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AbstractAbstract
[en] The computer codes RFSP-IST, WIMS-IST and DRAGON-IST were used to pre-simulate the Bruce A Nuclear Generating Station Unit 4 Restart Phase B commissioning physics tests. Comparisons between calculations and measurements have validated all Bruce A Restart accident analyses, previously done with the same computer codes and modelling methodologies. Post-simulations of Phase B commissioning physics tests were also performed, which differ from the pre-simulations mainly in the use of an improved methodology, the side-step method, for calculating the incremental cross-sections for reactivity devices. The post-simulation results showed better agreement with measurements than those of the pre-simulations, particularly for the reactivity worth of the liquid zone controllers. (author)
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Canadian Nuclear Society, Toronto, Ontario (Canada); 119 Megabytes; ISBN 0-919784-80-1;
; 2004; [16 p.]; 6. international conference on simulation methods in nuclear engineering; Montreal, Quebec (Canada); 12-15 Oct 2004; Available on Compact Disc from the Canadian Nuclear Society, Toronto, Ontario (Canada); 7 refs., 6 tabs., 5 figs.

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Czegeny, J.I., E-mail: Jim.Czegeny@Sympatico.ca, E-mail: j.czegeny@opg.com
6. CNS international conference on CANDU maintenance. Proceedings2003
6. CNS international conference on CANDU maintenance. Proceedings2003
AbstractAbstract
[en] In this paper we look respectively at three specific examples showing program strategies for maintenance management, organization and planning. Starting with preventive maintenance optimization, we will look at one Bruce B Predefined task on the Reactor Regulating System to illustrate reduced maintenance requirement, a maintenance management strategy. Next discussed is the organizational strategy at Darlington to have an engineering program meet the jurisdictional requirements for maintaining certification for TSSA registered pressure vessels. The last look-see will show the earned value of the planning for the first Pickering A unit to be returned to service. Finally all the above is tied together in a compare and contrast of what works and what could be improved upon. (author)
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Canadian Nuclear Society, Toronto, Ontario (Canada); 437 Megabytes; ISBN 0-919784-78-X;
; 2003; [11 p.]; 6. international conference on CANDU maintenance; Toronto, Ontario (Canada); 16-18 Nov 2003; Available from the Canadian Nuclear Society, Toronto, Ontario (Canada); 2 figs.

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AbstractAbstract
[en] The radiation-resistant polymer developed by the Savannah River National Laboratory is adaptable for multiple applications to enhance polymer endurance and effectiveness in radiation environments. SRNL offers to collaborate with TEPCO in evaluation, testing, and utilization of SRNL's radiation-resistant polymer in the D&D of the Fukushima Daiichi NPS. Refinement of the scope and associated costs will be conducted in consultation with TECPO.
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27 Sep 2017; 2 p; OSTIID--1395264; AC09-08SR22470; Available from http://sti.srs.gov/fulltext/SRNL-TR-2017-00345.pdf; PURL: http://www.osti.gov/servlets/purl/1395264/
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AbstractAbstract
[en] Short communication
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AbstractAbstract
[en] Risk comparison is essential for effective societal and individual decision-making. After the Fukushima disaster, studies compared radiation and other disaster-related risks to determine the effective prioritizing of measures for response. Evaluating the value of risk comparison information can enable effective risk communication. In this review, the value of risk comparison after the Fukushima disaster for societal and individual decision-making is discussed while clarifying the concept of radiation risk assessment at low doses. The objectives of radiation risk assessment are explained within a regulatory science framework, including the historical adoption of the linear non-threshold theory. An example of risk comparison (i.e. radiation risk versus evacuation-related risk in nursing homes) is used to discuss the prioritization of pre-disaster measures. The effective communication of risk information by authorities is discussed with respect to group-based and face-to-face approaches. Furthermore, future perspectives regarding radiation risk comparisons are discussed.
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Available from http://dx.doi.org/10.1093/jrr/rrx094; Available from http://www.ncbi.nlm.nih.gov/pmc/articles/PMC5941137; PMCID: PMC5941137; PMID: 29420739; PUBLISHER-ID: rrx094; OAI: oai:pubmedcentral.nih.gov:5941137; Copyright (c) The Author(s) 2018. Published by Oxford University Press on behalf of The Japan Radiation Research Society and Japanese Society for Radiation Oncology.; This is an Open Access article distributed under the terms of the Creative Commons Attribution Non-Commercial License (http://creativecommons.org/licenses/by-nc/4.0/), which permits non-commercial re-use, distribution, and reproduction in any medium, provided the original work is properly cited. For commercial re-use, please contact journals.permissions@oup.com; Country of input: International Atomic Energy Agency (IAEA)
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Journal Article
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Journal of Radiation Research; ISSN 0449-3060;
; v. 59(Suppl 2); p. 23-30

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Harrington, S.; Yu, K.X.
Sustainable development through nuclear technology : 29th annual conference of the Canadian Nuclear Society and 32nd CNS/CNA student conference2008
Sustainable development through nuclear technology : 29th annual conference of the Canadian Nuclear Society and 32nd CNS/CNA student conference2008
AbstractAbstract
[en] As electronic components of nuclear power plants age, their reliability decreases. With this decreased mean time between failures, there is increased cost. The increased costs are associated with replacing or repairing components and with the increased risk of production loss.To compound these problems there are issues of obsolescence. The impact of these effects on the area of instrumentation and control electronics is especially severe. By utilizing digital technology that is relatively cheap and readily available, one can achieve improved reliability in complex control loops. The deaerator level control loop in a nuclear power plant is a complex control loop. The control of the loop is achieved using a feed-forward control scheme. A station-specific implementation of this control scheme is achieved using several analog electronic components. A modification was performed to achieve increased reliability while implementing the same control algorithm by using digital components, an improved component arrangement and increased redundancy. This paper will describe how the improved reliability was achieved. (author)
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Canadian Nuclear Society, Toronto, Ontario (Canada); 268 Megabytes; ISBN 0-919784-90-9;
; 2008; [9 p.]; 29. Annual conference of the Canadian Nuclear Society and 32. CNS/CNA student conference on sustainable development through nuclear technology; Toronto, Ontario (Canada); 1-4 Jun 2008; Available from the Canadian Nuclear Society, Toronto, Ontario (Canada); 3 refs., 5 figs.

