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Effects of Transport and Scattering Pattern Approximations on Criticality Calculations for Spent Fuel Pools and Casks

Conference · · Transactions of the American Nuclear Society
OSTI ID:6109402
 [1];  [1]
  1. Rensselaer Polytechnic Institute, Troy, NY (United States)
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Abstract not provided.

Research Organization:
Rensselaer Polytechnic Institute, Troy, NY (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
OSTI ID:
6109402
Report Number(s):
CONF-821103-
Journal Information:
Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 43; ISSN TANSA; ISSN 0003-018X
Publisher:
American Nuclear Society
Country of Publication:
United States
Language:
English

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Related Subjects

050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
42 ENGINEERING
420203 -- Engineering-- Handling Equipment & Procedures
97 MATHEMATICS AND COMPUTING
ACCURACY
Accuracy
CASKS
COMPUTER CALCULATIONS
CONTAINERS
CRITICALITY
Casks
Computer Calculations
Containers
Criticality
DESIGN
Design
Engineering
FUEL POOLS
FUEL RACKS
Fuel Pools
Fuel Racks
MECHANICAL STRUCTURES
MONTE CARLO METHOD
Mechanical Structures
Monte Carlo Method
NEUTRON TRANSPORT THEORY
Neutron Transport Theory
Nuclear Criticality Safety Program (NCSP)
Nuclear Fuel Cycle and Fuel Materials
SPENT FUEL CASKS
SUPPORTS
Spent Fuel Casks
Supports
TRANSPORT THEORY
Transport Theory