Published 1997
| Version v1
Miscellaneous
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Analysis and qualification of steam generator relief valves (BRU-A)
Description
This paper presents a general overview of improvements foreseen in the frame of Safety Measures S01 and S10 in order to prevent and mitigate consequences of a large primary to secondary leakage. Among these improvements, a more detailed description of methodology and results relative to Steam Generator Relief Valves (BRU-A) qualification tests is presented. (author)
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Additional details
Publishing Information
- Publisher
- Power Equipment Research Institute.
- Imprint Place
- Levice (Slovakia)
- Imprint Title
- Mochovce NPP safety improvement and completion
- Imprint Pagination
- 522 p.
- Journal Page Range
- p. 367-386.
- Report number
- INIS-SK--98-006
Conference
- Title
- Nuclear society information meeting on Mochovce NPP safety improvement and completion.
- Acronym
- NUSIM '97
- Dates
- 19-21 Nov 1997.
- Place
- Levice (Slovakia).
INIS
- Country of Publication
- Slovakia
- Country of Input or Organization
- Slovakia
- INIS RN
- 29028197
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Is Lead record
- Yes
- Descriptors DEI
- DESIGN BASIS ACCIDENTS; ENGINEERED SAFETY SYSTEMS; LEAKS; MOCHOVCE-1 REACTOR; MOCHOVCE-2 REACTOR; NUCLEAR FACILITIES; NUCLEAR POWER PLANTS; REACTOR SAFETY; RISK ASSESSMENT; SAFETY ANALYSIS; SAFETY ENGINEERING; SLOVAKIA; STEAM LINES; STEAM SYSTEMS; SYSTEMS ANALYSIS; TEST FACILITIES; TESTING
- Descriptors DEC
- ACCIDENTS; EASTERN EUROPE; ENRICHED URANIUM REACTORS; EUROPE; PIPELINES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- 8 figs.