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Berntson, K.
IAEA technical meeting on integrating analog and digital instrumentation and control systems in hybrid main control rooms at nuclear power plants. Book of abstracts2007
IAEA technical meeting on integrating analog and digital instrumentation and control systems in hybrid main control rooms at nuclear power plants. Book of abstracts2007
AbstractAbstract
[en] The Canadian Nuclear Safety Commission (CNSC) guidance documents related to human factors do not specify design implementation as a specific aspect requiring review, as is done in NUREG-0711. However, even without being separately identified, it is clearly understood by any Human Factors specialist that issues arising from the implementation of a design need to be carefully reviewed and addressed. One of the key areas where implementation issues become a concern is the area of technological changes. This can be of particular concern in multi-unit control rooms, such as are used on many CANDU stations, as periods will exist where different designs and technologies are in use for the same purpose in the same control room. This paper will look at the techniques used by the Bruce Power Human Factors section to ensure that the existence of multiple technologies does not have a negative performance impact for the personnel operating and maintaining the station. This will be done using examples from past Bruce Power experience. Lessons learned will also be discussed. (author)
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International Atomic Energy Agency, Nuclear Power Engineering Section, Vienna (Austria); Atomic Energy Canada Limited (AECL) (Canada); Bruce Power (Canada); Ontario Power Generation (Canada); CANDU Owners Group, Inc. (Canada); Hydro Quebec (Canada); Electric Power Research Institute (EPRI) (United States); 72 p; 2007; p. 60; IAEA technical meeting on integrating analog and digital instrumentation and control systems in hybrid main control rooms at nuclear power plants; Toronto, ON (Canada); 29 Oct - 2 Nov 2007; Also available on-line: http://entrac.iaea.org/I-and-C/TM_TORONTO_2007/Book%20of%20Abstracts%202.pdf
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Szymandera, J.; Shaikh, O.; Hennig, D.; Goodchild, S.; Banica, C., E-mail: jakub.szymandera@amec.com
Nuclear at Niagara. 32nd Annual Canadian Nuclear Society conference and 35th CNS/CNA student conference2011
Nuclear at Niagara. 32nd Annual Canadian Nuclear Society conference and 35th CNS/CNA student conference2011
AbstractAbstract
[en] Physics simulations in safety analyses are generally performed using a bundle irradiation distribution that is consistent with an approximate time-average configuration. In this paper, three assessments of a spurious adjuster withdrawal event at Darlington are performed with RFSP. The simulations are performed using a time-average irradiation distribution and the SORO predicted irradiation distribution just prior to the actual event. In all three of the assessments it is shown that the results are quite insensitive to the assumed irradiation distribution. This supports the approach of assuming a time-average irradiation distribution in safety analyses. (author)
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Canadian Nuclear Society, Toronto, Ontario (Canada); 136 Megabytes; ISBN 978-1-926773-04-9;
; 2011; [20 p.]; 32. Annual Canadian Nuclear Society conference; Niagara Falls, Ontario (Canada); 5-8 Jun 2011; 35. CNS/CNA student conference; Niagara Falls, Ontario (Canada); 5-8 Jun 2011; Available from the Canadian Nuclear Society, Toronto, Ontario (Canada); 1 ref., 3 tabs., 16 figs.

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[en] This paper describes the major results of the recently-completed Bruce B Risk Assessment (BBRA). The results are presented in the form of the frequencies of various fuel damage categories (FDCs) and ex-plant release categories (EPRCs). Some of the dominant sequences leading to these categories are discussed. Also discussed are the key conclusions of the assessment. The paper also discusses how the products of the study have been used to support decision-making at the plant. Some specific examples are included. The paper concludes by describing the work undertaken to develop an on-line risk model that is being used on a regular basis by plant personnel to assess the risk impact of changes in plant configuration. (author)
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Canadian Nuclear Society, Toronto, Ontario (Canada); 49.1 Megabytes; ISBN 0-919784-66-6;
; 2000; [15 p.]; Proceedings of the Canadian Nuclear Society 21st annual conference; Toronto, Ontario (Canada); 11-14 Jun 2000; Available on Compact Disc from the Canadian Nuclear Society, Toronto, Ontario (Canada); 4 refs., 7 tabs., 5 figs.

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[en] This paper presents the results of a large study of 1340 articles published by two major newspapers in six European countries (Belgium, Italy, Norway, Slovenia, Spain and Russia) in the first 2 months after the Fukushima Daiichi nuclear disaster. The focus of the analysis is on the application and overall impact of protective actions, both during the emergency phase and later, how the newspapers describe those actions, which differences were apparent between countries and what recommendations can be extracted in order to improve general communication about these issues. A clear lesson is that, even under uncertainty and recognising limitations, responsible authorities need to provide transparent, clear and understandable information to the public and the mass media right from the beginning of the early phase of any nuclear emergency. Clear, concise messages should be given. Mass media could play a key role in reassuring the public if the countermeasures are clearly explained. (authors)
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Available from doi: http://dx.doi.org/10.1093/rpd/ncw334; Country of input: France; 8 refs.
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Journal Article
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Radiation Protection Dosimetry; ISSN 0144-8420;
; v. 173(1-3); p. 163-169

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