HDR URL confirmatory evaluations
Description
One phase of the seismic studies conducted with the decommissioned Heissdampfreaktor in Kahl, West Germany was the prediction of the response of the Recirculation Loop piping (URL) to the 5 Kg blast loading. As a follow-on study to the US effort in this area, BNL performed linear analyses of the URL piping to corroborate the linear analyses performed by an alternate NRC contractor and to verify those analyses considering distinct, independent support excitations. In this study the computer models and processed input data developed by the alternate contractor were used. The BNL effort was initiated in FY 1982 under the Mechanical Piping Benchmark Project. Specifically response predictions were made for the HDR URL system subjected to the 5 Kg blast loading considering uniform support motion with elastic supports and independent support motion with elastic supports. For the evaluations the independently developed BNL finite element piping analysis code, PSAFE2, was used. The paper includes a description of the computer model and comparisons between measured and predicted acceleration time history records for selected points in the system. Predicted results considering both uniform support excitation and independent support excitation are provided
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 - GPO as DE83010420.Files
14795525.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 10 p.
- Report number
- BNL-NUREG--32627
Conference
- Title
- 7. international conference on structural mechanics in reactor technology.
- Dates
- 22-26 Aug 1983.
- Place
- Chicago, IL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14795525
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CALCULATIONS; FINITE ELEMENT METHOD; PIPES; REACTOR SAFETY; SEISMIC EFFECTS; STRESS ANALYSIS
- Descriptors DEC
- NUMERICAL SOLUTION; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-830805--20.