Review of recent ANL safety experiments in SLSF and TREAT
- 1. Argonne National Laboratory, Argonne, IL (USA)
Description
Among the recent significant in-pile experiments conducted by ANL are Sodium Loop Safety Facility (SLSF) experiment P4 in the Engineering Test Facility (ETR) and TREAT experiments F3, F4 and J1. The P4 experiment, which had three heat-generating flow blockages each installed in six coolant channels in a 37-pin bundle of FTR (Fast Test Reactor)-type fuel elements, investigated the bounding consequences of severe local faults. The principal objectives were to eject molten fuel into the bundle geometry and, during subsequent extended operation, to characterize the behavior of (and response of instrumentation to) any subsequent blockage growth; secondary objectives included characterizing the severity of any molten-fuel/coolant interaction and the response of the coolant. The F3 and F4 experiments in TREAT were phenomenological tests to study the fuel column disruption mode in loss-of-flow accidents. The J1 experiment was the first slow period (approximately 10s) transient overpower experiment done in TREAT. Results of these experiments will be presented
Additional details
Additional titles
- Original title (no language)
- Actes de la conference de Lyon.
Publishing Information
- Publisher
- SFEN.
- Imprint Place
- Paris (France)
- Imprint Title
- Proceedings of the L.M.F.B.R. safety topical meeting
- Imprint Pagination
- 781 p.
- Journal Page Range
- v. 2 p. 153-161.
Conference
- Title
- L.M.F.B.R. safety topical meeting.
- Dates
- 19-23 Jul 1982.
- Place
- Lyon (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 14787382
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FLOW BLOCKAGE; FUEL ELEMENT FAILURE; FUEL-COOLANT INTERACTIONS; LMFBR TYPE REACTORS; LOSS OF FLOW; REACTOR SAFETY EXPERIMENTS; SIMULATION; TESTING; TRANSIENT OVERPOWER ACCIDENTS; TREAT REACTOR
- Descriptors DEC
- ACCIDENTS; AIR COOLED REACTORS; BREEDER REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; TEST REACTORS; THERMAL REACTORS
Optional Information
- Notes
- Imprint:Actes de la conference de Lyon.;Vol. 2.