Development of a continuous-energy version of KENO V.a

Journal Article · Tue Dec 31 04:00:00 EST 1996 · Transactions of the American Nuclear Society

OSTI ID:436942

Dunn, M E; Bentley, C L; Goluoglu, S; Paschal, L S ^[1]

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1. Univ. of Tennessee, Knoxville, TN (United States); and others

The KENO V.a code is a multigroup Monte Carlo code that solves the Boltzmann transport equation and is used extensively in the nuclear criticality safety community to calculate the effective multiplication factor k{sub eff} of systems containing fissile material. Due to the smaller amount of disk storage and CPU time required for multigroup calculations, multigroup approaches have been preferred over continuous-energy (point) approaches in the past to solve the transport equation. With the advent of high-performance computers, storage and CPU limitations are less restrictive, thereby making continuous-energy methods viable for transport calculations. Moreover, continuous-energy methods avoid many of the assumptions and approximations inherent in multigroup methods. Point cross sections provide sufficient detail of the cross-section energy dependence for most problems, and a single continuous-energy library can be used for a wide variety of problems. Currently, a continuous-energy version of KENO V.a does not exist, and the objective of this paper is to develop a new version of KENO V.a that utilizes continuous-energy cross sections.

• OSTI ID: 436942
• Report Number(s): CONF-9606116--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 74; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
66 PHYSICS
99 GENERAL AND MISCELLANEOUS
COMPUTERS
CRITICALITY
CROSS SECTIONS
K CODES
MULTIPLICATION FACTORS
NUCLEAR DATA COLLECTIONS
P CODES