PBF experimental program
Description
The fuels behavior research in PBF is directed towards providing a detailed understanding of the response of nuclear fuel assemblies to off-normal and hypothetical accident conditions. Single fuel rods and clusters of highly instrumented fuel rods are installed within a central test space of the PBF core for testing. The core can be operated in various modes to provide test conditions typical of accidents and off-normal conditions such as: (1) Power-Cooling-Mismatch (PCM) accidents; (2) Loss-of-Coolant Accident (LOCA); (3) Reactivity-Initiated-Accident (RIA); (4) Operational Transients With and Without Scram (OPTRAN); (5) Small Break LOCAs (SBL). This document provides an overview of each of the PBF test series with emphasis on what has been learned to date and why the remaining tests are being conducted
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.Files
12613411.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 35 p.
- Report number
- CONF-791118--12
Conference
- Title
- 7. water reactor safety research information meeting.
- Dates
- 5 - 9 Nov 1979.
- Place
- Gaithersburg, MD, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 12613411
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- LOSS OF COOLANT; PBF REACTOR; REACTOR SAFETY EXPERIMENTS; SIMULATION; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; PULSED REACTORS; REACTOR ACCIDENTS; REACTORS; TANK TYPE REACTORS