Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Severe accident research in Canada

Journal Article · · Transactions of the American Nuclear Society
OSTI ID:182078
 [1]
  1. AECL Research, Pinawa, Manitoba (Canada)

The reactor safety research program in Canada not only recognizes the unique features of the CANDU reactor, but is supplemented by a strong interaction with the LWR research community. This is especially so in the area of severe accidents. We participate in international programs such as Phebus FP and CSARP to take advantage of cooperative efforts on phenomena that are generic to all reactors, but also have our distinct programs in Canada on severe fuel damage, fission product chemistry, aerosol behaviour and hydrogen combustion and mitigation. These programs address the characteristics of Canadian nuclear fuel and containment design, and our own series of severe accident scenarios. The scope of the R&D encompasses separate effects experiments, model development and code development, leading to validation testing in several large integral test facilities including the Radioiodine Test Facility and the Blowdown Test Facility in the NRU reactor. We also have extensive hydrogen combustion test facilities including the Large Scale Vented Combustion Test Facility now under construction. The essence of the program is described with examples from recent experiments and analysis.

OSTI ID:
182078
Report Number(s):
CONF-940501--
Journal Information:
Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Journal Issue: Suppl.1 Vol. 70; ISSN 0003-018X; ISSN TANSAO
Country of Publication:
United States
Language:
English

Similar Records

Fuel behavior and fission product release in the BTF-107 severe-fuel-damage experiment
Conference · Thu Dec 31 23:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States) · OSTI ID:6844062

Severe accidents and CANDU - a challenge for designers and regulators
Conference · Thu Dec 31 23:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States) · OSTI ID:6024012

Full-length fuel rod behavior under severe accident conditions
Technical Report · Mon Nov 30 23:00:00 EST 1992 · OSTI ID:7042819