Development and validation of fuel stub motion model for the disrupted core of a sodium-cooled fast reactor-Reference-Cited by-同舟云学术

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Development and validation of fuel stub motion model for the disrupted core of a sodium-cooled fast reactor

Published:2021-12 Issue:12 Volume:53 Page:3930-3943
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Kawada Kenichi,Suzuki Tohru

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference16 articles.

1. Study on dominant aspects of unprotected loss-of-flow to be evaluated in the initiating phase for a sodium-cooled fast reactor;Kawada;J. Nucl. Sci. Technol.,2020

2. Simulating unprotected accidents for advanced liquid metal reactors using the SAS4A accident analysis code;Tentner,1988

3. Development of PIRT (phenomena identification and ranking table) for SAS-SFR (SAS4A) validation;Kawada,2014

4. Preliminary result of validation study in SAS-SFR(SAS4A) code in simulated top and undercooled overpower conditions;Kawada,2014

5. Validation study in SAS4A code in simulated mild TOP condition;Kawada;Transactions of the American Nuclear Society, ANS 2016,2016

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