated. The fuel was provided by Framatome ANP and had been irradiated in the Swiss NPP Gösgen to 89.9 MWd/kgU. The rod power was set to 25 kW/m to achieve a target peak cladding temperature of 1100°C. Due to fuel relocation, the temperature measured with the lower cladding thermocouple approached 1200°C, and the test was terminated to avoid even higher temperatures. Cladding failure occurred at about 800°C, which was 130 s after the start of blow-down. A special feature of this experiment is the strong fuel fragmentation, relocation and dispersal.
QL1 rod 4 profilometry_strain and average diameter.xlsx
Total (radiative+convective) Heat Flux from Cladding Surface (W/m) : Qloss_09125 at 912.5 mm, etc.
IFA-650.9 (PWR fuel) - Total Heat Flux from Cladding Surface
Irradiation Histories Axial Node5 225mmBFC
ATF SEM Cr Coated Zr Cross Research Report EK-FRL-2021-120-1-2-M0
The SUPERFACT experiment was implemented during the 1980s by two institutions, the French Commissariat à l’énergie atomique et aux énergies alternatives (CEA) and the European Commission’s Joint Research Centre (JRC) in Karlsruhe, the former Institute for Transuranium Elements (ITU) [1],[2],[3],[4]. The process of irradiation took place within the PHÉNIX reactor, France, during the years 1986 to 1988, and the program's primary objective was to demonstrate the technical viability of performing transmutation of Minor Actinides (MA) in fast reactors using a homogeneous and a heterogeneous approach. The test capsule was comprised of four (Pu,U,MA)O2-x pins with pellets that contained either 2% Am-241 or 2% Np-237, signifying the homogeneous transmutation concept, and four (U,MA)O2-x pins with either 45% Np-237 or a mix of 20% Am-241 + 20% Np-237, representing the heterogeneous transmutation concept. The fuels were synthesized at JRC Karlsruhe using the external sol-gel process [2],[4],[5], illustrated in the flow diagram below. The procedure involves the integration of polymers into the base solution to enhance its viscosity. Once the solution is dispersed into droplets, they solidify upon collection in an ammonia bath. The resultant beads undergo a process of washing, drying, and calcination, followed by being pressed into pellets and sintered at a temperature of 1600°C in an Ar-5%H2 atmosphere for a duration of 6 hours. This entire process was conducted in the JRC Karlsruhe laboratory. ![Fig. 1 ](https://data.iaea.org/uploads/page_images/2024-03-12-101300.459172Picture1.png) Fig. 1 Process flow diagram for Sol-gel synthesis used for SUPERFACT [2],[4],[5] SUPERFACT Pins 4 & 16 irradiation data Table 1 presented below highlights the primary characteristics of the sintered pellets of all four fuel compositions. Within the context of this report, we examine the irradiation behaviour of the fuel composed of (U0.74Pu0.24Am0.02)O2 (Pins number 4 and 16). The O/M ratio of pin 4 & 16 was determined to 1.957 and the density to 96.8 %TD. The detailed isotopic composition of pins 4 and 16 is summarized in Table 2. Table 2.1.5-1 Properties of SUPERFACT fuel pellets [4],[5] ![Table 2.1.5-1](https://data.iaea.org/uploads/page_images/2024-03-12-102234.794466Screenshot-2024-03-12-111720.png) ![Table 2.1.5-2](https://data.iaea.org/uploads/page_images/2024-03-12-102253.497057Screenshot-2024-03-12-111703.png) Pins number 4 and 16, exhibiting a homogeneous composition with 2% Am, underwent an irradiation process for a span of 448 days, encompassing 382 effective full power days (EFPD), culminating in a burn-up of 6.4 atomic percent (at%). The pins were irradiated in the internal core of the Phénix reactor together with 6 other experimental pins and 8 standard Phénix MOX pins in a hexagonal fuel assembly which is illustrated in Fig. 2 [5]. Since both pins were