Published 1995 | Version v1
Journal article Metadata-only

Evaluation of several parallel algorithms for KENO V.a

Creators

  • 1. Univ. of Tennessee, Knoxville, TN (United States)
  • 2. Lockheed Martin Energy Systems, Inc., Oak Ridge, TN (United States)

Description

In a previous paper, a parallel version of the Monte Carlo criticality safety code KENO Va was presented based on only one parallel algorithm. Results for a light water reactor problem using this algorithm on the Kendall Square Research supercomputer 3 (KSRI) at Oak Ridge National Laboratory (ORNL) gave speedup factors of up to 34. In this paper, we present results for another real-life problem, namely, the fuel drain tanks (FDTs) associated with the molten salt reactor experiment. The FDT results have been obtained using seven different algorithms the one algorithm discussed in Ref. 1 plus six additional algorithms. In addition, the results of a parametric study in which the number of generations is varied are also presented in this paper

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
73
Journal Page Range
p. 183-184.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
Winter meeting of the American Nuclear Society (ANS).
Dates
29 Oct - 1 Nov 1995.
Place
San Francisco, CA (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28019200
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ALGORITHMS; EFFICIENCY; EVALUATION; K CODES; MSRE REACTOR; MULTIPLICATION FACTORS; REACTOR SAFETY; TANKS
Descriptors DEC
COMPUTER CODES; CONTAINERS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GRAPHITE MODERATED REACTORS; MOLTEN SALT COOLED REACTORS; MOLTEN SALT REACTORS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; THERMAL REACTORS

Optional Information

Secondary number(s)
CONF-951006--.