Quantification of severe accident source terms of a Westinghouse 3-loop plant-Reference-Cited by-同舟云学术

Quantification of severe accident source terms of a Westinghouse 3-loop plant

Published:2008-04 Issue:4 Volume:238 Page:1080-1092
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Lee Min,Ko Yu-Chih

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

Reference24 articles.

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2. Cole R.K. et al., 1984. CORCOM/Mod2, a Computer Program for Analysis of Molten-Core Concrete Interaction, Sandia National Laboratories, August NUREG/CR-3920, SAND84-1246.

3. Denning, R.S., et al., 1986. Radionuclide Release Calculations for Selected Severe Accident Scenario, Battelle Columbus Laboratories, NUREG/CR-4624, BMI-2139.

4. Calculation of Distance Factors for Power and Test Reactor Sites, Technical Information Documents (TID)-14844;DiNunno,1962

5. Fauske & Associated Incorporated, 1994. MAAP4-Modular Accident Analysis Program for LWR Power Plants.

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