irradiated in a symmetric configuration within the same hexagonal fuel assembly, they are assumed to be equivalent in irradiation history and performance. ![Fig. 2](https://data.iaea.org/uploads/page_images/2024-03-12-101319.884799Picture2.png) Fig. 2 Position of experimental pins 4 & 16 in fuel assembly [5] ## References [1] L. L Gilpin, R. B. Baker, S. A. Chastain, “Evaluation of the Advanced Mixed Oxide Fuel Test FO-2 Irradiated in Fast Flux Test Facility,” WHC-SA-0498, 1989. [2] Melissa Teague, Brian Gorman, Jeffrey King, Douglas Porter, Steven Hayes, “Microstructural characterization of high burn-up mixed oxide fast reactor fuel,” Journal of Nuclear Materials 441 (2013) 267–273. [3] A.E. Bridges, A.E. Walter, R.D. Leggett, R.B. Baker, Nucl. Technol. 102 (1993) 353–366. [4] C. Prunier et al. (1993), “Some specific aspects of homogeneous Am and Np based fuel transmutation through the outcomes of the SUPERFACT Experiment in Phénix”, Global 1993, September 1993, Seattle, United States. [5] Chauvin, N., Minato, K., Ogata, T., Lee, C. B., Pouchon, M. A., Pasamehmetoglu, K. O., Somers J., ... & McClellan, K. (2014). State-of-the-art Report on Innovative Fuels for Advanced Nuclear Systems. Dataset provided by the French Commissariat à l’énergie atomique et aux énergies alternatives (CEA) and the European Commission’s Joint Research Centre (JRC) in Karlsruhe in the framework of CRP T12031” FUEL MATERIALS FOR FAST REACTORS (FMFR) (2019-2023)”. The data and accompanying documentation are supplied with the understanding that any utilization of these resources sourced from the IAEA fuel database or locally adapted versions thereof, leading to a publication (be it a journal article, conference proceeding, laboratory report, book, etc.), requires the acknowledgment in said publication of both the IAEA fuel database and the data’s respective authors or originating laboratories. Disclaimer Neither the IAEA, nor any of its Member States, nor any person acting either on behalf of the IAEA or its Member States, nor otherwise in furtherance of the activities of the IAEA, assume any liabilities with respect to the use of, or for damage resulting from the use of, any information, method or process disclosed in the distributed material. This applies also to non-Member States and Organizations that have contributed to the distributed information.
Radiological analysis was carried out on fish, crustacean and sediment samples collected from both fresh and marine water of river Igbokoda in the coastal area of Ondo State, Nigeria. The activity concentrations of radionuclides were determined using gamma spectrometry method. The means of the annual effective ingestion dose varied between 23.3 ± 10.2 μSv.y-1 (OreochromisniloticusandGymnarchusniloticus) and 34.8 ± 1.7 μSv.y-1 (Parachnnaobscura) for fresh water fish samples and 6.4 ± 0.7 μSv.y-1 (Chrysithctysnigrodigitatus) and 14.2 ± 1.6 μSv.y-1 (Cynoglossussenegalensis) for marine water fish samples. That of the crustacean samples (Peanusmonodon) was 2.4 ± 0.2 μSv.y-1. The equivalent dose to the skin of humans from contact with sediment was 2.0 μSv.y-1 and 1.2 μSv.y-1 for the fresh and marine water sediments, respectively. The effective dose was calculated as 0.010 μSv.y-1 and 0.006 μSv.y-1 for the fresh and marine water sediments, respectively. The equivalent doses obtained are less than the ICRP recommended 50mSv per annum for the public. View on MARIS: * Biota View: https://maris.iaea.org/explore/type/2/ref/343 * Sediment View: https://maris.iaea.org/explore/type/3/ref/343
Radiological analysis of 40K, 226Ra and 232Th in fish, crustacean and sediment samples from fresh and marine water in oil exploration area of Ondo State, Nigeria
