Implementation of Surface Detector Option in SCALE SAS4 Shielding Module
The Shielding Analysis Sequence No. 4 (SAS4) in the Standardized Cask Analysis and Licensing Evaluation System (SCALE) is designed to aid the novice user in the preparation of detailed three-dimensional models and radiation protection studies of transportation or storage packages containing spent fuel from a nuclear reactor facility. The underlying methodology in these analyses is the Monte Carlo particle-tracking approach as incorporated into the MORSE-SGC computer code. The use of these basic procedures is enhanced via the automatic generation of the biasing parameters in the SAS4 sequence, which dramatically increases the calculational efficiency of most standard shielding problems. Until recently the primary mechanism for dose estimates in SAS4 was the use of point detectors, which were effective for single-dose locations, but inefficient for quantification of dose-rate profiles. This paper describes the implementation of a new surface detector option for SAS4 with automatic discretization of the detector surface into multiple segments or subdetectors. Results from several sample problems are given and discussed.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy, Science and Technology (NE) (US)
- DOE Contract Number:
- AC05-96OR22464
- OSTI ID:
- 10781
- Report Number(s):
- ORNL/CP-104463; EX 02 MM 12 0; EX 02 MM 12 0; TRN: US0103846
- Resource Relation:
- Conference: 9th International Conference on radiation Shielding, ICRS-9, Tsukuba (JP), 11/17/1999--11/22/1999; Other Information: PBD: 17 Nov 1999
- Country of Publication:
- United States
- Language:
- English
Similar Records
Applications of SAS4 Monte Carlo shielding sequence to deep-penetration problems
Evaluation of shielding analysis methods in spent-fuel cask environments