Published May 2018 | Version v1
Miscellaneous

Validation Study of MATRA Code for PNL 7 by 7 Flow Blockage Test

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

Concern on the hydraulic design on DNB estimation under abnormal operating condition is slightly different. The abnormal operating condition may occur at postulating an isolated flow blockage in the hot channel which may enhance or deteriorate critical heat flux(CHF) at the unblocked condition. As clad temperatures increases during an accident, internal fuel rod pressure may cause clad swelling or ballooning which could lead to coolant blockage. Most of experiments on flow blockage is focused on the heat transfer and flow distribution under these accident condition. The objective of this study is to evaluate the local flow distribution prediction of MATRA code on flow blockage condition as a prerequisite study to conduct the DNB estimation under an isolated flow blockage condition. The PNL 7x7 experiment is selected as a validation data of subchannel code because this experiment provides the local flow distribution averaged on subchannel area. Sequential validation works of MATRA code on PNL 7x7 experiments were performed by same author groups.

Part of:
Proceedings of the KNS 2018 Spring Meeting

Additional details

Identifiers

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2018 Spring Meeting
Imprint Pagination
vp.
Journal Page Range
[3 p.]

Conference

Title
2018 Spring Meeting of the KNS
Dates
16-18 May 2018
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
50059175
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature, Numerical Data
Descriptors DEI
CRITICAL HEAT FLUX; DESIGN; EXPERIMENTAL DATA; FLOW BLOCKAGE; LOSS OF COOLANT; M CODES; SAFETY ANALYSIS; THERMAL HYDRAULICS; VALIDATION
Descriptors DEC
ACCIDENTS; COMPUTER CODES; DATA; FLUID MECHANICS; HEAT FLUX; HYDRAULICS; INFORMATION; MECHANICS; NUMERICAL DATA; REACTOR ACCIDENTS; TESTING

Optional Information

Notes
4 refs, 4 figs, 1 tab