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Post-test thermal-hydraulic analysis of PKL tests F1.1 and F1.2 / prepared by J. Freixa [and three others] ; prepared for Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.
Connect to full text Available online
View online- Format:
- Book
- Government document
- Author/Creator:
- Freixa Terradas, Jordi, author.
- Series:
- International agreement report ; NUREG/IA-0417.
- International agreement report ; NUREG/IA-0417
- Language:
- English
- Subjects (All):
- Nuclear power plants--Accidents--Computer simulation.
- Nuclear power plants.
- Nuclear power plants--Computer programs--Testing.
- Pressurized water reactors--Loss of coolant--Computer simulation.
- Pressurized water reactors.
- Nuclear reactor accidents--Computer simulation.
- Nuclear reactor accidents.
- Physical Description:
- 1 online resource ([73] pages) : color illustrations.
- Place of Publication:
- Washington, DC : U.S. Nuclear Regulatory Commission, October 2014.
- Notes:
- Title from title screen (viewed April 8, 2015).
- "Manuscript completed: April 2011 ; Date published: October 2014."
- Includes bibliographical references (pages 7-1).
- Other Format:
- Print version: Post-test thermal-hydraulic analysis of PKL tests F1.1 and F1.2
- OCLC:
- 905541583
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