Published May 1999
| Version v1
Miscellaneous
Study on partial blockage in an LMR 19 pin bundle subassembly
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
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