TRAC-BD1 analysis of a small break test in the ROSA-III facility
Description
A best-estimate, TRAC-BD1 computer simulation and subsequent code/data comparison was conducted for Run 912 of the ROSA-III small break LOCA test series. Run 912 is a simulated 5% split break in the recirculation piping, assuming failure of the high pressure core spray. The Organization for Economic Cooperation and Development designated this test as International Standard Problem 12. One objective of this work was to provide results for the United States Nuclear Regulatory Commission's participation in International Standard Problem 12. This work also serves a second objective through its applicability to the Nuclear Regulatory Commission's code assessment objectives. Results from the code-calculated behavior, with comparisons to the experimental data, are presented. These results indicate that TRAC-BD1 gave reasonable results over a wide range of conditions typically encountered with small break LOCAs
Additional details
Publishing Information
- Journal Title
- Am. Soc. Mech. Eng., [Pap.]
- Journal Volume
- 83-WA/HT-17
- Series
- Am. Soc. Mech. Eng., [Pap.].
- Journal Page Range
- 6
- ISSN
- 0402-1215
Conference
- Title
- ASME winter annual meeting.
- Dates
- 13-18 Nov 1983.
- Place
- Boston, MA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16010928
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPRESSIBLE FLOW; COMPUTER CODES; COMPUTERIZED SIMULATION; COOLANTS; FAILURE MODE ANALYSIS; HEAT TRANSFER; HYDRAULICS; LEAKS; LOSS OF COOLANT; PIPES; POWER REACTORS; PWR TYPE REACTORS; R CODES; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR SAFETY; SPRAYS; TECHNOLOGY TRANSFER
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-831111--.