Interpretation of the SNEAK-12A/B experimental programs on severe core accidents in LMFBRS - Some feedback on nuclear data re-assimilation for the prediction of reactivity changes

Marat Margulis, Patrick Blaise, Gérald Rimpault, Erez Gilad

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Abstract

The presented work details the SNEAK-12B experimental program, which is under reevaluation in a joint collaboration of CEA/KIT/Ben-Gurion University. In this work a reevaluation of the SNEAK-12B programs is made with the Serpent 2 code, which enables a detailed study of the presented core. The reevaluation was made utilizing two nuclear data evaluations (JEFF-3.1.1 and JEFF-3.2). The paper provides a complete overview on the benchmark specification and the calculation results for the different configurations. This is followed by a complete sensitivity/uncertainty analysis based on the JEFF-3.2 evaluation, and finished with cross-section adjustment procedure, which was made in order to evaluate the impact of the experimental program on the nuclear data. This work was done in the frame work of new core design and innovative experimental program to be implemented in the new zero power reactor ZEPHYR.

Original languageAmerican English
Title of host publication2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings
ISBN (Electronic)9784890471676
StatePublished - 1 Jan 2017
Event2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017 - Fukui and Kyoto, Japan
Duration: 24 Apr 201728 Apr 2017

Publication series

Name2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings

Conference

Conference2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017
Country/TerritoryJapan
CityFukui and Kyoto
Period24/04/1728/04/17

All Science Journal Classification (ASJC) codes

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering

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