Quantification of severe accidents source terms of BWR 4 reactor with Mark I containment using source term code package-Reference-Cited by-同舟云学术

Quantification of severe accidents source terms of BWR 4 reactor with Mark I containment using source term code package

Published:1992-12 Issue:3 Volume:138 Page:313-337
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Lee M.,Lee G.D.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference29 articles.

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2. PRA Proceduces Guide,1983

3. Calculation of distance factors for power and test reactor site;Di Nunno,1962

4. Technical bases for estimating fission product behavior during LWR accidents,1981

5. Radionuclide release under specific LWR accident conditions;Gieseke,1983

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