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