Published 2007
| Version v1
Miscellaneous
Neutron and Gamma Shielding Evaluation for KN-12 Spent Nuclear Fuel Transport Cask
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
- 2. Korea Hydro and Nuclear Power Co., LTD., Kori (Korea, Republic of)
Description
The CASTOR KN-12 is designed to transport 12 intact PWR spent fuel assemblies for dry and wet transportation conditions. The overall cask length is 480.1 cm with a wall thickness 37.5 cm. Shield for the KN-12 is maintained by the thick walled cask body and the lid. For neutron shielding, polyethylene rods (PE) are arranged in longitudinal boreholes in the vessel wall and PE-plates are inserted between the cask lid and lid side shock absorber and between the cask bottom and bottom steel plate. The shielding evaluation of the cask has been performed with MCNP to confirm the shielding integrity of cask for pre-service inspection of transport cask
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS spring meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2007 spring meeting of the KNS
- Dates
- 10-11 May 2007
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 38113253
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- FUEL ASSEMBLIES; GAMMA RADIATION; M CODES; NEUTRONS; SHIELDING; SHOCK ABSORBERS; SPENT FUEL CASKS; SPENT FUELS
- Descriptors DEC
- BARYONS; CASKS; COMPUTER CODES; CONTAINERS; ELECTROMAGNETIC RADIATION; ELEMENTARY PARTICLES; ENERGY SOURCES; FERMIONS; FUELS; HADRONS; IONIZING RADIATIONS; MATERIALS; NUCLEAR FUELS; NUCLEONS; RADIATIONS; REACTOR MATERIALS
Optional Information
- Notes
- 4 refs, 5 figs, 2 tabs