Published 1985
| Version v1
Report
Open
SAS4A validation and analysis of in-pile TUCOP experiments
Description
This paper presents the results of SAS4A analysis for PFR/TREAT experiment L07, a simulated TUCOP accident. This is one of a series of TUCOP tests with different channel conditions at pin failure time and different power burst shapes. While other TUCOP tests such as L6 and L7 have been analyzed with earlier versions of the SAS code, the L07 analysis is the first to use the release version of SAS4A without special modifications, using recommended values of the input variables whenever possible. The PRIMAR-4 thermal-hydraulic model is used to compute the loop characteristics during the test
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE85005053.Files
16064895.pdf
Files
(96.9 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:252094a8c74279463ccebe2d43c32aab
|
96.9 kB | Preview Download |
Additional details
Publishing Information
- Imprint Pagination
- 5 p.
- Report number
- CONF-850410--28-Summ
Conference
- Title
- ANS/ENS fast reactor safety meeting.
- Dates
- 21-24 Apr 1985.
- Place
- Knoxville, TN (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16064895
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; FUEL PINS; HEAT TRANSFER; HYDRAULICS; IN PILE LOOPS; LMFBR TYPE REACTORS; REACTOR SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TESTING; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIE; REACTORS; SAFETY