Published 1995 | Version v1
Journal article

The AECL's research reactor analysis methodology

Creators

  • 1. Atomic Energy of Canada Ltd., Manitoba (Canada)

Description

As the cost of developing completely new computer codes becomes prohibitive, designers of nuclear facilities are turning to more cost-effective approaches for meeting increasingly strict regulatory requirements applied to safety-related analysis. For designing and licensing the MAPLE family of research reactors, Atomic Energy of Canada Ltd. (AECL) is employing the strategy of adapting major existing codes by linking them together within networks of custom-built interface software. This approach builds on the international investment in developing, maintaining, and verifying existing primary codes and focuses on the less onerous development of interface codes. The resultant code systems are then validated for the new applications of interest

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
73
Journal Page Range
p. 398-400.
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
28019213
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ATOMIC ENERGY OF CANADA LTD; COMPUTER CODES; DESIGN; INVESTMENT; M CODES; NEUTRON TRANSPORT; RESEARCH REACTORS
Descriptors DEC
CANADIAN ORGANIZATIONS; NATIONAL ORGANIZATIONS; NEUTRAL-PARTICLE TRANSPORT; RADIATION TRANSPORT; REACTORS; RESEARCH AND TEST REACTORS

Optional Information

Secondary number(s)
CONF-951006--.