Filters
Results 1 - 1 of 1
Results 1 - 1 of 1.
Search took: 0.016 seconds
AbstractAbstract
[en] The Canadian Nuclear Fuel Waste Management Program was initiated in 1978 to develop a concept for safe disposal of nuclear fuel waste (intact used nuclear fuel or high-level waste from any future reprocessing of used fuel) from CANDU reactors. The concept includes the immobilization of nuclear fuel waste and emplacement of the waste in an engineered vault, deep underground in a stable rock formation within the Canadian Shield. In 1994, AECL submitted an environmental and safety assessment of the disposal concept in the form of an Environmental Impact Statement or EIS for regulatory, scientific and public reviews. Ontario Hydro's contribution to the EIS included the preclosure assessment consisting of the safety and environmental implications of the construction, operation and decommissioning (closure) of a conceptual used-fuel disposal centre (UFDC), plus transportation of used fuel from storage at reactor sites to the UFDC. In the EIS, the environmental impact from routine emissions from the UFDC during the operation phase was calculated in a deterministic mode using single-valued constants representing the geometric mean or the average value of the input parameters in the preclosure model PREAC (Preclosure Radiological Environmental Assessment Code). A qualitative estimate of the range of uncertainty associated with the preclosure model dose predictions was about an order of magnitude based on a review of the expected range of input parameter values. This paper examines the time-behaviour of the preclosure system and provides a quantitative estimate of the uncertainty, as determined through the use of probabilistic techniques, associated with the potential radiological impact from the same chronic UFDC radionuclide emissions during the preclosure phase. The individual dose to a member of the critical group assumed to be living near the UFDC has been assessed for selected key radionuclides and exposure pathways identified in the EIS. The purpose of this post-EIS probabilistic analysis is to test and support the results of the deterministic analysis submitted in the EIS. (author)
Primary Subject
Secondary Subject
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); 1 v; ISBN 0-919784-44-5;
; 1996; p. 8.99-8.108; International conference on deep geological disposal of radioactive waste; Winnipeg, Manitoba (Canada); 16-19 Sep 1996; Available from Canadian Nuclear Society, 144 Front Street, Toronto, Ontario M5J 2L7; 10 refs., 1 tab., 5 figs.

Record Type
Book
Literature Type
Conference
Country of publication
DEVELOPED COUNTRIES, ENVIRONMENTAL TRANSPORT, GEOLOGIC STRUCTURES, GEOLOGY, HEAVY WATER MODERATED REACTORS, MANAGEMENT, MASS TRANSFER, MATERIALS, NORTH AMERICA, POWER REACTORS, PRESSURE TUBE REACTORS, RADIOACTIVE MATERIALS, RADIOACTIVE WASTES, REACTORS, THERMAL REACTORS, WASTE DISPOSAL, WASTE MANAGEMENT, WASTES
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue