Published 1990
| Version v1
Report
Open
Quantitative studies of severe fuel damage using delayed neutron data
Creators
- 1. Argonne National Lab., IL (USA)
- 2. Kernforschungszentrum Karlsruhe GmbH (Germany, F.R.)
Description
A technique to quantify fuel damage in an LMR through analysis of delayed neutron data is presented, which is suitable for analysis of both small-scale in-pile experiments and full-scale plants. Validating analyses are described for five in-pile severe accident simulations performed within the SLSF and Mol 7C test programs. Comparison is made of measured and calculated amounts of fuel damage. 8 refs., 5 figs., 2 tabs
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A03/MF A01 as DE90011175; OSTI; INIS; US Govt. Printing Office Dep.Files
21076016.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 11 p.
- Report number
- CONF-900804--26
Conference
- Title
- International topical meeting on fast reactor safety.
- Dates
- 12-16 Aug 1990.
- Place
- Snowbird, UT (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21076016
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; D CODES; DELAYED NEUTRONS; FUEL ELEMENT FAILURE; LMFBR TYPE REACTORS; M CODES; NEUTRON DETECTION; REACTOR COOLING SYSTEMS; REACTOR MONITORING SYSTEMS; REACTOR SAFETY; S CODES; TRANSIENT OVERPOWER ACCIDENTS
- Descriptors DEC
- ACCIDENTS; BARYONS; BREEDER REACTORS; COMPUTER CODES; COOLING SYSTEMS; DETECTION; ELEMENTARY PARTICLES; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FERMIONS; FISSION NEUTRONS; HADRONS; LIQUID METAL COOLED REACTORS; NEUTRONS; NUCLEONS; RADIATION DETECTION; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SIMULATION
Optional Information
- Contract/Grant/Project number
- Contract W-31109-ENG-38