Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

Standardized Analyses of Nuclear Shipping Containers

Conference ·
OSTI ID:6008979
 [1];  [1];  [1];  [1];  [1];  [1];  [1]
  1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
+ Show Author Affiliations
This paper describes improved capabilities for analyses of nuclear fuel shipping containers within SCALE -- a modular code system for Standardized Computer Analyses for Licensing Evaluation. Criticality analysis improvements include the new KENO V, a code which contains an enhanced geometry package and a new control module which uses KENO V and allows a criticality search on optimum pitch (maximum k-effective) to be performed. The SAS2 sequence is a new shielding analysis module which couples fuel burnup, source term generation, and radial cask shielding. The SAS5 shielding sequence allows a multidimensional Monte Carlo analysis of a shipping cask with code generated biasing of the particle histories. The thermal analysis sequence (HTAS1) provides an easy-to-use tool for evaluating a shipping cask response to the accident capability of the SCALE system to provide the cask designer or evaluator with a computational system that provides the automated procedures and easy-to-understand input that leads to standardization.
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:
W-7405-ENG-26
OSTI ID:
6008979
Report Number(s):
CONF-830528-12; ON: DE83012634
Country of Publication:
United States
Language:
English

Similar Records

SCALE: a modular code system for performing standardized computer analyses for licensing evaluation
Technical Report · Thu Dec 31 23:00:00 EST 1981 · OSTI ID:5358952
Executive summary: Reactor critical benchmark calculations for burnup credit applications
Technical Report · Sat Mar 31 23:00:00 EST 1990 · OSTI ID:6882841
Automated shielding analysis sequences for spent fuel casks
Conference · Wed Dec 31 23:00:00 EST 1986 · OSTI ID:7061172

Related Subjects

050900 -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
420204* -- Engineering-- Shipping Containers
97 MATHEMATICS AND COMPUTING
CASKS
COMPUTERIZED SIMULATION
CONTAINERS
CRITICALITY
ENERGY TRANSFER
EVALUATION
Fuel Assembly Cross Sections
HEAT TRANSFER
KENO V
Monte Carlo
Nuclear Criticality Safety Program (NCSP)
Pressurized Water Reactor (PWR)
SHIELDING
SIMULATION
Shielding Analysis Sequence No. 2 (SAS2)
Shipping Cask Model
Standardized Computer Analyses for Licensing Evaluation (SCALE)
Thermal Analysis Sequence (HTAS1)