A probabilistic consequence assessment for a very high temperature reactor
Creators
- 1. Hanyang Univ., Seoul (Korea, Republic of). Dept. of Nuclear Engineering
Description
Currently, fossil fuel is globally running out. If current trends continue, crude oil will be depleted in 20 years and natural gas in 40 years. In addition, the use of fossil resource has increased emissions of green gas such as carbon dioxide. Therefore, there has been a strong demand in recent years for producing large amounts of hydrogen as an alternative energy [1]. To generate hydrogen energy, very high temperature more than 900 C is required but this level is not easy to reach. Because a Very High Temperature Reactor (VHTR), one of next generation reactor, is able to make the temperature, it is regarded as a solution of the problem. Also, VHTR has an excellent safety in comparison with existing and other next generation reactors. Especially, a passive system, Reactor Cavity Cooling System (RCCS), is adopted to get rid of radiant heat in case of accidents. To achieve variety requirements of new designed-reactors, however, it needs to develop new methodologies and definitions different with existing method. At the same time, an application of probability safety assessment (PSA) has been proposed to ensure the safety of next generation NPPs. For this, risk-informed designs of structures have to be developed and verified. Particularly, the passive system requires to be evaluated for its reliability. The objective of this study is to improve safety of VIITR by conducting risk profile.
Additional details
Publishing Information
- Journal Title
- Atw. Internationale Zeitschrift fuer Kernenergie
- Journal Volume
- 62
- Journal Issue
- 2
- Journal Page Range
- p. 89-95
- ISSN
- 1431-5254
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 48038085
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- FISSION PRODUCT RELEASE; M CODES; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RELIABILITY; RISK ASSESSMENT; SAFETY CULTURE; SYSTEMS ANALYSIS; VHTR REACTOR
- Descriptors DEC
- ACCIDENTS; ATTITUDES; CALCULATION METHODS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; THERMAL POWER PLANTS; THERMAL REACTORS