Published date:
16 May 2003
NEA/NSC/DOC(2003)4
Results and Analysis of MOX Fuels Depletion Calculations
Published date:
17 April 2003
Published date:
16 May 2003
NEA/NSC/R(2015)1
Impact of Isotopic Inventory Changes due to Control Rod Insertions on Reactivity and the End Effect in PWR UO2 Fuel Assemblies
Published date:
2 June 2015
NEA/NSC/R(2015)6
Nuclide Composition and Neutron Multiplication Factor of a Boiling Water Reactor Spent Fuel Assembly for Burn-up Credit and Criticality Control of Damaged Nuclear Fuel
Published date:
2 October 2015
Published date:
21 February 2012
Published date:
23 February 2016
NEA/NSC/R(2022)3/CORR
Please note that this report was initially published in November 2022 (NEA/NSC/R(2022)3) under erroneous benchmark number IIB; in this updated version (NEA/NSC/R(2022)3/CORR) this has been corrected ...
Published date:
30 November 2022
This benchmark is organised to examine the models for fission gas release during anticipated operational occurrences (AOOs).
Published date:
7 March 2023
Published date:
1 January 1979
Published date:
1 January 2000
Kick-off workshop of the thermal hydraulic code validation benchmark for high temperature gas-cooled reactors using High Temperature Test Facility (HTTF) data.
Published date:
16 June 2023
The present volume is a reprint of the 1995 edition of Chemical Thermodynamics of Americium.
by Robert J. Silva (Chairman), Giovanni Bidoglio, Malcolm H. Rand, Piotr B. Robouch, Hans Wanner and Ign...
Published date:
2 June 2004
by Robert J. Lemire (Chairman), Urs Berner, Claude Musikas, Donald A. Palmer, Peter Taylor and Osamu Tochiyama
This volume is the 13a in the OECD Nuclear Energy Agency (NEA) Chemical Thermodynamics s...
Published date:
13 December 2013
This volume is the 13b in the OECD Nuclear Energy Agency (NEA) Chemical Thermodynamics series. It is the second part of a critical review of the thermodynamic properties of iron, its solid compounds ...
Published date:
3 March 2020
by Robert J. Lemire (Chairman), Jean Fuger, Heino Nitsche, Paul Potter, Malcolm H. Rand, Jan Rydberg, Kastriot Spahiu, James C. Sullivan, William J. Ullman, Pierre Vitorge and Hans Wanner
This volume...
Published date:
6 June 2001
by Jordi Bruno (Chairman), Dirk Bosbach, Dmitrii Kulik and Alexandra Navrotsky
This volume provides a state-of-the-art report on the modelling of aqueous-solid solution systems by the combined use of...
Published date:
25 July 2007
by Malcom Rand (Chairman), Jean Fuger, Ingmar Grenthe, Volker Neck and Dhanpat Rai
This volume is the 11th in the OECD Nuclear Energy Agency (NEA) Chemical Thermodynamics series. It is based on a cri...
Published date:
22 January 2009
by Heinz Gamsjäger (Chairman), Tamás Gajda, James Sangster, Surendra K. Saxena, and Wolfgang Voigt
This volume is the 12th in the OECD Nuclear Energy Agency (NEA) Chemical Thermodynamics series. It i...
Published date:
31 December 2013
The present volume is a reprint of the 1992 edition of Chemical Thermodynamics of Uranium.
by Ingmar Grenthe (Chairman), Jean Fuger, Rudy J. M. Konings, Robert J. Lemire, Anthony B. Muller, Chinh N...
Published date:
2 June 2004
Published date:
12 March 2020
Published date:
12 March 2020
Published date:
21 February 2002
Published date:
17 January 2023
Published date:
18 April 2006
NEA/NSC/DOC(1996)5
The OECD/NEA Nuclear Science Committee Task Force on Computing Radiation Dose and Modelling of Radiation-induced Degradation of Reactor Components was set up in November 1995 in response to a request...
Published date:
1 January 1996
Published date:
11 August 2004
Published date:
1 January 2000
Published date:
12 October 2020
NEA/NSC/R(2019)6
The purpose of this prismatic High Temperature Reactor (HTR) benchmark is to provide a solution set that can be used in future code benchmarking and to better understand the effects induced by the pr...
Published date:
18 November 2021
A criticality excursion (also referred to as a criticality accident) is the accidental production of a self-sustaining or divergent chain reaction of fissionable material.
Published date:
24 March 2020
Criticality safety relates to accident prevention and protection from an uncontrolled nuclear fission chain reaction, or a criticality accident.
Published date:
2 December 2019
Criticality is the state of a nuclear reactor when there is a self-sustaining chain reaction of fissionable material. Criticality safety analysis relates to evaluation approaches in data and computat...
Published date:
24 March 2020
Criticality is the state of a nuclear reactor when there is a self-sustaining chain reaction of fissionable material. Criticality experiments are controlled tests using fissile materials, like pluton...
Published date:
24 March 2020
Published date:
4 January 2012
Published date:
1 January 1992
Published date:
1 January 1999
Experts from 16 countries met on 13-15 September for the 24th annual Working Group on Fuel Safety GFS meeting in Paris.
Published date:
27 October 2023
The International Criticality Safety Benchmark Evaluation Project (ICSBEP) released the first version of the Database for the International Handbook of Evaluated Criticality Safety Benchmark Experime...
Published date:
25 April 2022
Development started on DATIF, the DATabase for IFpe, in 2018 in order to enhance accessibility to the IFPE legacy collection of integral fuel performance experiments data, jointly put together by the...
Published date:
12 April 2023
To ensure reliable modelling of neutron physics within a state-of-the-art transient code, the neutron kinetics part of such a code should be based on the full-scale calculation of the space-time neu...
Published date:
19 July 2022
Published date:
5 May 2020
The event gathered 129 participants from 75 international institutions.
Published date:
6 October 2022
WPRS gathered 172 experts from 22 countries at the annual Benchmark Workshop.
Published date:
9 June 2022
The WPRS met from 20-24 February 2023.
Published date:
17 March 2023
NEA/NSC/DOC(1995)3
Document content and format guide for the International Criticality Safety Benchmark Evaluation Project (ICSBEP) – NEA/NSC/DOC(95)03
Published date:
24 March 2020
The page describes the NEA's work on computing radiation dose and modelling of radiation-induced degradation of reactor components.
Published date:
30 September 2020
View of Dragon Reactor. Photo: AEA Technology.
In 1959, twelve OECD countries began the Dragon Reactor Experiment (DRE) to build a reactor at Winfrith in Dorset, United Kingdom. The Dragon was the fi...
Published date:
14 October 2022
Sustained performance of nuclear technology depends on access to a talented and well-qualified workforce, thus it is important to ensure that adequate infrastructures exist for education and training...
Published date:
22 July 2020
EGPRS Task Force members met on 3 April 2023.
Published date:
7 April 2023