Concentrations of 210Po and 210Pb were determined in the edible muscle tissue of 36 species of marine fish and seven species of fresh water fish collected from Syrian local markets. Concentrations in sea fish were found to vary between 0.27 and 27.48Bqkg−1 fresh wt and 0.05–0.38Bqkg−1 fresh wt for 210Po and 210Pb, respectively. On the other hand, in fresh water fish, the concentrations were relatively low and varied between 0.61 and 3.08Bqkg−1 fresh wt for 210Po and 0.04 to 0.10Bqkg−1 fresh wt for 210Pb. These variations in 210Po and 210Pb content in different species are due to differences in metabolism and feeding patterns. However, the highest levels were observed in Euthynnus alletteratus and Sardinella sp collected from different markets. The daily levels of intake due to fish consumption containing 210Po and 210Pb were calculated and found to be 6.0 and 0.24mBq respectively, which are much lower than those reported in other countries. In addition, the collective doses were found to be 5.09 and 2.93man.Sv for 210Po and 210Pb respectively. This suggests that the dose received by Syrians due to consumption of sea and river fish is rather small. View on MARIS: * https://maris.iaea.org/explore/type/2/ref/266
210 Po and 210 Pb concentrations in fish consumed in Syria
Concentrations of 210Po were determined in the edible muscle tissue of ﬁve species of marine ﬁsh: Sardine (Sardine plichardus) and Anchovy (Engraulis encrasicolus), Red mullet (Mullus barbatus), Horse mackerel (Trachurus trachurus) and Gilt-head sea bream (Sparus aurata) collected from ﬁve stations in the Aegean Sea Region of Turkey during the ﬁshery season 2010. The 210Po concentrations in the ﬁsh samples were found to vary from not detected levels to 389 Æ 45 Bq kgÀ1 dry wt. These variations in 210Po content in different species are probably due to differences in metabolism and feeding patterns. The highest levels for 210Po were observed in Anchovy (E. encrasicolus) species. ###Additional Information * Location in Archive: 123 * View on MARIS: https://maris.iaea.org/explore/type/1/ref/44
Levels of 210Po in some commercial fish species consumed in the Aegean Sea coast of Turkey and the related dose assessment to the coastal population
Report_KIT-SR_7571__Commissioning_QUENCH-L0__Zry4 (1).pdf
Irradiation Histories Axial Node2 75mmBFC
Irradiation Histories Axial Node8 375mmBFC
EK Oxidation Tests Research Report EK-FRL-2023-120-1-2-M1
View on MARIS: * https://maris.iaea.org/explore/type/2/ref/437
Concentrations of 210Po and 210Pb in Zooplankton at Pulau Redang, Terengganu, Malaysia
The Halden Reactor test series IFA-650 was part of the joint international programme of the Halden Reactor Project. These tests addressed the LOCA performance of high burnup fuel irradiated in commercial nuclear power plants. IFA-650.10 (PWR fuel): moderate ballooning, fuel fragmentation and dispersal were indicated. The fuel was supplied by EDF/FRAMATOME and had been irradiated in the French Graveline 5 PWR to 61 MWd/kgU. The target peak cladding temperature (PCT) was 850°C. Rod burst was detected 249 s after the start of blow-down. Minor fuel relocation was confirmed by gamma scanning and PIE.
Concentrations of 210Po and 210Pb were determined in the edible muscle tissue of twelve species of marine ﬁsh collected from Izmir Bay in the Aegean Sea Region of Turkey during the 2006–2007. 210Po activity concentrations in ﬁsh samples were found to vary from ND to 400 ± 9 Bq kg-1 dry weight and 210Pb activity concentrations were found to vary from ND to 15 ± 3 Bq kg-1 dry weight. The highest dose contribution due to 210Po to humans was found to be 8.908 μSv y-1. View on MARIS: * https://maris.iaea.org/explore/type/2/ref/284
Activity levels of 210Po and 210Pb in some fish species of the Izmir Bay (Aegean Sea)