Published August 1979
| Version v1
Report
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Design basis neutronics calculations for NRU-LOCA experiments
Description
The report describes the neutronics analysis for the LOCA simulation experiments in the NRU reactor. The experimental program will provide greater understanding of nuclear fuel assembly behavior during the heatup, reflood and quench sequence of a hypothetical LOCA. The decay heat and stored heat, which are the energy source in a LOCA will be simulated by fission heat provided by the NRU reactor. The reactor, the test and test operation are described
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A07/MF A01.Files
11517545.pdf
Files
(20.8 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 135 p.
- Report number
- NUREG/CR--1025
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11517545
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- LOSS OF COOLANT; MATHEMATICAL MODELS; NEUTRON FLUX; NRU REACTOR; POWER DENSITY; PWR TYPE REACTORS; REACTOR KINETICS; REACTOR SAFETY EXPERIMENTS; SIMULATION
- Descriptors DEC
- ACCIDENTS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; KINETICS; NATURAL URANIUM REACTORS; RADIATION FLUX; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEST REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- PNL--3113.