Shielding analysis of storage canister of neutron source for exponential experiment
- 1. KAERI, Taejon (Korea, Republic of)
Description
Shielding analysis of storage canister of neutron source for exponential experiment has been carried out. The Shielding analysis code used in this study was MCNP-4B. Storage canister of neutron source is composed of an internal and external shielding. The dose rate at the container surface has been estimated for the storage canister with a Cf-252 spontaneous neutron point source. Neutron source is located at the center of the storage canister. A recommendable distance from the safety point of view has been made by calculating the position which gives 1 mrem/h dose rate. Dose rate at the side and top surface of the internal shielding appear to be 1.38 and 1.45 rem/h, respectively. The distance for the safety work seems to be 372 cm and 382 cm. Dose rate at the side surface of the external shielding seems to be 0.015 rem/h and accordingly the distance for the safety work is 117 cm
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS-KARP Joint spring meeting
- Imprint Pagination
- [CD-ROM]
- Journal Page Range
- [13 p.]
Conference
- Title
- 2002 joint spring meeting of the KNS-KARP
- Dates
- 23-24 May 2002
- Place
- Gwangju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 34010020
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- DOSE RATES; NEUTRON SOURCES; SAFETY; SHIELDING; STORAGE
- Descriptors DEC
- PARTICLE SOURCES; RADIATION SOURCES
Optional Information
- Notes
- 5 refs, 9 figs, 5 tabs