Event sequence analyses of a forest fire heat effect on a sodium-cooled fast reactor for an external hazard PRA methodology development
Description
As a part of a probabilistic assessment methodology development on a forest fire, this paper deals with an event sequence by forest fire heat effect on a decay heat removal function of a sodium-cooled fast reactor. Related to the potential vulnerability, an event scenario was developed using conservative assumptions such as loss of off-site power due to a damage of high-voltage lines in the course of the forest fire approaching to a nuclear power plant. An event tree was developed with an initiating event of the loss of off-site power, and the headings are related to 'external diesel fuel tanks', 'emergency diesel generator and its auxiliary system', 'alternative cooling system and its power source', and 'decay heat air cooler'. A failure probability on each heading was given from a fragility curve as a function of reaction intensity or by assumptions based on conservative models. A core damage frequency, under the conditional of the loss of off-site power, was conservatively evaluated around 10-7/year. A key heading in the event tree with large effect on the frequency is the intactness of the external diesel fuel tanks. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 10th Japan-Korea symposium on nuclear thermal hydraulics and safety (NTHAS10)
- Imprint Pagination
- 592 p.
- Journal Page Range
- 9 p.
Conference
- Title
- 10. Japan-Korea symposium on nuclear thermal hydraulics and safety
- Acronym
- NTHAS10
- Dates
- 27-30 Nov 2016
- Place
- Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 48059621
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCIDENT MANAGEMENT; AFTER-HEAT REMOVAL; FAILURE MODE ANALYSIS; FORCED CONVECTION; NATURAL CONVECTION; NUCLEAR POWER PLANTS; POWER SUPPLIES; PROBABILISTIC ESTIMATION; REACTOR ACCIDENT SIMULATION; REACTOR COOLING SYSTEMS; REACTOR CORE DISRUPTION; RISK ASSESSMENT; SODIUM COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; CALCULATION METHODS; CONVECTION; COOLING SYSTEMS; ELECTRONIC EQUIPMENT; ENERGY SYSTEMS; ENERGY TRANSFER; EQUIPMENT; HEAT TRANSFER; LIQUID METAL COOLED REACTORS; MANAGEMENT; MASS TRANSFER; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; REMOVAL; SIMULATION; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS
Optional Information
- Notes
- Available as USB Flash Memory Data in PDF format, Paper ID: NTHAS10_sub_data/pdf/N10P1072.pdf; 14 refs., 6 figs., 2 tabs.