The AECL's research reactor analysis methodology
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--.