Development of a transient three-dimensional neutron transport code with feedback

Conference · Sun Nov 13 00:00:00 EST 1994

OSTI ID:135157

Waddell, Jr, M. W. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

A new code is being developed at the Y-12 Plant for solving the time-dependent, three-dimensional Boltzmann transport model with feedback. The new code, PADK, uses the quasi-static method in its adiabatic form and is to be utilized to analyze hypothetical criticality accidents. A description of the code along with preliminary results without feedback are presented in this paper. The code is applied to 2 standard benchmark problems and the results are compared to another method. Also, the code is used to model the GODIVA reactor. Further work needed to be completed is described.

• 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)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 135157
• Report Number(s): Y/DD-642; CONF-941102-47; ON: DE96002328; TRN: 96:000197
• Resource Relation: Conference: Winter Meeting of the American Nuclear Society (ANS), Washington, DC (United States), 13-18 Nov 1994; Other Information: PBD: 19 Jul 1994
• Country of Publication: United States
• Language: English

Related Subjects

66 PHYSICS
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
BOLTZMANN EQUATION
P CODES
NEUTRON TRANSPORT THEORY
BENCHMARKS
FEEDBACK
THREE-DIMENSIONAL CALCULATIONS
CRITICALITY
Nuclear Criticality Safety Program (NCSP)
PADK
Preliminary Results