Published October 1981
| Version v1
Report
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LOCA simulation in the NRU reactor: materials test-1
Description
A simulated loss-of-coolant accident was performed with a full-length test bundle of pressurized water reactor fuel rods. This second experiment of the program produced peak fuel cladding temperatures of 1148K (16070F) and resulted in six ruptured fuel rods. Test data and initial results from the experiment are presented here in the form of photographs and graphical summaries. These results are also compared with the preceding prototypic thermal-hydraulic test results and with computer model test predictions
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A08/MF A01.Files
13699435.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 169 p.
- Report number
- NUREG/CR--2152-V1
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 13699435
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FUEL RODS; LOSS OF COOLANT; NEUTRON FLUX; PWR TYPE REACTORS; REACTOR SAFETY; SIMULATION
- Descriptors DEC
- ACCIDENTS; FUEL ELEMENTS; RADIATION FLUX; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- PNL--3835.