Current and Future Applications of Thermal-Hydraulic and Neutronic Best- Estimate Methods in Support of the Swiss Licensing Process
Creators
- 1. Paul Scherrer Institut, CH 5232 Villigen PSI (Switzerland)
- 2. Swiss Federal Nuclear Inspectorate, CH 5232 Villigen HSK (Switzerland)
Description
Best-estimate methods are employed within the STARS project at PSI. The project provides independent technical expertise primarily to HSK in support of the Swiss licensing process in the area of deterministic safety analysis, and covers applications ranging from operational occurrences as well as beyond-design-basis transients. Some examples are presented: an assessment of the coolability of a PWR for reduced availability of ECCS, timing studies for an MSIV-ATWS event in a BWR in order to quantify the effect of delayed operator actions, predictions of planned start-up tests and research on BWR-stability to deepen the understanding of the phenomenon. Future work will include an extensive use of 3D-kinetics in transient analysis and the development of a comprehensive uncertainty methodology. Calculations on high burnup fuel behavior for RIA- and LOCA-scenarios are planned; also CFD applications will be developed to assess mixing problems in reactor geometries on a rigorous basis. (authors)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the workshop on advanced thermal-hydraulic and neutronic codes: current and future applications
- Imprint Pagination
- 723 p.
- Journal Page Range
- p. 182-192
- Report number
- NEA-CSNI-R--2001-2
Conference
- Title
- current and future applications
- Acronym
- Workshop on advanced thermal-hydraulic and neutronic codes
- Dates
- 10-13 Apr 2000
- Place
- Barcelona (Spain)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39036570
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATWS; AVAILABILITY; BURNUP; BWR TYPE REACTORS; ECCS; GEOMETRY; LICENSING; LOSS OF COOLANT; PWR TYPE REACTORS; SAFETY ANALYSIS; THERMAL HYDRAULICS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; DESIGN BASIS ACCIDENTS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MATHEMATICS; MECHANICS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS