Applying the GIF-PR&PP methodology for a qualitative analysis of a misuse scenario in a notional Generation IV Example Sodium Fast Reactor.

The Generation IV International Forum (GIF) Proliferation Resistance and Physical Protection (PR&PP) Working Group has developed a methodology for the PR&PP evaluation of advanced nuclear energy systems (NES). A notional sodium cooled fast neutron nuclear reactor system, named the Example Sodium Fast Reactor (ESFR), was used as a case study for the development and demonstration of the GIF-PR&PP Evaluation Methodology. This paper presents the results of the application of the GIF-PR&PP Evaluation Methodology to a misuse scenario involving the Example Sodium Fast Reactor (ESFR). The ESFR baseline design and two design variations are addressed. Rather than presenting a complete evaluation of all the possible misuse scenarios the paper concentrates on methodological aspects and illustrates how a qualitative analysis, following the GIF PR&PP evaluation methodology, can generate traceable results of the considered design variations and provide useful feedback for both System & Safeguards designers.

COJAZZI Giacomo;  RENDA G.;  CHOI Jor-Shan;  HASSBERGER Jim; 

2012-10-23

AMER NUCLEAR SOC

JRC62419

0029-5450,   

http://epubs.ans.org/?a=14068,    https://publications.jrc.ec.europa.eu/repository/handle/JRC62419,