A Evaluation of Shielding Deficiency by Means of Gamma Scanning Test
Creators
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
In this paper the method to evaluate shielding deficiency by gamma scanning test was presented and verified theoretically by Monte Carlo code which is one of the best effective method for radiation shielding calculation. The cylindrical shielding model was selected to evaluate shielding deficiency by gamma scanning test. First, the reference shielding according to the design requirement of cask was fabricated specially and reference values were measured with Co-60 source and scintillation detector. As a result with which calculated the reference values, it is shown that maximum deficiency thickness for lead of true cylindrical shielding model was 12mm. To verify this, thickness of lead was calculated by MCNP code and maximum deficiency thickness was 11.6mm. The experimental result obtained by the use of reference shielding was in good agreement with the theoretical result within 4.1%. So, this method can be applied to inspect the shielding ability for great shielding or cask which the radioactive material is used. To perform measurement more exactly, the further work on the development of measuring equipment to display the results on the screen will be required
Additional details
Publishing Information
- Journal Title
- Journal of the Korean Society for Nondestructive Testing
- Journal Volume
- 14
- Journal Issue
- 4
- Series
- 13 refs, 6 figs, 4 tabs
- Journal Page Range
- p. 228-236
- ISSN
- 1225-7842
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 42102690
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- COMPUTER CALCULATIONS; DESIGN; M CODES; MONTE CARLO METHOD; RADIATIONS; RADIOACTIVE MATERIALS; SHIELDING
- Descriptors DEC
- CALCULATION METHODS; COMPUTER CODES; MATERIALS