Published October 2018 | Version v1
Miscellaneous Metadata-only

Validation of MATRA-S Code for Studsvik Nine-Rod Bundle Experiment with Power Tilt

Creators

  • 1. King Abdullah City for Atomic and Renewable Energy, Riyadh (Saudi Arabia)
  • 2. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

MATRA-S is a subchannel code which has been developed for thermal hydraulic design and analysis of SMART core. The test was conducted under two-phase flow of typical BWR operation conditions. A series of calculation have been done for various operational conditions of the experiment to evaluate the mass velocity and steam quality distributions. This paper describes an experimental method as well as the measurement and the errors between the measurement and the predicted results. In this paper, calculations to validate MATRA-S code for 3x3 bundle with high power tilt were conducted. As the results, it was found that the MATRA-S code showed a similar prediction performance to the existing subchannel analysis codes.

Part of:
Proceedings of the KNS 2018 Fall Meeting

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
[4 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
50060149
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTER CALCULATIONS; DESIGN; ERRORS; FUEL ELEMENT CLUSTERS; M CODES; PERFORMANCE; PWR TYPE REACTORS; REACTOR CORES; THERMAL HYDRAULICS; VALIDATION; VELOCITY
Descriptors DEC
COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID MECHANICS; FUEL ASSEMBLIES; HYDRAULICS; MECHANICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
4 refs, 3 figs, 5 tabs