LBLOCA analysis in a Westinghouse PWR 3-loop design using RELAP5/MOD3 / prepared by J.I. Sánchez, C.A. Lage, T. Núñuz.
- Physical Description: 1 online resource (ix, 61 pages) : illustrations.
- Publisher: Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, January 2001.
"Empresa Nacional del Uranio S.A."
"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Code Application and Maintenance Program (CAMP)."
"Sponsoring organization: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Bibliographic data sheet.
|Bibliography, etc. Note:||
Includes bibliographical references (page 61).
|Type of Report and Period Covered Note:||
|Source of Description Note:||
Description based on online resource; title from PDF title page (viewed on Aug. 25, 2017).
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|Subject:||Pressurized water reactors > Loss of coolant > Computer simulation.