Published June 1987
| Version v1
Report
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Initial pipe break analyses for advanced LMR [liquid metal reactor] concepts using MINET
Description
In support of an initial NRC review of DOE sponsored advanced liquid metal reactors (LMRs), BNL has performed some very conservative calculations of postulated primary loop pipe breaks using the MINET Code. This report briefly describes the results obtained from these calculations. 5 refs., 2 figs
Availability note (English)
Available from NTIS, PC A02/MF A01; 1 as DE87012119.Files
19023831.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- BNL-NUREG--39956
Conference
- Title
- Joint meeting of the American Nuclear Society and the Atomic Industrial Forum.
- Dates
- 15-19 Nov 1987.
- Place
- Los Angeles, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19023831
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPUTER CALCULATIONS; COMPUTERIZED SIMULATION; COOLANTS; FAILURES; HEAT TRANSFER; HYDRAULICS; LMFBR TYPE REACTORS; LOSS OF COOLANT; M CODES; PIPES; PRIMARY COOLANT CIRCUITS; PUMPS; RISK ASSESSMENT; THEORETICAL DATA
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; COMPUTER CODES; COOLING SYSTEMS; DATA; ENERGY TRANSFER; EPITHERMAL REACTORS; EQUIPMENT; FAST REACTORS; FBR TYPE REACTORS; INFORMATION; LIQUID METAL COOLED REACTORS; NUMERICAL DATA; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SIMULATION
Optional Information
- Notes
- Portions of this document are illegible in microfiche products.
- Secondary number(s)
- CONF-871101--35.