Published 2007 | Version v1
Miscellaneous

Passive safety features in the ACR-1000

  • 1. Atomic Energy of Canada Limited, Mississauga, Ontario (Canada)

Description

The Advanced CANDU Reactor (ACR) is a Generation III+ pressure tube type reactor using light water coolant and heavy water moderator. The ACR-1000 reactor design is an evolutionary extension of the proven CANDU reactor design. ACR utilizes passive, stored-energy, natural circulation, and gravity features for: Reactor shutdown; Cooling of the heat transport system when forced circulation is unavailable; Core refill and fuel cooling following a LOCA; Post-accident pressure and temperature suppression inside containment; Emergency feedwater supply to the steam generators; and, Mitigation of postulated beyond design basis accidents. This paper describes passive design elements and how they complement the active features, enhance reliability and improve the overall safety margins. (author)

Part of:
Embracing the future: Canada's nuclear renewal and growth. 28th annual conference of the Canadian Nuclear Society and 31st CNS/CNA student conference

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
0-919784-88-7
Imprint Title
Embracing the future: Canada's nuclear renewal and growth. 28th annual conference of the Canadian Nuclear Society and 31st CNS/CNA student conference
Imprint Pagination
303 Megabytes
Journal Page Range
[13 p.]

Conference

Title
Canada's nuclear renewal and growth
Acronym
28. Annual conference of the Canadian Nuclear Society and 31. CNS/CNA student conference on embracing the future
Dates
3-6 Jun 2007
Place
Saint John, New Brunswick (Canada)

Optional Information

Notes
Paper T8005; 6 refs., 6 figs.