RELAP4/MOD6 analysis of forced- and gravity-feed reflood tests
Conference
·
OSTI ID:5164046
The RELAP4/MOD6 computer code is used for the analysis of the reactor core heat transfer during the reflooding phase of a postulated loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR). The code requires the user to specify input parameters for the reflood heat transfer models. Results of previous comparisons of code calculations with experimental data have indicated no single selection of input parameters is adequate for a spectrum of tests and test facilities. This paper presents the development of revised quidelines and assesses the effect of those modifications on RELAP4/MOD6 data comparisons using previously analyzed reflood experiments. The paper also presents an assessment of the revised guidelines and the original guidelines against experimental data significantly different from previously analyzed tests.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5164046
- Report Number(s):
- CONF-800723--2
- Country of Publication:
- United States
- Language:
- English
Similar Records
Code option guideline improvement using comparisons of RELAP4/MOD6 with forced and gravity-feed reflood data. [PWR]
Improved guidelines for RELAP4/MOD6 reflood calculations. [PWR]
Experiment predictions of LOFT reflood behavior using the RELAP4/MOD6 code. [PWR]
Technical Report
·
Fri Sep 01 00:00:00 EDT 1978
·
OSTI ID:6541763
Improved guidelines for RELAP4/MOD6 reflood calculations. [PWR]
Conference
·
Mon Dec 31 23:00:00 EST 1979
·
OSTI ID:5352984
Experiment predictions of LOFT reflood behavior using the RELAP4/MOD6 code. [PWR]
Conference
·
Mon Oct 16 00:00:00 EDT 1978
·
OSTI ID:6494162
Related Subjects
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ACCIDENTS
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210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CALCULATIONS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS