Published October 2017 | Version v1
Miscellaneous

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.

Part of:
Proceedings of the KNS 2017 Fall Meeting

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