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Joint project
Dragon Project

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...

Criticality safety Generation IV reactors Nuclear science Gas-cooled reactors Reactor physics …
Published date: 14 October 2022
NEA Document
Statistical Tests for Diagnosing Fission Source Convergence and Undersampling in Monte Carlo Criticality Calculations
NEA/NSC/R(2021)3

Monte Carlo criticality calculations involve a two-step procedure based on a stochastic implementation of the power iteration method: first, achieve convergence of the fission source distribution dur...

Criticality safety Monte Carlo method Nuclear science Criticality WPNCS Nuclear science …
Published date: 17 February 2023
NEA Document
English Nuclear science Criticality WPNCS WPRS Multiphysics Reactor physics Multiphysics EGMUP Reactor physics Criticality safety NSC Nuclear science …
Published date: 23 February 2016
Subtopic
Criticality safety

Criticality safety relates to accident prevention and protection from an uncontrolled nuclear fission chain reaction, or a criticality accident.

Criticality safety
Published date: 2 December 2019
NEA Document
Role of Integral Experiment Covariance Data for Criticality Safety Validation: EG UACSA Benchmark Phase IV
NEA/NSC/R(2021)1

This benchmark report has been compiled under the guidance of the NEA Working Party on Nuclear Criticality Safety (WPNCS) in the Subgroup on the Role of Integral Experiment Uncertainties and Covarian...

English UACSA Criticality safety Criticality WPNCS Nuclear science Benchmark …
Published date: 30 January 2023
NEA Document
Burnup Credit Criticality Benchmark Phase IIB: Burnup Calculations of Gadolinium-Bearing Fuel Rods in Boiling Water Reactor Assemblies for Storage and Transportation
NEA/NSC/R(2022)3

The NEA Expert Group on Used Nuclear Fuel criticality (EGUNF) organised a Phase IIB benchmark to re-examine code and nuclear data performance for BWR lattice calculations and focus on the depletion m...

Criticality safety Nuclear science WPNCS Nuclear science Benchmark …
Published date: 30 November 2022
NEA Document
Spent Nuclear Fuel Assay Data for Isotopic Validation - State-of-the-art Report
NEA/NSC/WPNCS/DOC(2011)5

Spent Nuclear Fuel Assay Data for Isotopic Validation - State-of-the-art Report

English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science ADSNF …
Published date: 6 June 2011
NEA Document
Document content and format guide for the International Criticality Safety Benchmark Evaluation Project (ICSBEP)
NEA/NSC/DOC(1995)3

Document content and format guide for the International Criticality Safety Benchmark Evaluation Project (ICSBEP) – NEA/NSC/DOC(95)03

Criticality safety NSC Nuclear science Criticality WPNCS ICSBEP Nuclear science …
Published date: 24 March 2020
NEA Document
Burn-up Credit Criticality Benchmark - Phase III-A
NEA/NSC/DOC(1996)4

Criticality Calculations of BWR Spent Fuel in Storage and Transportation, Yoshitaka Naito, Hiroshi Okuno and Yoshihara Ando (JAERI)

English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
Published date: 1 January 1996
NEA Document
Burn-up Credit Criticality Benchmark - Phase IV-A
NEA/NSC/DOC(2003)3

Reactivity Prediction Calculations for Infinite Arrays of PWR Mox Fuel Pincells

English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
Published date: 17 April 2003
NEA Document
Burn-up Credit Criticality Benchmark - Phase IV-B
NEA/NSC/DOC(2003)4

Results and Analysis of MOX Fuels Depletion Calculations

English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
Published date: 17 April 2003
NEA Document
Burn-up Credit Benchmark - Phase VIII
NEA/NSC/R(2016)2

Numerical benchmark for the analysis of small-sample reactivity experiments

English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
Published date: 9 June 2016
NEA Document
Burn-up Credit Criticality Benchmark - Phase I-A
NEA/NSC/DOC(1993)22

JAERI-M-94-003 Makoto TAKANO (JAERI), January 1994

English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
Published date: 1 January 1993
NEA Document
Burn-up Credit Criticality Benchmark - Phase III-B
NEA/NSC/DOC(2002)2

Burn-up Calculations of BWR Fuel Assemblies for Storage and Transport

English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
Published date: 16 January 2002
NEA Document
Burn-up Credit Criticality Benchmark - Phase III-A
NEA/NSC/DOC(2000)12

Criticality Calculations of BWR Spent Fuel in Storage and Transport, Hiroshi OKUNO, Yoshitaka NAITO, Yoshihira ANDO

English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
Published date: 30 June 2000
NEA Document
Burn-up Credit Criticality Benchmark - Phase III-A
NEA/NSC/DOC(1997)11

Hiroshi OKUNO, Yoshitaka NAITO and Yoshihira ANDO (JAERI)

English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
Published date: 1 January 1997
NEA Document
Burn-up Credit Criticality Benchmark - Part I
NEA/NEACRP/L(1991)337

Simple PWR Spent Fuel Cell (Problem Specification), Makoto TAKANO (JAERI), Michaele BRADY (ORNL), 1991

English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
Published date: 1 January 1991
NEA Document
Burn-up Credit Criticality Benchmark - Phase II-A
NEA/NSC/DOC(1993)15

Effect of Axial Burnup Profile (Infinite fuel pin array) Makoto Takano (JAERI), Michaele Brady (SNL), Alain Santamarina (CEA), June 1993. See NEA/NSC/DOC(96)1

English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
Published date: 1 January 1993
NEA Document
Burn-up Credit Criticality Benchmark - Part I-B
NEA/NSC/DOC(1992)10

Isotopic Prediction (Problem Specification). Revised, January 1993 Michaele C. Brady<br>See <a href="/html/science/docs/1996/nsc-doc96-06.pdf">NEA/NSC/DOC(96)6</a>.

English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
Published date: 1 January 1992
NEA Document
Burn-up Credit Criticality Safety Benchmark - Phase III-C
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

English Criticality safety NSC Nuclear science Criticality WPNCS Nuclear science …
Published date: 2 October 2015