A Research to Determine Blast Wave Parameters
- 1. Kyung Hee University, Seoul (Korea, Republic of)
- 2. ELSOLTEC, Yongin (Korea, Republic of)
- 3. RETEC, Yongin (Korea, Republic of)
Description
When a sudden rupture occurs in the high energy lines, ejection of inner fluid with high temperature and pressure causes jet impingement, pipe whip and jet reflection as well as blast wave with secondary damage of adjacent major components. For this matter, ANSI/ANS 58.2 standard was established to provide design concept and requirements against the postulated rupture of the high energy line. USNRC also addressed that some assumptions related to high energy line break (HELB) in the standard, so that new assessment method should be developed under the HELB condition. In this study, for the verification of major parameter which demonstrate the blast wave phenomena, an experimental apparatus has been constructed and test was conducted under a preliminary HELB condition. Subsequently, 3-dimensional numerical analysis was performed using TNT model which are widely used to simulate the blast wave. Finally, blast wave parameters were verified with comparing the experimental data and corresponding analysis results.
Additional details
Identifiers
- URL
- https://www.kns.org;
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2018 Fall Meeting
- Imprint Pagination
- vp.
- Journal Page Range
- [2 p.]
Conference
- Title
- 2018 Fall Meeting of the KNS
- Dates
- 24-26 Oct 2018
- Place
- Yeosu (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 50060616
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DESIGN; ENGINEERED SAFETY SYSTEMS; REACTOR COOLING SYSTEMS; RHR SYSTEMS; RUPTURES; STEAM; USES; VERIFICATION
- Descriptors DEC
- COOLING SYSTEMS; ENERGY SYSTEMS; FAILURES; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS
Optional Information
- Notes
- 4 refs, 5 figs