Fuel pins and core response under LMFBR top accident conditions
Description
Out-of-reactor experiments are currently being performed at Argonne National Laboratory to examine fuel sweepout and related post-failure phenomena under hypothetical TOP accident conditions. These tests are supplementing the TREAT MARK-II loop data base by keying on effects of important parameter variations such as system hydraulics and intrabundle coherency. In these tests, molten UO2, generated by a thermite reaction at 34700K, is injected over approximately 40 msec into flowing sodium in a bundle of simulated LMFBR-type fuel pins. Hydraulic conditions in the bundle are selected to match conditions in either the MARK-II loop (HUMP-series) or the current design LMFBR subassembly (CAMEL-series). To date, four tests have been performed in both single-pin and seven-pin configurations representing coherent and incoherent subassembly power-to-flow cases, respectively. Details of the fuel motion were observed using a flash x-ray cine system. A compilation of significant findings from the four sweepout tests is presented
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A02/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 18 p.
- Report number
- HEDL-SA--1500-FP
Conference
- Title
- ENS/ANS international topical meeting on nuclear power reactor safety.
- Dates
- 16 - 19 Oct 1978.
- Place
- Brussels, Belgium.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10482244
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- FLOW BLOCKAGE; FLOW RATE; FUEL ELEMENT FAILURE; FUEL-COOLANT INTERACTIONS; GRAPHS; HYDRAULICS; LIQUID FLOW; LMFBR TYPE REACTORS; NUMERICAL DATA; PRESSURE GRADIENTS; REACTIVITY INSERTIONS; REACTOR CORE DISRUPTION; REACTOR SAFETY; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; DATA; DATA FORMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FLUID FLOW; INFORMATION; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY
Optional Information
- Secondary number(s)
- CONF-781022--38.