Published October 2011
| Version v1
Miscellaneous
Criticality and Its Uncertainty Analysis of Spent Fuel Storage Rack for Research Reactor
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
For evaluating the criticality safety of spent fuel storage rack in an open pool type research reactor, a permissible upper limit of criticality should be determined. It can be estimated from the criticality upper limit presented by the regulatory guide and an uncertainty of criticality calculation. In this paper, criticalities for spent fuel storage rack are carried out at various conditions. The calculation uncertainty of MCNP system is evaluated from the calculation results for the benchmark experiments. Then, the upper limit of criticality is determined from the uncertainties and the calculated criticality of the spent fuel storage rack is evaluated
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2011 autumn meeting of the KNS
- Dates
- 26-28 Oct 2011
- Place
- Kyoungju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 43045330
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- COMPUTER CALCULATIONS; CRITICALITY; REGULATORY GUIDES; RESEARCH REACTORS; SAFETY; SPENT FUEL STORAGE
- Descriptors DEC
- DOCUMENT TYPES; REACTORS; RESEARCH AND TEST REACTORS; STORAGE
Optional Information
- Notes
- 4 refs, 1 fig, 2 tabs