Deterministic Methods for Time-Dependent Stochastic Neutron Transport
Conference
·
OSTI ID:956445
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
A numerical method is presented for solving the time-dependent survival probability equation in general (lD/2D/3D) geometries using the multi group SN method. Although this equation was first formulated by Bell in the early 1960's, it has only been applied to stationary systems (for other than idealized point models) until recently, and detailed descriptions of numerical solution techniques are lacking in the literature. This paper presents such a description and applies it to a dynamic system representative of a figurative criticality accident scenario.
- Research Organization:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC52-06NA25396
- OSTI ID:
- 956445
- Report Number(s):
- LA-UR-09-01057; LA-UR-09-1057; TRN: US1004066
- Resource Relation:
- Conference: Int. Conf. on Mathematics, Comp. Methods, & Reactor Physics (M&C 2009) , Saratoga Springs, NY (United States), 4 May 2009
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
CRITICALITY
NEUTRON TRANSPORT
PROBABILITY
RADIATION ACCIDENTS
REACTOR PHYSICS
TIME DEPENDENCE
CALCULATION METHODS
Nuclear Criticality Safety Program (NCSP)
Numerical Method
Multi Group SN Method
Figurative Criticality Accident Scenario
Stochastic Neutron Transport
Probability of Initiation
Survival Probability
97 MATHEMATICS AND COMPUTING
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
CRITICALITY
NEUTRON TRANSPORT
PROBABILITY
RADIATION ACCIDENTS
REACTOR PHYSICS
TIME DEPENDENCE
CALCULATION METHODS
Nuclear Criticality Safety Program (NCSP)
Numerical Method
Multi Group SN Method
Figurative Criticality Accident Scenario
Stochastic Neutron Transport
Probability of Initiation
Survival Probability