Modification and benchmarking of SKYSHINE-III for use with ISFSI cask arrays
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:552559
- Georgia Institute of Technology, Atlanta, GA (United States)
- NAC International, Norcross, GA (United States)
Dry cask storage arrays are becoming more and more common at nuclear power plants in the United States. Title 10 of the Code of Federal Regulations, Part 72, limits doses at the controlled area boundary of these independent spent-fuel storage installations (ISFSI) to 0.25 mSv (25 mrem)/yr. The minimum controlled area boundaries of such a facility are determined by cask array dose calculations, which include direct radiation and radiation scattered by the atmosphere, also known as skyshine. NAC International (NAC) uses SKYSHINE-III to calculate the gamma-ray and neutron dose rates as a function of distance from ISFSI arrays. In this paper, we present modifications to the SKYSHINE-III that more explicitly model cask arrays. In addition, we have benchmarked the radiation transport methods used in SKYSHINE-III against {sup 60}Co gamma-ray experiments and MCNP neutron calculations.
- OSTI ID:
- 552559
- Report Number(s):
- CONF-971125--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 77; ISSN TANSAO; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
Similar Records
Characterization of neutron sources from spent fuel casks. [Skyshine]
Hybrid Skyshine Calculations for Complex Neutron and Gamma-Ray Sources
Methodology for calculating dose rates from storage cask arrays using MCNP
Conference
·
Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:5989933
Hybrid Skyshine Calculations for Complex Neutron and Gamma-Ray Sources
Journal Article
·
Sun Oct 15 00:00:00 EDT 2000
· Nuclear Science and Engineering
·
OSTI ID:20804671
Methodology for calculating dose rates from storage cask arrays using MCNP
Journal Article
·
Sun Nov 30 23:00:00 EST 1997
· Transactions of the American Nuclear Society
·
OSTI ID:552562