PFR/TREAT CO1 and LO1 experiments
Creators
- 1. Argonne National Laboratory, IL (USA)
- 2. Westinghouse Hanford Co., Richland, WA (USA)
- 3. UKAEA, AEE Winfrith (UK)
- 4. UKAEA, AERE Harwell (UK)
Description
The CO1 and LO1 TREAT experiments were the first two in a series of international fast reactor safety experiments to be conducted as part of the PFR/TREAT program being performed by the US and the UK. Conditions for these two experiments simulated a large fast reactor hypothetical (150 ms period) transient overpower (TOP) accident. The CO1 configuration was a single fuel pin in a NaK filled capsule while LO1 used a seven-pin bundle in a flowing sodium loop. The fuel pins in both experiments had no prior irradiation and represented the PFR driver fuel. The CO1 and LO1 experiments were performed on November 5 and November 24, 1980, respectively. This paper describes the objectives, test articles, experimental approach, and the major observations. Post-transient examination results and fuel failure modeling studies are also 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
- 651 p.
- Journal Page Range
- v. 4 p. 439-448.
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
- 14795746
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONFIGURATION; FUEL ELEMENT FAILURE; FUEL PINS; LMFBR TYPE REACTORS; PFR REACTOR; REACTOR SAFETY EXPERIMENTS; SIMULATION; TESTING; TIME DEPENDENCE; 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; FUEL ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; LIQUID METAL COOLED REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; SOLID HOMOGENEOUS REACTORS; TEST REACTORS; THERMAL REACTORS
Optional Information
- Notes
- Imprint:Actes de la conference de Lyon.;Vol. 4.