Scale-PC Shielding Analysis Sequences
Conference
·
OSTI ID:245072
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Computational Physics and Engineering Division
The SCALE computational system is a modular code system for analyses of nuclear fuel facility and package designs. With the release of SCALE-PC Version 4.3, the radiation shielding analysis community now has the capability to execute the SCALE shielding analysis sequences contained in the control modules SAS1, SAS2, SAS3, and SAS4 on a MS-DOS personal computer (PC). In addition, SCALE-PC includes two new sequences, QADS and ORIGEN-ARP. The capabilities of each sequence are presented, along with example applications.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). Computational Physics and Engineering Division
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC05-96OR22464
- OSTI ID:
- 245072
- Report Number(s):
- CONF-960415-35; ON: DE96008092; TRN: 96:015964
- Resource Relation:
- Conference: American Nuclear Society (ANS) Radiation Protection and Shielding Division Topical Meeting on Advancements and Applications in Radiation Protection and Shielding, PC Applications Session, Falmouth, MA (United States), 21-25 Apr 1996; Other Information: PBD: [1996]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
97 MATHEMATICS AND COMPUTING
FUEL FABRICATION PLANTS
SAFETY
PACKAGING
CONTAINERS
S CODES
CRITICALITY
DESIGN
SHIELDING
HEAT TRANSFER
SPENT FUELS
SOURCE TERMS
NUCLEAR DECAY
BURNUP
Nuclear Criticality Safety Program (NCSP)
Modular Code System
Nuclear Fuel Facility
Package Designs
Personal Computer (PC)
Radiation Shielding Analysis
Material Information Processor
Bondarenko Factor Method (BONAMI)
ORIGEN-ARP
Light-Water-Reactor (LWR)
Spent Fuel Analyses
Monte Carlo Shielding Code
FUEL FABRICATION PLANTS
SAFETY
PACKAGING
CONTAINERS
S CODES
CRITICALITY
DESIGN
SHIELDING
HEAT TRANSFER
SPENT FUELS
SOURCE TERMS
NUCLEAR DECAY
BURNUP
Nuclear Criticality Safety Program (NCSP)
Modular Code System
Nuclear Fuel Facility
Package Designs
Personal Computer (PC)
Radiation Shielding Analysis
Material Information Processor
Bondarenko Factor Method (BONAMI)
ORIGEN-ARP
Light-Water-Reactor (LWR)
Spent Fuel Analyses
Monte Carlo Shielding Code