Published 1979
| Version v1
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Fuel-coolant interaction-phenomena under prompt burst conditions
Description
The Prompt Burst Energetics (PBE) experiments conducted at Sandia Laboratories are a series of in-pile tests with fresh uranium oxide or uranium carbide fuel pins in stagnant sodium. Fuel-coolant-interactions in PBE-9S (oxide/sodium system) and PBE-SG2 (carbide/sodium) have been analyzed with the MURTI parametric FCI code. The purpose is to gain insight into possible FCI scenarios in the experiments and sensitivity of results to input parameters. Results are in approximate agreement for the second (triggered) event in PBE-9S (32 MPa peak) and the initial interaction in PBE-SG2
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.Files
11513732.pdf
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Additional details
Additional titles
- Augmented title (English)
- LMFBR
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- SAND--79-0123C
Conference
- Title
- International meeting on fast reactor safety technology.
- Dates
- 19 - 23 Aug 1979.
- Place
- Seattle, WA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11513732
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPARATIVE EVALUATIONS; COMPUTER CALCULATIONS; FUEL PINS; FUEL-COOLANT INTERACTIONS; LMFBR TYPE REACTORS; PRESSURE GRADIENTS; REACTOR CORE DISRUPTION; REACTOR SAFETY; SIMULATION; URANIUM CARBIDES; URANIUM DIOXIDE
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; BREEDER REACTORS; CARBIDES; CARBON COMPOUNDS; CHALCOGENIDES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; OXIDES; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Secondary number(s)
- CONF-790816--33.