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Incident and Trafficking Database (ITDB)
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... -
Database of separate effect tests carried out at HUN-REN EK with cladding sam...
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... -
IAEA’s MODARIA II Soil-Plant Transfer Parameter Dataset for Tropical Environm...
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... -
The JOYO B5D-2 test
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)... -
FBTR MOX
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... -
Thermohydraulic Boundary Conditions for Simulation
Thermohydraulic Boundary Conditions for Simulation were developed in the framework of IAEA Coordinated Research Project (CRP) “Fuel Modelling in Accident Conditions” (FUMAC,... -
ATF Open Sources Material Properties Database Developed by IAEA CRP “ATF-TS” ...
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... -
CRIEPI - DEGREE Single Rod and Bundle Tests
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... -
Assessment of the committed effective dose due to the 210Po intake from fish ...
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... -
Phenix SUPERFACT
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... -
Sentenay, Phenix (MOX fuel)
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... -
METAPHIX-2#1
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... -
METAPHIX-1#1
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... -
Studsvik LOCA test (NRC-192)
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... -
KIT QUENCH-L1 Bundle Test
This dataset has no description
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KIT QUENCH-L0 Bundle Test
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... -
KIT CORA-15
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... -
Halden Reactor Test IFA-650.11 (PWR)
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... -
Halden Reactor Test IFA-650.10 (PWR)
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... -
Halden Reactor Test IFA-650.9 (PWR)
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...
