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

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

Numerical benchmark for the analysis of small-sample reactivity experiments

Results and Analysis of MOX Fuels Depletion Calculations

Reactivity Prediction Calculations for Infinite Arrays of PWR Mox Fuel Pincells

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

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

The implementation of advanced nuclear systems requires that new technologies associated with the back end of the fuel cycle are developed. The separation of minor actinides from other fuel component...

LACANES – Phase II: Natural Convection

State-of-the-Art Report on Multi-scale Modelling of Nuclear Fuels

Primary Radiation Damage in Materials – Review of Current Understanding and Proposed New Standard Displacement Damage Model to Incorporate in Cascade Defect Production Efficiency and Mixing Effects

LACANES – Phase I: Isothermal forced convection case

Spent Nuclear Fuel Reprocessing Flowsheet

The present report provides a summary of the experiments analysed and consensuses reached by NEA WPEC Subgroup 41, including final recommendations based on all experimental data available at the time...

The following report is issued by WPEC Subgroup 28, which builds upon the work of the previous Subgroup 20 for developing new methods for cross-section covariance evaluation. Subgroup 28 was tasked w...

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

Paul Scherrer Institute, Villigen, Switzerland, 15-16 October 2001

21-22 January 2003, Barcelona, Spain

6 October 2002, Seoul, Korea

Rossendorf (Dresden), Germany, 28-30 May 2002

Attitudes towards plutonium management vary from country to country and from utility to utility: some regard plutonium as a liability and others as a valuable source of energy.

The purpose of this st...

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...

In this benchmark exercise the goal is to test the current state-of-the-art two-dimensional methods of calculating neutron flux to reactor components against the measured data of the VENUS-1 critical...

A summary of the Sixth Symposium on Reactor Noise (SMORN VI), Gatlinburg, United States, 19-24 May 1991

Several NEA Nuclear Science Committee (NSC) activities are concerned with the validation of computation methods and codes as applied to nuclear technology. One of the challenges has been and continue...

Particle transport calculations in three-dimensional configurations are becoming prevalent in nuclear applications. This places a premium on determining the accuracy of numerical solutions to practic...

Saratoga Springs, New York, 6 May 2009 - Meeting summary

Twelfth Workshop Proceedings, Batavia, Illinois, United States, 28-30 April 2014

Proceedings of the Fourteenth Workshop, 30 October-2 November 2018, Gyeongju, Korea.

Based on the success of the OECD/NRC BFBT Benchmark, Japan released data based on the NUPEC PWR Sub-channel and Bundle Tests (PSBT) Benchmark and asked Pennsylvania State University (PSU) in the Unit...

This report defines the “OECD/NEA/NSC PBMR Coupled Neutronics/Thermal-hydraulics Transient Benchmark of the PBMR-400 Core Design”. This chapter gives more information on the day-to-day management of ...

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...

The high-temperature gas-cooled reactor (HTGR) is a Generation IV reactor concept that uses a graphitemoderated gas-cooled nuclear reactor with a once-through uranium fuel cycle. This design permits ...

In 2013, the Expert Group on Reactor Physics and Advanced Nuclear Systems (EGRPANS) published a report that investigated fuel depletion effects in a pressurised water reactor (PWR). This was entitled...

The need to refine models for best-estimate calculations based on good-quality experimental data has arisen for various nuclear applications. One of the most extensive and valuable databases availabl...

The objective of the benchmark was twofold. First, the benchmark aimed to evaluate currently available computational approaches in an effort to understand the strengths and weaknesses of current ther...

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...