Peak power characteristics of postulated criticality in fuel debris
Description
For safe operation at the retrieval of fuel debris in Fukushima Daiichi Nuclear Power Plant, inadvertent criticality should be considered and the prediction of its peak power is important for the evaluation of the shielding between the fission source and operators, while measured data or analytical values in past criticality accidents are quite rare. Characteristics of the peak power under a postulated criticality accident condition have been investigated. One-point kinetics basis analysis of a postulated criticality in the fuel debris in comparison with that of JCO criticality accident showed its dependency on the parameters such as excess reactivity, delayed neutron fraction, neutron generation time, etc. In conclusion, the difference of the peak power values is mainly from heat capacity, and the key factor is the size of fuel debris at criticality. (author)
Files
Additional details
Publishing Information
- Imprint Title
- Proceedings of reactor physics Asia conference 2019 (RPHA19)
- Imprint Pagination
- [321 p.]
- Journal Page Range
- p. 31-33
- Report number
- KURNS-EKR--5
Conference
- Title
- Reactor physics Asia conference 2019
- Acronym
- RPHA19
- Dates
- 2-3 Dec 2019
- Place
- Osaka (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 52054166
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S38: RADIATION CHEMISTRY, RADIOCHEMISTRY AND NUCLEAR CHEMISTRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRITICALITY; FEEDBACK; FISSION PRODUCTS; FUKUSHIMA DAIICHI NUCLEAR POWER STATION; KINETIC EQUATIONS; OCCUPATIONAL SAFETY; PEAK LOAD; RADIATION ACCIDENTS; REACTIVITY; REACTOR DECOMMISSIONING; REACTOR OPERATORS; SEVERE ACCIDENTS; SHIELDING; SPECIFIC HEAT
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; DECOMMISSIONING; EQUATIONS; ISOTOPES; MATERIALS; PERSONNEL; PHYSICAL PROPERTIES; RADIOACTIVE MATERIALS; REACTOR LIFE CYCLE; REACTOR SITES; SAFETY; THERMODYNAMIC PROPERTIES
Optional Information
- Notes
- 15 refs., 1 fig., 3 tabs.