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A statistical approach to nuclear fu...

Royal Military College of Canada (Canada)., Nuclear Engineering.

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A statistical approach to nuclear fuel design and performance.

紀錄類型:	書目-語言資料,印刷品 : Monograph/item
正題名/作者:	A statistical approach to nuclear fuel design and performance./
作者:	Cunning, Travis Andrew.
面頁冊數:	154 p.
附註:	Source: Masters Abstracts International, Volume: 52-03.
Contained By:	Masters Abstracts International52-03(E).
標題:	Engineering, Nuclear. -
電子資源:	http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=MR95039
ISBN:	9780494950395

A statistical approach to nuclear fuel design and performance.
Cunning, Travis Andrew.

A statistical approach to nuclear fuel design and performance. - 154 p.

Source: Masters Abstracts International, Volume: 52-03.

Thesis (M.A.Sc.)--Royal Military College of Canada (Canada), 2013.

As CANDU fuel failures can have significant economic and operational consequences on the Canadian nuclear power industry, it is essential that factors impacting fuel performance are adequately understood. Current industrial practice relies on deterministic safety analysis and the highly conservative "limit of operating envelope" approach, where all parameters are assumed to be at their limits simultaneously. This results in a conservative prediction of event consequences with little consideration given to the high quality and precision of current manufacturing processes.

ISBN: 9780494950395Subjects--Topical Terms:

1043651
Engineering, Nuclear.

A statistical approach to nuclear fuel design and performance.
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100 1 $a Cunning, Travis Andrew. $3 2099635
245 1 2 $a A statistical approach to nuclear fuel design and performance.
300 $a 154 p.
500 $a Source: Masters Abstracts International, Volume: 52-03.
502 $a Thesis (M.A.Sc.)--Royal Military College of Canada (Canada), 2013.
520 $a As CANDU fuel failures can have significant economic and operational consequences on the Canadian nuclear power industry, it is essential that factors impacting fuel performance are adequately understood. Current industrial practice relies on deterministic safety analysis and the highly conservative "limit of operating envelope" approach, where all parameters are assumed to be at their limits simultaneously. This results in a conservative prediction of event consequences with little consideration given to the high quality and precision of current manufacturing processes.
520 $a This study employs a novel approach to the prediction of CANDU fuel reliability. Probability distributions are fitted to actual fuel manufacturing datasets provided by Cameco Fuel Manufacturing, Inc. They are used to form input for two industry-standard fuel performance codes: ELESTRES for the steady-state case and ELOCA for the transient case---a hypothesized 80% reactor outlet header break loss of coolant accident. Using a Monte Carlo technique for input generation, 105 independent trials are conducted and probability distributions are fitted to key model output quantities. Comparing model output against recognized industrial acceptance criteria, no fuel failures are predicted for either case. Output distributions are well removed from failure limit values, implying that margin exists in current fuel manufacturing and design. To validate the results and attempt to reduce the simulation burden of the methodology, two dimensional reduction methods are assessed. Using just 36 trials, both methods are able to produce output distributions that agree strongly with those obtained via the brute-force Monte Carlo method, often to a relative discrepancy of less than 0.3% when predicting the first statistical moment, and a relative discrepancy of less than 5% when predicting the second statistical moment. In terms of global sensitivity, pellet density proves to have the greatest impact on fuel performance, with an average sensitivity index of 48.93% on key output quantities. Pellet grain size and dish depth are also significant contributors, at 31.53% and 13.46%, respectively. A traditional limit of operating envelope case is also evaluated. This case produces output values that exceed the maximum values observed during the 105 Monte Carlo trials for all output quantities of interest. In many cases the difference between the predictions of the two methods is very prominent, and the highly conservative nature of the deterministic approach is demonstrated.
520 $a A reliability analysis of CANDU fuel manufacturing parametric data, specifically pertaining to the quantification of fuel performance margins, has not been conducted previously.
520 $a Key Words: CANDU, nuclear fuel, Cameco, fuel manufacturing, fuel modelling, fuel performance, fuel reliability, ELESTRES, ELOCA, dimensional reduction methods, global sensitivity analysis, deterministic safety analysis, probabilistic safety analysis.
590 $a School code: 1103.
650 4 $a Engineering, Nuclear. $3 1043651
650 4 $a Chemistry, Nuclear. $3 1916260
650 4 $a Statistics. $3 517247
690 $a 0552
690 $a 0738
690 $a 0463
710 2 $a Royal Military College of Canada (Canada). $b Nuclear Engineering. $3 2099636
773 0 $t Masters Abstracts International $g 52-03(E).
790 $a 1103
791 $a M.A.Sc.
792 $a 2013
793 $a English
856 4 0 $u http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=MR95039