RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Volume III. Checkout applications. [BWR, PWR]
Technical Report
·
OSTI ID:7252059
- ed.
A description is provided of the RELAP4/MOD5 computer program checkout process and the specific problems modeled to demonstrate the usability of the code. One of the eight checkout problems reported was for an actual Semiscale test. A comparison of the RELAP4/MOD5 and Semiscale Test S-02-9 results is given in an appendix.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- E(10-1)-1375
- OSTI ID:
- 7252059
- Report Number(s):
- TID-27136/3; TRN: 77-000166
- Country of Publication:
- United States
- Language:
- English
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RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Volume III. Checkout applications. [PWR and BWR]
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Technical Report
·
Wed Sep 01 00:00:00 EDT 1976
·
OSTI ID:7252059
+13 more
RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Volume I. RELAP4/MOD5 description. [BWR; PWR]
Technical Report
·
Tue Jun 01 00:00:00 EDT 1976
·
OSTI ID:7252059
RELAP4/MOD5: a computer program for transient thermal-hydraulic analysis of nuclear reactors and related systems. User's manual. Supplement 1, RELAP4/MOD5, Update 2. [BWR; PWR]
Technical Report
·
Sun Aug 01 00:00:00 EDT 1976
·
OSTI ID:7252059
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
LOSS OF COOLANT
COMPUTER CODES
R CODES
HYDRAULICS
PWR TYPE REACTORS
BLOWDOWN
COMPUTER CALCULATIONS
EXCURSIONS
MANUALS
MATHEMATICAL MODELS
REACTOR COOLING SYSTEMS
TRANSIENTS
ACCIDENTS
COOLING SYSTEMS
DOCUMENT TYPES
FLUID MECHANICS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
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210200 - Power Reactors
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
LOSS OF COOLANT
COMPUTER CODES
R CODES
HYDRAULICS
PWR TYPE REACTORS
BLOWDOWN
COMPUTER CALCULATIONS
EXCURSIONS
MANUALS
MATHEMATICAL MODELS
REACTOR COOLING SYSTEMS
TRANSIENTS
ACCIDENTS
COOLING SYSTEMS
DOCUMENT TYPES
FLUID MECHANICS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled