Abstract

SFCOMPO is the world’s largest database for measured spent nuclear fuel assay data. An international effort coordinated by the Nuclear Energy Agency (NEA) resulted in a significant expansion of the database and its release online in 2017 as a downloadable application. The SFCOMPO Technical Review Group (TRG) was recently formed under the direction of NEA’s Nuclear Science Committee/Working Party on Nuclear Criticality Safety and was mandated to maintain and further coordinate the development of SFCOMPO. This TRG is currently focused on (1) critical evaluation of the experimental assay data by independent experts and (2) development of benchmarks and benchmark models that can be applied to validate burnup codes. This will improve the quality and documentation of the experimental datasets and enable their use by the international community to support code validation for design and safety analysis of spent nuclear fuel transportation, storage, and repository applications. It follows the precedent and draws on the experience gained from similar NEA efforts in the International Reactor Physics Experiment Evaluation Project and the International Criticality Safety Benchmark Experiment Project. Ongoing SFCOMPO evaluations have served as a test bed to develop templates for documenting evaluations, develop review guidance, improve approaches for a global uncertainty analysis, and devise a strategy focused on providing practical information of highest value to the user community. The current effort, status, and associated challenges are discussed.

Highlights

  • SFCOMPO is the world’s largest database for measured spent nuclear fuel isotopic assay data [1]

  • The evaluation process follows precedent and draws on the experience gained from similar Nuclear Energy Agency (NEA) activities in the International Reactor Physics Experiment Evaluation Project (IRPhEP) [4,5] and the International Criticality Safety Benchmark Experiment Project (ICSBEP) [6]

  • It included tables of isotopic measurement data for spent nuclear fuel samples selected from fuel that had been irradiated in two types of reactors: pressurized water reactors (PWRs) and boiling water reactors (BWRs)

Read more

Summary

INTRODUCTION

SFCOMPO is the world’s largest database for measured spent nuclear fuel isotopic assay data [1]. The SFCOMPO Technical Review Group (TRG) was recently formed under the direction of NEA’s Nuclear Science Committee/Working Party on Nuclear Criticality Safety (WPNCS) and was mandated to maintain and further coordinate the development of the database [3] This TRG transitioned from the former NEA Expert Group on Assay Data for Spent Nuclear Fuel (EGADSNF). The SFCOMPO TRG is currently focused on (1) critical evaluation of the data by independent experts and (2) development of benchmarks and benchmark models This process will improve the quality and documentation of the experimental datasets and enable their use by the international community to support code validation for design and safety analysis of spent fuel transportation, storage, and repository applications. The current effort, status, and associated challenges are presented

Database Evolution
Current Status
SFCOMPO TRG MANDATE
Background
SFCOMPO Evaluations Status
11 Evaluation of Fukushima-Daini-1 Samples
Evaluation Process and Challenges
CONCLUSIONS
Full Text
Published version (Free)

Talk to us

Join us for a 30 min session where you can share your feedback and ask us any queries you have

Schedule a call