Published October 2008
| Version v1
Miscellaneous
Efficiency Evaluation on A Newly Developed Neutron Counter for Small SF Sample Application
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
Nuclear material accounting in spent fuel handling facilities is indispensable to the safeguards and process controls. Several non-destructive accounting methods are used for these purposes. In this work, counting efficiency of a neutron counter developed for a small spent fuel sample application was determined by an experimental method. And then this efficiency was compared and evaluated with that of the MCNPX code calculation
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
- 2008 autumn meeting of the KNS
- Dates
- 30-31 Oct 2008
- Place
- Pyongchang (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 40066593
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- EVALUATION; M CODES; MATERIALS HANDLING; NEUTRONS; SAFEGUARDS; SPENT FUELS
- Descriptors DEC
- BARYONS; COMPUTER CODES; ELEMENTARY PARTICLES; ENERGY SOURCES; FERMIONS; FUELS; HADRONS; MATERIALS; NUCLEAR FUELS; NUCLEONS; REACTOR MATERIALS
Optional Information
- Notes
- 1 ref, 2 figs, 1 tab