Published 2013
| Version v1
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Calculation and Analysis of Neutron Time-spatial Kinetics in Uncontrolled Withdrawal Accident of Regulating rod in CEFR
Description
Feedback calculation model: – NKF: → reactivity is obtained by the calculation formula of the reactivity; → fuel temperature,coolant temperature and some other parameters are averages over the whole core; → not considering the differences in the various components; → temperature feedback coefficients are given in advance, not change with temperature. – NAS-K: → feedback effects are directly reflected in the cross section; → considering the changes of spatial distribution; → considering the relationship between the rate of various reactivities and the current temperature; → feedback model of the NAS-K is more accurate
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45089627.pdf
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Additional details
Identifiers
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- Imprint Title
- International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13). Presentations
- Imprint Pagination
- vp.
- Journal Page Range
- 22 p.
- Report number
- IAEA-CN--199
Conference
- Title
- International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios
- Acronym
- FR13
- Dates
- 4-7 Mar 2013
- Place
- Paris (France)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 45089627
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENTS; COOLANTS; CROSS SECTIONS; FEEDBACK; FUELS; KINETICS; NEUTRONS; REACTIVITY; REGULATING RODS; SPATIAL DISTRIBUTION
- Descriptors DEC
- BARYONS; CONTROL ELEMENTS; DISTRIBUTION; ELEMENTARY PARTICLES; FERMIONS; HADRONS; NUCLEONS; REACTOR COMPONENTS
Optional Information
- Notes
- PowerPoint presentation
- Secondary number(s)
- IAEA-CN--199/189