In 2012, the Radioactive Waste Management Committee (RWMC) noted the needs of developing operational best practices and guidelines for geological repositories. Under the RWMC’s mandate, the Integrati...
Investigation for damage condition and radiation dose in Unit 3 at Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company Holdings (December 2019). Photo: Japan Nuclear Regulation Au...
Analysis of selected thermal reactor benchmark experiments based on the JEF-1 Evaluated Nuclear Data File; M. Mattes. (May 1986).
Preservation of know-how in the nuclear field is promoted through the activities of the OECD Nuclear Energy Agency Data Bank. One area of importance concerns methods for solving radiation transport p...
This is the summary of the key issues discussed in the topical session of the 14th IGSC meeting.
Last update: 30 May 2006
Activity report of the OECD NEA Bubbler Condenser Steering Group, January 2003
Appendix D. Reference multi-group Monte Carlo solutionAppendix E. Complementary reference multi-group Monte Carlo solutions and comparisonAppendix F. Two-dimensional result analysisAppendix G. All co...
This appendix provides the complete compilation of responses received to the questionnaire issued in conjunction with the workshop announcements. The responses are provided as received, with changes ...
For preparation of the workshop held by the Working Group of Inspection Practices in May 2002 in Veracruz (Mexico), participants were invited to supply their national inspection approaches used in in...
Selection of data for the JEFF-3.1 general-purpose neutron data file
Performance reports on the JEFF-3.1 general-purpose neutron data library
List of definitions to the ENDF-6 file format for JEFF-3.1
NEA Expert Group on the Application of Robotics and Remote Systems in the Nuclear Back‑end (EGRRS) plenary meeting, 7 December 2020
NEA Expert Group on the Application of Robotics and Remote Systems in the Nuclear Back‑end (EGRRS) kick‑off meeting, 9‑10 December 2019
The OECD NEA RASPLAV Project provided experiments with prototypical material and data on the behavior of molten core material (corium) in the reactor pressure vessel lower head during a severe accide...
The scope of the proposed project is therefore to perform practical exercises of demonstration of the SAPIUM approach.
Experience from decommissioning projects suggests that the decommissioning of nuclear power plants could be made easier if it received greater consideration at the design stage and during the operati...