An accurate determination of the flux within a slab
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:6904528
- Univ. of Arizona, Tucson, AZ (United States)
- Politecnico di Torino (Italy)
During the past decade, several articles have been written concerning accurate solutions to the monoenergetic neutron transport equation in infinite and semi-infinite geometries. The numerical formulations found in these articles were based primarily on the extensive theoretical investigations performed by the [open quotes]transport greats[close quotes] such as Chandrasekhar, Busbridge, Sobolev, and Ivanov, to name a few. The development of numerical solutions in infinite and semi-infinite geometries represents an example of how mathematical transport theory can be utilized to provide highly accurate and efficient numerical transport solutions. These solutions, or analytical benchmarks, are useful as [open quotes]industry standards,[close quotes] which provide guidance to code developers and promote learning in the classroom. The high accuracy of these benchmarks is directly attributable to the rapid advancement of the state of computing and computational methods. Transport calculations that were beyond the capability of the [open quotes]supercomputers[close quotes] of just a few years ago are now possible at one's desk. In this paper, we again build upon the past to tackle the slab problem, which is of the next level of difficulty in comparison to infinite media problems. The formulation is based on the monoenergetic Green's function, which is the most fundamental transport solution. This method of solution requires a fast and accurate evaluation of the Green's function, which, with today's computational power, is now readily available.
- OSTI ID:
- 6904528
- Report Number(s):
- CONF-931160--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 69
- Country of Publication:
- United States
- Language:
- English
Similar Records
Green`s function method for the monoenergetic transport equation in heterogeneous plane geometry
The infinite medium Green's function for neutron transport in plane geometry 40 years later
Analytical Radiation Transport Benchmarks for the Next Century
Journal Article
·
Sat Dec 30 23:00:00 EST 1995
· Transactions of the American Nuclear Society
·
OSTI ID:411636
The infinite medium Green's function for neutron transport in plane geometry 40 years later
Conference
·
Thu Dec 31 23:00:00 EST 1992
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:6947398
Analytical Radiation Transport Benchmarks for the Next Century
Technical Report
·
Tue Jan 25 23:00:00 EST 2005
·
OSTI ID:836281