Published May 2002 | Version v1
Miscellaneous

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

Part of:
Proceedings of the KNS-KARP Joint spring meeting

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