Published May 1999 | Version v1
Miscellaneous

Study on partial blockage in an LMR 19 pin bundle subassembly

  • 1. KAERI, Taejon (Korea, Republic of)

Description

It is important to know the effect of a local flow blockage on the potential of localized boiling and a failure of the fuel cladding within an LMR fuel subassembly. In this study, flow blockage is simulated by using the subchannel analysis codes, MATRA-LMR and SABRE4 with THORS experimental data of ORNL. Both codes show relatively good agreement to the experimental data for exit temperatures in no blockage case. But in blockage case, there were some differences between the experimental data and the code calculational results. Solid blockage could not be exactly predicted by MATRA-LMR because of the numerical instabilities of this code

Part of:
Proceedings of the Korean Nuclear Society spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the Korean Nuclear Society spring meeting
Imprint Pagination
[one CD-ROM]
Journal Page Range
[8 p.]

Conference

Title
1999 spring meeting of the Korean Nuclear Society
Dates
28-29 May 1999
Place
Pohang (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
33042375
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data, Non-conventional Literature
Descriptors DEI
CLADDING; COMPUTER CODES; EXPERIMENTAL DATA; FUEL PINS; LIQUID METAL COOLED REACTORS; ORNL
Descriptors DEC
DATA; DEPOSITION; FUEL ELEMENTS; INFORMATION; NATIONAL ORGANIZATIONS; NUMERICAL DATA; REACTOR COMPONENTS; REACTORS; SURFACE COATING; US AEC; US DOE; US ERDA; US ORGANIZATIONS

Optional Information

Notes
5 refs, 9 figs, 1 tab