Comparative Analysis of FAST-2 and MATRA-S Code Using Validation Problem
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
FAST code is developed to calculate quickly the MDNBR calculation for this purpose. Recently, the FAST code, named as FAST-2, is entirely improved as adopting an expanded multichannel ability, iterative linear solver to improve the calculation speed and robustness of linear system of equations, and transient term considering unsteady condition. In this study, validation of FAST-2 is performed with comparing the experiment results which are used to validate MATRA-S code. These validation problem set are basically consisted of the single phase and two phase condition where test geometry is constricted as a bundle geometry. Fast running DNBR calculation code to implement core monitoring and protection system, FAST-2 code, is developed with enhancing the functionality and accuracy compared with original FAST code. It is a result of pay-off for improving robustness caused by removing the iteration and 2 or 3 times of calculation speed. Acutally, the calculation time of FAST-2 is consumed with 1/5 and 1/10 of MATRA-S calculation time on CNEN 4x4 and WH 14x14 problem and 1/2 or 1/5 in two-phase flow condition.
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2017 Fall Meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [3 p.]
Conference
- Title
- 2017 Fall Meeting of the KNS
- Dates
- 25-27 Oct 2017
- Place
- Kyungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 49078813
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; F CODES; M CODES; MONITORING; PWR TYPE REACTORS; TWO-PHASE FLOW; VALIDATION
- Descriptors DEC
- COMPUTER CODES; ENRICHED URANIUM REACTORS; EVALUATION; FLUID FLOW; POWER REACTORS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 2 refs, 5 figs, 2 tabs