SCALE-4 (Standardized Computer Analyses for Licensing Evaluation): An Improved Computational System for Spent-Fuel Cask Analysis
Conference
·
OSTI ID:6176812
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
The purpose of this paper is to provide specific information regarding improvements available with Version 4.0 of the SCALE system and discuss the future of SCALE within the current computing and regulatory environment. The emphasis focuses on the improvements in SCALE-4 over that available in SCALE-3.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Nuclear Regulatory Commission (USNRC), Office of Nuclear Material Safety and Safeguards
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6176812
- Report Number(s):
- CONF-890631-49; ON: DE89013535
- Resource Relation:
- Conference: PATRAM '89: 9. International Symposium on Packaging and Transporting of Radioactive Materials, Washington, DC (United States), 11-16 Jun 1989; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
97 MATHEMATICS AND COMPUTING
SPENT FUEL CASKS
EVALUATION
CRITICALITY
HEAT TRANSFER
HIGH-LEVEL RADIOACTIVE WASTES
S CODES
SHIELDING
TRANSPORT REGULATIONS
US NRC
WASTE TRANSPORTATION
CASKS
COMPUTER CODES
CONTAINERS
ENERGY TRANSFER
MANAGEMENT
MATERIALS
NATIONAL ORGANIZATIONS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REGULATIONS
TRANSPORT
US ORGANIZATIONS
WASTE MANAGEMENT
WASTES
Nuclear Criticality Safety Program (NCSP)
Heat Transfer
High-Level Waste (HLW)
Standardized Computer Analyses for Licensing Evaluation (SCALE)
Monte Carlo Criticality Code
KENO IV
JUNEBUG Package
FORTRAIN 77
Evaluated Nuclear Data File (ENDF)
050900* - Nuclear Fuels- Transport
Handling
& Storage
990220 - Computers
Computerized Models
& Computer Programs- (1987-1989)
97 MATHEMATICS AND COMPUTING
SPENT FUEL CASKS
EVALUATION
CRITICALITY
HEAT TRANSFER
HIGH-LEVEL RADIOACTIVE WASTES
S CODES
SHIELDING
TRANSPORT REGULATIONS
US NRC
WASTE TRANSPORTATION
CASKS
COMPUTER CODES
CONTAINERS
ENERGY TRANSFER
MANAGEMENT
MATERIALS
NATIONAL ORGANIZATIONS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REGULATIONS
TRANSPORT
US ORGANIZATIONS
WASTE MANAGEMENT
WASTES
Nuclear Criticality Safety Program (NCSP)
Heat Transfer
High-Level Waste (HLW)
Standardized Computer Analyses for Licensing Evaluation (SCALE)
Monte Carlo Criticality Code
KENO IV
JUNEBUG Package
FORTRAIN 77
Evaluated Nuclear Data File (ENDF)
050900* - Nuclear Fuels- Transport
Handling
& Storage
990220 - Computers
Computerized Models
& Computer Programs- (1987-1989)