Parallel collision probability solutions with GTRAN2 and P4

Journal Article · Sat Dec 31 04:00:00 EST 1994 · Transactions of the American Nuclear Society

OSTI ID:89098

Slater, S M; Vujic, J L ^[1]

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1. Univ. of California, Berkeley, CA (United States)

The solution of the Boltzmann transport equation for the neutron distribution in a nuclear reactor remains one of the most cornputationally intensive applications in engineering and science. A three-dimensional transport analysis of the entire reactor core is still beyond the capability of current machines (and algorithms), but with the use of workstations as nodes in a distributed computing environment, this large-scale problem may soon be solved. The GTRAN2 code uses the exact collision probability formalism to solve the multigroup integral transport equation in general two-dimensional geometries and employs combinatorial geometry to describe complex and irregular configurations. The code first performs ray tracing to generate the geometric data needed throughout the analysis. The next step involves numerical integration, which calculates the collision/transfer probability (CTP) matrices. The resulting set of eigenvalue nations is then solved by an iterative method.

• OSTI ID: 89098
• Report Number(s): CONF-941102--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 71; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS
BOLTZMANN EQUATION
COLLISION INTEGRALS
G CODES
PROBABILITY
REACTOR PHYSICS
TRANSPORT THEORY