Published 2011 | Version v1
Miscellaneous Open

Current Progress and Preliminary Shielding Design Analysis for Gamma Cell using MCNP

  • 1. Malaysian Nuclear Agency, Bangi, Kajang, Selangor (Malaysia), TEchnical Support Div.

Description

The design of indigenous gamma cell based on the basic safety criteria published by IAEA and AELB has been completed by PDC. One of the important safety criteria for designing gamma cell is shielding design. For this gamma cell, shielding thickness has been calculated manually and the shielding concept was designed based on the past experience in the development of other nuclear equipment and facilities. MCNP software has been used for verification to ensure the shielding design is complying to the requirement. The paper discussed about the preliminary result of shielding design of indigenous gamma cell using MCNP software. (author)

Availability note (English)

Also available in Malaysian Nuclear Agency Document Delivery Center

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Additional details

Publishing Information

Imprint Pagination
2 p.
Report number
INIS-MY--2013-147

Conference

Title
Nuclear Technical Convention 2011
Acronym
NTC 2011
Dates
13-15 Sep 2011
Place
Bangi (Malaysia)

INIS

Country of Publication
Malaysia
Country of Input or Organization
Malaysia
INIS RN
44122668
Subject category
S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER CODES; DESIGN; GAMMA RADIATION; MONTE CARLO METHOD; SHIELDING; SHIELDING MATERIALS
Descriptors DEC
CALCULATION METHODS; ELECTROMAGNETIC RADIATION; IONIZING RADIATIONS; MATERIALS; RADIATIONS

Optional Information

Notes
Oral presentation. 11 slides