Development of integrated system for accident consequence evaluation using Level 2 and Level 3 PRA codes
- 1. Japan Atomic Energy Agency, Tokai, Ibaraki (Japan)
- 2. Visible Information Center, Inc., Tokai, Ibaraki (Japan)
Description
An integrated system between the THALES2 and the OSCAAR was developed in order to assist in preparing the input file of the OSCAAR. For the result of a state-of-the-art source term analysis with the THALES2, the authors implemented a preliminary analysis using the OSCAAR in order to evaluate the difference in setting of release fraction rates for the radionuclide groups. The effective dose was calculated for some cases by changing of release fraction rates divided into 1h (case 1), 3h (case 2), 5h (case 3), none (case 4) and arbitrary hours (case 5). After that, the ratio of the effective dose for these cases was compared. The result indicates that it was better to set short duration of release stages while the release fraction rates increased sharply. It seems that the case 5 is a better method in order to adapt to various accident scenarios. The method shows that it is useful for reducing the uncertainty in a Level 3 PRA analysis. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 27th international conference on nuclear engineering (ICONE-27)
- Imprint Pagination
- [4028 p.]
- Journal Page Range
- 5 p.
Conference
- Title
- 27. international conference on nuclear engineering
- Acronym
- ICONE-27
- Dates
- 19-24 May 2019
- Place
- Tsukuba, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51011468
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT; MASS TRANSFER; O CODES; PLUMES; PROBABILISTIC ESTIMATION; RADIOISOTOPES; REACTOR COOLING SYSTEMS; REACTOR VESSELS; RISK ASSESSMENT; SEVERE ACCIDENTS; SOURCE TERMS; T CODES; WEATHER
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; CALCULATION METHODS; COMPUTER CODES; CONTAINERS; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; ISOTOPES; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as Internet Data in PDF format, Folder Name: Track06, Paper ID: ICONE27-2319F.pdf; 5 refs., 5 figs., 2 tabs.