Uranium orebodies contain a wide range of radionuclides and heavy metals of direct interest to waste repository design, including actinides, radium isotopes, lead isotopes and rare earth elements, as...
Published date:
1 January 1994
NEA/RWM/RKM(2014)5
This document is collection of articles produced by the RK&M project team about strategic aspects of the preservation of records, knowledge and memory across generations. This compilation represent o...
Published date:
11 March 2014
Published date:
1 January 1983
NEA/CSNI/R(2014)12
Following recommendations made at an exploratory meeting of experts to define an action plan on the application of Computational Fluid Dynamics (CFD) codes to nuclear reactor safety (NRS) problems, h...
Published date:
16 January 2015
NEA/CSNI/R(2007)13
Following recommendations made at an “Exploratory Meeting of Experts to Define an Action Plan on the Application of Computational Fluid Dynamics (CFD) Codes to Nuclear Reactor Safety (NRS) Problems”,...
Published date:
28 January 2008
NEA/NSC/WPEC/DOC(2010)429
Published date:
21 December 2010
NEA/NSC/WPEC/DOC(2003)291
Published date:
27 June 2003
NEA/NSC/WPEC/DOC(2001)247
Published date:
23 May 2001
Published date:
1 January 1978
NEA/NSC/WPEC/DOC(2008)409
Published date:
8 July 2008
Published date:
1 January 1975
Published date:
24 April 2001
Published date:
1 January 2000
Published date:
1 January 1974
The optimisation of the nuclear fuel cycle is a key issue for the sustainability of nuclear energy. This book presents the papers from a workshop which investigated alternative nuclear energy futures...
Published date:
1 January 1999
NEA/RWM(2014)3
This document aims at providing a starting point for discussing the usefulness of launching an international discussion and reflection on the basic elements, the concrete experiences and the challeng...
Published date:
27 February 2014
In response to growing interest in high-temperature, gas-cooled reactors (HTGRs) in many countries and the need for improved materials for nuclear applications in high-temperature environments, the N...
Published date:
1 June 2004
In response to increasing interest in high-temperature, gas-cooled reactors (HTGRs) in many countries and the need for improved materials for nuclear applications in high-temperature environments, th...
Published date:
29 May 2002
In response to increasing interest in high-temperature, gas-cooled reactors (HTGRs) and the need for improved knowledge of materials for nuclear applications that resist high temperatures, the NEA or...
Published date:
1 January 2000
NEA/CSNI/R(2006)2
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) Programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...
Published date:
19 June 2006
NEA/CSNI/R(2007)4
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the Sa...
Published date:
11 October 2007
NEA/CSNI/R(2008)6/VOL2
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...
Published date:
26 November 2008
NEA/CSNI/R(2008)6/VOL3
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...
Published date:
26 November 2008
NEA/CSNI/R(2008)6/VOL1
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...
Published date:
26 November 2008
NEA/CSNI/R(2009)13
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Accident Management and Analysis (WGAMA) and endorsed by the Committee on the S...
Published date:
21 December 2009
NEA/CSNI/R(2011)4
The Best-estimate Methods – Uncertainty and Sensitivity Evaluation (BEMUSE) programme, promoted by the Working Group on Analysis and Management of Accidents (WGAMA) and endorsed by the Committee on t...
Published date:
28 March 2011
Published date:
24 February 2000
Published date:
1 January 1991
Published date:
1 January 2000
Published date:
1 January 1989
Published date:
16 December 2008
NEA/NSC/R(2015)9
Sodium fast reactors offer the most promising type of reactors to achieve such Generation IV goals at a reasonable time scale given the experience accumulated over the years. However, it is recognise...
Published date:
5 November 2015
NEA/NSC/DOC(2012)11
The objective of the OECD LWR UAM activity is to establish an internationally accepted benchmark framework to compare, assess and further develop different uncertainty analysis methods associated wit...
Published date:
24 May 2012
Published date:
4 December 2007
Published date:
3 June 2003
Published date:
8 August 2003
Published date:
9 July 2004
Published date:
17 March 2004
Published date:
14 November 2005
An important issue regarding deterministic transport methods for whole core calculations is that homogenised techniques can introduce errors into results. In addition, with modern computational abili...
Published date:
16 September 2005
One of the important issues regarding deterministic transport methods for whole core calculations is that homogenised techniques can introduce errors into results. On the other hand, with modern comp...
Published date:
8 August 2003
Published date:
7 July 2006
Published date:
21 November 2005
In order to validate the calculations methods and nuclear data used for the prediction of power in MOX-fuelled systems, the OECD Nuclear Energy Agency (NEA) has examined a series of theoretical physi...
Published date:
9 February 2004
Published date:
30 March 2000
Published date:
22 December 2000
NEA/CSNI/R(2017)11
For most nuclear design and in-service inspection codes, fracture mechanics is used to evaluate the integrity of cracked components. The major parameters used in this kind of analysis are K and J whi...
Published date:
1 November 2017
Published date:
16 June 2009
Published date:
15 October 1999
Published date:
1 January 1993
