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 CenterFiles
44122668.pdf
Files
(145.0 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:78a0c72c64c519ccb8b9df9329c04104
|
145.0 kB | Preview Download |
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