ROSA/LSTF test and RELAP5 code analyses on PWR hot leg small-break LOCA with accident management measure based on core exit temperature and PKL counterpart test-Reference-Cited by-同舟云学术

ROSA/LSTF test and RELAP5 code analyses on PWR hot leg small-break LOCA with accident management measure based on core exit temperature and PKL counterpart test

Published:2018-11 Issue: Volume:121 Page:594-606
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Takeda Takeshi^ORCID

Funder

Japan Atomic Energy Agency

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference32 articles.

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5. Post-test analysis of the ROSA/LSTF and PKL counterpart test;Carlos;Nucl. Eng. Des.,2016

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