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.
|General Note:|| "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:|| Technical report.
|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.