Benchmarking Computer Codes for Cask Development
Conference
·
OSTI ID:6440049
- Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)
Sandia National Laboratories has taken the lead in developing a series of standard problems to evaluate structural and thermal computer codes used in the development of nuclear materials packaging for the United States Department of Energy (DOE). These problems were designed to simulate the hypothetical accident conditions given in Title 10 of the Code of Federal Regulation, Part 71 (10CFR71) while retaining simple geometries. This problem set exercises the ability of the codes to model pertinent physical phenomena without requiring extensive use of computer resources. The development of the standard problem set has involved both national and international consensus groups. Nationally, both the problems and consensus solutions have been developed and discussed at Industry/Government Joint Thermal and Structural Code Information Exchange meetings. Internationally, the Organization for Economic Cooperation and Development (OECD), through its Nuclear Energy Agency's Committee on Reactor Physics, has hosted a series of Specialists' Meetings on Heat Transfer to develop standard thermal problems and solutions. Each of these activities is represented in the standard problem set and the consensus solutions. This paper presents a brief overview of the structural and thermal problem sets.
- Research Organization:
- Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6440049
- Report Number(s):
- SAND-87-1174C; CONF-870713-36; ON: DE87012733
- Country of Publication:
- United States
- Language:
- English
Similar Records
Benchmarking computer codes for cask development
Sample problem manual for benchmarking of cask analysis codes
Solutions obtained to international heat transfer benchmarking problems for nuclear fuel casks using Q/TRAN
Conference
·
Wed Jul 01 00:00:00 EDT 1987
· Nucl. Mater. Manage. Annu. Meet. Proc.; (United States)
·
OSTI ID:5793714
Sample problem manual for benchmarking of cask analysis codes
Technical Report
·
Sun Jan 31 23:00:00 EST 1988
·
OSTI ID:5498009
Solutions obtained to international heat transfer benchmarking problems for nuclear fuel casks using Q/TRAN
Technical Report
·
Sat Jan 31 23:00:00 EST 1987
·
OSTI ID:6826030
Related Subjects
050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
96 KNOWLEDGE MANAGEMENT AND PRESERVATION
97 MATHEMATICS AND COMPUTING
A CODES
ACCIDENTS
C CODES
CASKS
COMPUTER CODES
CONTAINERS
CRITICALITY
Codes
D CODES
DEFORMATION
DESIGN
ENERGY TRANSFER
FIRES
H CODES
HEAT TRANSFER
INTERNATIONAL ORGANIZATIONS
LICENSING
MATERIALS
MATERIALS TESTING
MECHANICAL TESTS
Nuclear Criticality Safety Program (NCSP)
Nuclear Materials Packaging
OECD
PACKAGING
PERFORMANCE TESTING
Q CODES
RADIOACTIVE MATERIALS
Sandia National Laboratories
Standard Problems
Structural and Thermal Computer
Structural and Thermal Computer Codes
Structural and Thermal Problem Sets
T CODES
TESTING
TRANSPORT
Title 10 of the Code of Federal Regulation
Part 71 (10CFR71)
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
96 KNOWLEDGE MANAGEMENT AND PRESERVATION
97 MATHEMATICS AND COMPUTING
A CODES
ACCIDENTS
C CODES
CASKS
COMPUTER CODES
CONTAINERS
CRITICALITY
Codes
D CODES
DEFORMATION
DESIGN
ENERGY TRANSFER
FIRES
H CODES
HEAT TRANSFER
INTERNATIONAL ORGANIZATIONS
LICENSING
MATERIALS
MATERIALS TESTING
MECHANICAL TESTS
Nuclear Criticality Safety Program (NCSP)
Nuclear Materials Packaging
OECD
PACKAGING
PERFORMANCE TESTING
Q CODES
RADIOACTIVE MATERIALS
Sandia National Laboratories
Standard Problems
Structural and Thermal Computer
Structural and Thermal Computer Codes
Structural and Thermal Problem Sets
T CODES
TESTING
TRANSPORT
Title 10 of the Code of Federal Regulation
Part 71 (10CFR71)