Reevaluation of the case, de Hoffman, and Placzek one-group neutron transport benchmark solution in plane geometry
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5157455
In a course on neutron transport theory and also in the analytical neutron transport theory literature, the pioneering work of Case et al. (CdHP) is often referenced. This work was truly a monumental effort in that it treated the fundamental mathematical properties of the one-group neutron Boltzmann equation in detail as well as the numerical evaluation of most of the resulting solutions. Many mathematically and numerically oriented dissertations were based on this classic monograph. In light of the considerable advances made both in numerical methods and computer technology since 1953, when the historic CdHP monograph first appeared, it seems appropriate to reevaluate the numerical benchmark solutions found therein with present-day computational technology. In most transport theory courses, the subject of proper benchmarking of numerical algorithms and transport codes is seldom addressed at any great length. This may be the reason that the benchmarking procedure is so rarely practiced in the nuclear community and when practiced is improperly applied. In this presentation, the development of a new benchmark for the one-group neutron flux in an infinite medium will be detailed with emphasis placed on the educational aspects of the benchmarking activity.
- Research Organization:
- Univ. of Arizona, Tucson (USA)
- OSTI ID:
- 5157455
- Report Number(s):
- CONF-860610-Summs.
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 52
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ALGORITHMS
BENCHMARKS
BOLTZMANN EQUATION
DIFFERENTIAL EQUATIONS
EQUATIONS
MATHEMATICAL LOGIC
MATHEMATICAL MODELS
NEUTRON TRANSPORT THEORY
ONE-GROUP THEORY
PARTIAL DIFFERENTIAL EQUATIONS
TRANSPORT THEORY
220100* -- Nuclear Reactor Technology-- Theory & Calculation
654003 -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ALGORITHMS
BENCHMARKS
BOLTZMANN EQUATION
DIFFERENTIAL EQUATIONS
EQUATIONS
MATHEMATICAL LOGIC
MATHEMATICAL MODELS
NEUTRON TRANSPORT THEORY
ONE-GROUP THEORY
PARTIAL DIFFERENTIAL EQUATIONS
TRANSPORT THEORY