Development of piping evaluation diagram for LBB application to KNGR surge line
- 1. KOPEC, Taejon (Korea, Republic of)
- 2. KEPRI, Taejon (Korea, Republic of)
Description
Plant specific data, such as pipe geometry, material properties and pipe loads, are required in order to evaluate Leak-Before-Break (LBB) applicability to piping systems in nuclear power plant under the construction. However, the existing method of LBB evaluation for KSNP's can not be used for newly developed nuclear plants such as Korean Next Generation Reactor (KNGR) which material properties is not available and LBB evaluation is required during design process. In order to solve this problem during developing process for KNGR surge line LBB Piping Evaluation Diagram (PED), which is independent of piping geometry and has a function of the loads applied in piping system, is developed in this paper. Also, in order to evaluate LBB applicability during construction process with only the comparative evaluation of material properties between actually used and expected, the expected changes of material properties are considered in the PED. The PED, therefore, can be used for quick LBB evaluation of KNGR surge line in the process of both design and construction. The benefit obtained by using the PED is : 1) to be able to very quickly confirm LBB applicability without calculating any leakage crack length for all concerned piping locations in the process of both iterative design for optimal routing and construction and 2) to save significantly a lot of computing times required for the corresponding LBB analyses
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the Korean Nuclear Society autumn meeting
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- [8 p.]
Conference
- Title
- 1998 autumn meeting of the Korean Nuclear Society
- Dates
- 30-31 Oct 1998
- Place
- Seoul (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 32067162
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPARATIVE EVALUATIONS; DESIGN; DIAGRAMS; LEAKS; NUCLEAR POWER PLANTS; PIPES; USES
- Descriptors DEC
- EVALUATION; INFORMATION; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS; TUBES
Optional Information
- Notes
- 11 refs, 6 figs