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Analysis of the RELAP5/MOD3.2.2 beta critical flow models and assessment against critical flow data from the Marviken tests / prepared by C. Queral, J. Mulas, C.G. de la Rua.

Record details

  • Physical Description: 1 online resource (xx, 74 pages) : illustrations.
  • Publisher: Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, July 2000.

Content descriptions

General Note: "Energy Systems Department, School of Mining Engineering, Polytechnic University of Madrid."
"July 2000."
"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"--Bibliographical data sheet.
Bibliography, etc. Note: Includes bibliographical references (pages 144-147).
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. 18, 2017).
Subject: Nuclear reactors > Cooling > Computer simulation.

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