Published September 1992
| Version v1
Journal article
Quantitative studies of severe fuel damage using delayed neutron data
Creators
- 1. Argonne National Lab., IL (United States)
- 2. Kernforschungszentrum Karlsruhe GmbH (Germany)
Description
In this paper, a technique is presented to quantify fuel damage in a liquid-metal reactor through fast-running computer analysis of delayed neutron data, 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 Sodium Loop Safety Facility and Mol-7C test programs. Comparison is made of measured and calculated amounts of fuel damage
Additional details
Publishing Information
- Journal Title
- Nuclear Technology
- Journal Volume
- 99
- Journal Issue
- 3
- Journal Page Range
- p. 343-350.
- ISSN
- 0029-5450
- CODEN
- NUTYBB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24012326
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- CALCULATION METHODS; COMPUTERIZED SIMULATION; DATA; DELAYED NEUTRONS; FUEL CYCLE; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; SODIUM; TEST REACTORS
- Descriptors DEC
- ACCIDENTS; ALKALI METALS; BARYONS; ELEMENTARY PARTICLES; ELEMENTS; FERMIONS; FISSION NEUTRONS; HADRONS; INFORMATION; METALS; NEUTRONS; NUCLEONS; REACTORS; RESEARCH AND TEST REACTORS; SIMULATION; TEST FACILITIES