Actions for RELAP4
RELAP4/MOD5 : a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Volume II. Program implementation. [BWR; PWR].
- Published
- United States : [publisher not identified], 1976.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1976. - Physical Description
- microfiche : negative ; 11 x 15 cm
- Summary
- A discussion is presented of the use of the RELAP4/MOD5 computer program in simulating the thermal-hydraulic behavior of light-water reactor systems when subjected to postulated transients such as a LOCA, pump failure, or nuclear excursion. The volume is divided into main sections which cover: (1) program description, (2) input data, (3) problem initialization, (4) user guidelines, (5) output discussion, (6) source program description, (7) implementation requirements, (8) data files, (9) description of PLOTR4M, (10) description of STH20, (11) summary flowchart, (12) sample problems, (13) problem definition, and (14) problem input.
- Report Numbers
- TID-27136/2
- Other Subject(s)
- 21 specific nuclear reactors and associated plants
- 210100 - power reactors, nonbreeding, light-water moderated, boiling water cooled
- 210200 - power reactors, nonbreeding, light-water moderated, nonboiling water cooled
- 22 general studies of nuclear reactors
- 220900 - nuclear reactor technology- reactor safety
- Accidents
- Blowdown
- Bwr type reactors
- Computer calculations
- Computer codes
- Cooling systems
- Document types
- Excursions
- Fluid mechanics
- Hydraulics
- Loss of coolant
- Manuals
- Mathematical models
- Mechanics
- Pwr type reactors
- R codes
- Reactor accidents
- Reactor components
- Reactor cooling systems
- Reactors
- Transients
- Water cooled reactors
- Water moderated reactors
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- DOE contract number: E(10-1)-1375
OSTI Identifier 7334741
Research organization: Idaho National Engineering Lab., Idaho Falls (USA).
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