2 options
Simulation of the PKL-G7.1 experiment in a Westinghouse nuclear power plant using RELAP5/MOD3.3 / prepared by F. Sánchez-Sáez [and three others]
- Format:
- Book
- Government document
- Author/Creator:
- Sánchez-Saez, Francisco, author.
- Series:
- International agreement report ; NUREG/IA-0487.
- International agreement report ; NUREG/IA-0487
- Language:
- English
- Subjects (All):
- Nuclear power plants--Computer programs.
- Nuclear power plants.
- Pressurized water reactors--Loss of coolant.
- Pressurized water reactors.
- Physical Description:
- 1 online resource (xv, 25 pages) : illustrations (some color)
- Place of Publication:
- Washington, DC : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission., January 2019.
- Notes:
- "January 2019."
- "Prepared as part of the Agreement on Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."
- Includes bibliographical references (pages 25-26).
- Online resource; title from PDF title page (NRC, viewed November 14, 2019).
- Other Format:
- Print version: Sanchez-Sáez, F. Simulation of the PKL-G7.1 experiment in a Westinghouse nuclear power plant using RELAP5/MOD3.3
- OCLC:
- 1127642701
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