Published 1993
| Version v1
Report
Open
Seismic margin of the WWER model 213 reactor and safety significant pipings
Creators
- 1. Nuclear Research Institute Rez plc, Integrity and Materials Division, Rez (Czech Republic)
- 2. West-Bohemia University Plzen, Department of Mechanics, Plzen (Czech Republic)
Description
Due to several deficiencies of the seismic design of the second generation NPPs with WWER 440 Model 213 the seismic reevaluation is of primary importance. In present the effort is concentrated on the reactor and the safety significant pipings, e.g. primary piping, pressurizer surge lines, feed water and steam pipings and LP ECCS piping. This task consist of two phases. In the first one the HCLPF values are evaluated. In the second one the upgrading is performed and the effectiveness is against verified using HCLPF according EPRI approach. The next step consist of application of LBB technology. (author)
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30053302.pdf
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Additional details
Publishing Information
- Imprint Title
- Upgrading of existing NPPs with 440 and 1000 MW WWER type pressurized water reactors for severe external loading conditions. Proceedings. Working material. V. 1, 2
- Imprint Pagination
- 778 p.
- Journal Page Range
- p. 679-691
- Report number
- INIS-XA--184
Conference
- Title
- SMIRT-12 conference seminar no. 16 on upgrading of existing NPPs with 440 and 1000 MW VVER type pressurized water reactors for severe external loading conditions
- Dates
- 23-25 Aug 1993
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 30053302
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- EARTHQUAKES; ECCS; PIPES; PRESSURIZERS; PRIMARY COOLANT CIRCUITS; REACTOR SAFETY; RISK ASSESSMENT; SEISMICITY; STEAM GENERATORS; WWER TYPE REACTORS
- Descriptors DEC
- BOILERS; COOLING SYSTEMS; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; SEISMIC EVENTS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs, 4 figs, 5 tabs