Assessment and SMART application of system analysis design code, TASS/SMR-S for SBLOCA
- 1. Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong, Daejeon 305-353 (Korea, Republic of)
Description
Highlights: ► TASS/SMR-S code is thermal hydraulic design code for SMART. ► Thermal hydraulic design code must be assessed using ITE such as LOFT and semiscale test. ► TASS/SMR-S was assessed for SBLOCA using LOFT L3-7 with good agreement. ► It is proven that TASS/SMR-S has feasibility of application to SBLOCA. ► TASS/SMR-S was applied to simulate SBLOCA scenario of SMART. - Abstract: TASS/SMR-S is thermal-hydraulic design code for safety analysis of SMART plant. SBLOCA is considered as the design basis accident in the SMART. The capability of TASS/SMR-S for SBLOCA analysis was assessed using LOFT L3-7 as TMI action plan. Because TASS/SMR-S has been developed only for SMART, which is an integral reactor with helical steam generator heat exchanger, the steam generator model of TASS/SMR-S cannot be used directly for LOFT experiment that involves the use of U-tube steam generator. Therefore, the general heat structure model of TASS/SMR-S was used for modeling the SG heat exchanger. Nevertheless, TASS/SMR-S predicted important thermal-hydraulic parameters such as system pressure, fluid temperatures, and cladding temperature of reactor within reasonable error ranges. Further, TASS/SMR-S was applied to simulate SBLOCA in the SMART plant. In this simulation, thermal hydraulic parameters similar to those predicted in LOFT L3-7 were predicted.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2012.09.029Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2012.09.029;
- PII
- S0029-5493(12)00517-1;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 254
- Journal Page Range
- p. 291-299
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44047521
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
- Descriptors DEI
- CLADDING; COMPUTERIZED SIMULATION; DESIGN BASIS ACCIDENTS; HEAT EXCHANGERS; LOSS OF COOLANT; LOSS OF FLOW; SAFETY ANALYSIS; STEAM GENERATORS; SYSTEMS ANALYSIS; T CODES; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; BOILERS; COMPUTER CODES; DEPOSITION; FLUID MECHANICS; HYDRAULICS; MECHANICS; REACTOR ACCIDENTS; SIMULATION; SURFACE COATING; VAPOR GENERATORS
Optional Information
- Copyright
- Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.