Published 1973
| Version v1
Report
Sensitivity study with the code BRUCH-D for the analysis of loss-of-coolant accidents
Creators
Description
no abstract available
Additional details
Publishing Information
- Imprint Title
- Topical meeting on water-reactor safety
- Imprint Pagination
- p. 740-757.
- Report number
- CONF-730304--
Conference
- Title
- National topical meeting on water reactor safety.
- Dates
- 26 Mar 1973.
- Place
- Salt Lake City, Utah, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 4082710
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- B CODES; BLOWDOWN; HEAT TRANSFER; LIQUID FLOW; LOSS OF COOLANT; REACTOR ACCIDENTS; REACTOR SAFETY; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; FLUID FLOW; REACTORS; SAFETY