A Simplified Multi-Path Event Tree for the Integral, Inherently-Safe Light Water Reactor (I2S-LWR)
Creators
- 1. Department of Nuclear Engineering and Radiological Sciences University of Michigan, Ann Arbor, MI 48109-2104 (United States)
Description
The Integral, Inherently-Safe Light Water Reactor (I2S-LWR) concept aims to raise the bar for nuclear power plant safety while maintaining the economic advantages of large, gigawatt-scale plants.1 To obtain this goal, the project safety team seeks to eliminate initiating events where possible, maximize passivity of safety systems, and optimize a balance of redundancy, diversity, and simplicity of safety systems.2 Achievement of these objectives, particularly the last set, requires detailed, quantitative risk information from the earliest stages of development. Therefore, despite limited design information, we have constructed a preliminary probabilistic risk assessment (PRA) for I2S-LWR. Safety implementation for I2S-LWR, then, requires an iterative process involving system design, thermal-hydraulic (T/H) and neutronic deterministic analyses, and risk-informing PRA studies. Due to this parallelism, it is vital those team members without PRA expertise quickly and correctly understand preliminary PRA results. To this end, we have developed a method to condense the entire PRA into a single, multi-path event tree (MPET). (authors)
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 115
- Journal Page Range
- p. 826-829
- ISSN
- 0003-018X
Conference
- Title
- 2016 ANS Winter Meeting and Nuclear Technology Expo
- Dates
- 6-10 Nov 2016
- Place
- Las Vegas, NV (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 52083098
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HAZARDS; ITERATIVE METHODS; NUCLEAR POWER PLANTS; PASSIVITY; PROBABILISTIC ESTIMATION; REACTOR DESIGN; REACTOR SAFETY; REDUNDANCY; RISK ASSESSMENT; THERMAL HYDRAULICS; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- CALCULATION METHODS; DESIGN; FLUID MECHANICS; HYDRAULICS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR LIFE CYCLE; REACTORS; SAFETY; THERMAL POWER PLANTS
Optional Information
- Notes
- 6 refs.; available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)