Published 2005 | Version v1
Miscellaneous

Safety analysis for non-power reactors

Creators

  • 1. Nuclear Safety Solutions, Toronto, Ontario (Canada)

Description

Non-power reactors have been operating in Canada since 1945, with NRU (National Research Universal, 1957) being the oldest operating non-power reactor. Presently, there are five generic 'types' of non-power reactors: NRU, ZED-2, SLOWPOKE, MNR and MAPLE, the latter undergoing commissioning as the MDS Medical Isotope Reactor. These reactors range in thermal power from 200 Watts to more than 100 MW. Other non-power reactors are likely to be built for new applications and to replace older reactors. The uniqueness of each reactor, the wide range of power levels and the evolution of safety philosophy over time have lead to non-uniform practices for safety analysis. This non-uniformity may be a problem for the preparation by the licensee and review by the regulator of the safety analysis report required for licensing of the reactor facility. Clearly, there is no universally applicable practice, while at the same time, expectations for safety analyses have evolved in order to demonstrate higher levels of overall safety. This paper examines a new 'graded approach' to preparing the safety analysis report for reactors of diverse features but with a common standard of safety. It discusses necessary content, methods and the training and qualification of the safety analyst. (author)

Part of:
26th Annual CNS conference; 29th CNS/CNA student conference

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
0-919784-82-8
Imprint Title
26th Annual CNS conference; 29th CNS/CNA student conference
Imprint Pagination
168 Megabytes
Journal Page Range
[12 p.]

Conference

Title
26. Annual CNS conference; 29. CNS/CNA student conference. Proceedings
Dates
12-15 Jun 2005
Place
Toronto, Ontario (Canada)

Optional Information

Notes
3 refs., 2 tabs.