Published May 1978
| Version v1
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Comparison of RELAP4/MOD6 with forced-feed reflood data
Description
Comparisons of RELAP4/MOD6 code calculatins and experimental data from FLECHT and Semiscale forced feed reflood tests were made. These comparisons were made as part of a larger effort to verify the capabilities of the code using a wide variety of exprimental configurations and conditions. Ground rules for code usage were established and rigidly adhered to during base runs of each test. In certain fruitful areas, diagnostic studies were made subsequent to the verification base runs to clarify the previous results. Adequate, inadequate and incomplete features of the verification process and the code are identified. Recommendations are made regarding potential code and modeling improvements
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A06/MF A01.
Files
Additional details
Additional titles
- Augmented title (English)
- PWR
Publishing Information
- Imprint Pagination
- 106 p.
- Report number
- CVAP-TR--7-78
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10469981
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; ECCS; FLOW RATE; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MATHEMATICAL MODELS; PWR TYPE REACTORS; REACTOR SAFETY; SPATIAL DISTRIBUTION
- Descriptors DEC
- ACCIDENTS; DISTRIBUTION; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS