RELAP5 assessment: semiscale small break tests S-UT-1, S-UT-2, S-UT-6, S-UT-7, and S-UT-8. [PWR]

Technical Report · Thu Nov 01 00:00:00 EST 1984

OSTI ID:5950872

Peterson, A C

This report describes the results of RELAP5 analyses of 10% cold leg break tests S-UT-1 and S-UT-2 and 5% cold leg break tests S-UT-6, S-UT-7, and S-UT-8. The RELAP5 models used for the analyses are described. The individual transient results are presented, and the calculations of relative effects and selected sensitivity studies are discussed. The overall conclusions and their possible relevance to future RELAP5 computer code development and application are discussed. Appendix I provides a brief description of the test facility. The RELAP5 input for each test is contained in Appendix II. RELAP5 calculations using detailed and coarse node steam generators are documented in Appendix III. The additional INEL updates used to create cycle 18+ from cycle 18 of RELAP5/MOD1 are listed in Appendix IV.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 5950872
• Report Number(s): NUREG/CR-3772; SAND-84-0884; ON: TI85007411
• Resource Relation: Other Information: Includes 2 sheets of 48x reduction microfiche
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOSS OF COOLANT
HEAT TRANSFER
HYDRAULICS
PWR TYPE REACTORS
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
EXPERIMENTAL DATA
FLOW RATE
PRESSURE GRADIENTS
REACTOR SAFETY
TEMPERATURE GRADIENTS
TEST FACILITIES
THEORETICAL DATA
ACCIDENTS
DATA
ENERGY TRANSFER
FLUID MECHANICS
INFORMATION
MECHANICS
NUMERICAL DATA
REACTOR ACCIDENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled