Published 1986
| Version v1
Report
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Fuel pin failure in the PFR/TREAT experiments
Description
The PFR/TREAT safety testing programme involves the transient testing of fresh and pre-irradiated UK and US fuel pins. This paper summarizes the experimental and calculational results obtained to date on fuel pin failure during transient overpower (resulting from an accidental addition of resolivity) and transient undercooling followed by overpower (arising from an accidental stoppage of the primary sodium circulating pumps) accidents. Companion papers at this conference address: (I) the progress and future plans of the programme, and (II) post-failure material movements
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02; 3 as DE86012123.Files
18002725.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 10 p.
- Report number
- CONF-860501--12
Conference
- Title
- Conference on the science and technology of fast reactor safety.
- Dates
- 12-16 May 1986.
- Place
- Channel Islands (UK).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18002725
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FAILURES; FUEL PINS; PFR REACTOR; REACTOR SAFETY EXPERIMENTS; 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; LMFBR TYPE REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; SOLID HOMOGENEOUS REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS
Optional Information
- Notes
- Paper copy only, copy does not permit microfiche production.