2 options
Assessment of interphase drag correlations in the RELAP5/MOD2 and TRAC-PF1/MOD2 codes / prepared by K.H. Ardon, A.J. Clare.
- Format:
- Book
- Government document
- Author/Creator:
- Ardron, K. H., author.
- Clare, A. J., author.
- Series:
- International agreement report ; NUREG/IA-0015.
- International agreement report ; NUREG/IA-0015
- Language:
- English
- Subjects (All):
- Two-phase flow--Computer programs.
- Two-phase flow.
- Nuclear reactors--United States--Computer programs.
- Nuclear reactors.
- Thermodynamics--Computer programs.
- Thermodynamics.
- Nuclear reactors--Computer programs.
- United States.
- Genre:
- Online resources.
- Physical Description:
- 1 online resource (various pagings) : illustrations
- Other Title:
- Assessment of interphase drag correlations in the RELAP5/MOD2 and TRAC-PF1/MOD1 codes
- Place of Publication:
- Washington, DC : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, July 1989.
- Notes:
- Online resource; title from PDF title page (viewed on September 27, 2016).
- "Central Electricity Generating Board."
- "July 1989."
- "Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP)."
- "GD/PE-N/557"--Bibliographic data sheet
- "Technical report"--Bibliographic data sheet
- Includes bibliographical references (page 7).
- Other Format:
- Microfiche version: Ardron, K.H. Assessment of interphase drag correlations in the RELAP5/MOD2 and TRAC-PF1/MOD2 codes
- Print version: Ardron, K.H. Assessment of interphase drag correlations in the RELAP5/MOD2 and TRAC-PF1/MOD2 codes
- OCLC:
- 959831943
The Penn Libraries is committed to describing library materials using current, accurate, and responsible language. If you discover outdated or inaccurate language, please fill out this feedback form to report it and suggest alternative language.