Technical issues for safety improvement 2. Validation of effectiveness of heat removal using SG secondary system in PWR
Creators
- 1. Mitsubishi Heavy Industries, Ltd., Kobe, Hyogo (Japan)
- 2. Central Research Institute of Electric Power Industry, Komae, Tokyo (Japan)
- 3. Toshiba Corp., Yokohama, Kanagawa (Japan)
- 4. Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki (Japan)
- 5. Japan Atomic Energy Agency, Tokai, Ibaraki (Japan)
Description
Cooling with steam generator (SG) secondary system is one of the most important AM measures for PWR because that makes it possible to remove the core decay heat without losing the inventory of the primary system and to reduce pressure of the primary system promoting coolant injection by low-pressure injection equipment in the case of LOCA. Effectiveness of the cooling using SG secondary system has been indicated by various integrated system tests, but the data that can cover a wide range of SA scenarios is insufficient, for example when the primary system inventory is small or core decay heat is small. This paper summarizes typical subjects relating to the SG secondary-side depressurization and shows some recent activities to expand the database for the validation of BE analytical methods. (author)
Additional details
Publishing Information
- Imprint Title
- The 20th national symposium on power and energy systems (SPES 2015)
- Imprint Pagination
- 402 p.
- Journal Page Range
- p. 263-264
Conference
- Title
- 20. national symposium on power and energy systems
- Acronym
- SPES 2015
- Dates
- 18-19 Jun 2015
- Place
- Sendai, Miyagi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 48008642
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCIDENT MANAGEMENT; AFTER-HEAT REMOVAL; COOLANTS; DEPRESSURIZATION; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR CORES; SAFETY; SECONDARY COOLANT CIRCUITS; STEAM GENERATORS; VALIDATION
- Descriptors DEC
- ACCIDENTS; BOILERS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; MANAGEMENT; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; TESTING; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 refs., 2 figs., 1 tab.