U. S. /JAERI calculational benchmarks for nuclear data and codes intercomparison

Conference · Sat Nov 01 04:00:00 EST 1986 · Fusion Technol.; (United States)

OSTI ID:7190781

Youssef, M; Jung, J; Sawan, M; Nakagawa, M; Mori, T; Kosako, K

Four calculational benchmarks were selected by the U.S. and JAERI to compare numerical results based on various transport codes and data bases developed individually by both parties. The benchmarks chosen are fusion-oriented. Data intercomparison were performed with the ENDF/B-IV, ENDF/B-V, and JENDL-3 evaluations. Both deterministic and Monte Carlo methods were used in the codes intercomparison. Among the codes considered are ONEDANT, ANISN-DD, DOT, MORSE, MCNP, and VIM. Results from these intercomparisons are presented in this paper.

• Research Organization: Mechanical, Aerospace and Nuclear Engineering, Univ. of California at Los Angeles, Los Angeles, CA 90024
• OSTI ID: 7190781
• Report Number(s): CONF-860652-
• Conference Information: Journal Name: Fusion Technol.; (United States) Journal Volume: 10:3
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200* -- Fusion Energy-- Fusion Power Plant Technology
A CODES
BENCHMARKS
COMPARATIVE EVALUATIONS
COMPUTER CODES
D CODES
DATA BASE MANAGEMENT
DATA COVARIANCES
JAERI
JAPANESE ORGANIZATIONS
M CODES
MANAGEMENT
MONTE CARLO METHOD
NATIONAL ORGANIZATIONS
NEUTRON TRANSPORT THEORY
NORTH AMERICA
O CODES
THERMONUCLEAR REACTORS
TRANSPORT THEORY
USA
V CODES