Filters
Results 1 - 10 of 79
Results 1 - 10 of 79.
Search took: 0.031 seconds
Sort by: date | relevance |
AbstractAbstract
[en] This paper reviews the energy portfolio of Department of National Defence (DND) and of the Canadian Armed Forces (CAF) from different perspectives based on recent data analyses of the energy used over several years. Then it shows a projection of the potential impacts on current and future DND/CAF capabilities of selected emerging technologies (nuclear and non-nuclear). When possible, it estimates the potential life-cycle cost savings from the hypothetical adoption of such technologies that minimize operational cost and waste management burden. (author)
Primary Subject
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); International Atomic Energy Agency, Vienna (Austria); 48.3 Megabytes; ISBN 978-1-926773-20-9; ; 2015; [17 p.]; 7. International Conference on Modelling and Simulation in Nuclear Science and Engineering; Ottawa, Ontario (Canada); 18-21 Oct 2015; Available from the Canadian Nuclear Society, 700 University Avenue, 4th Floor, Toronto, Ontario, Canada; Paper 7ICMSNSE-53. 29 refs., 2 tabs., 9 figs.
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Shenglong, Q.; Dong, Y.; Danrong, S.; Wei, L., E-mail: qiangshenglong@tsinghua.org.cn, E-mail: d.yao@npic.ac.cn, E-mail: songdr@npic.ac.cn, E-mail: luwei@npic.ac.cn
Seventh International conference on modelling and simulation in nuclear science and engineering2015
Seventh International conference on modelling and simulation in nuclear science and engineering2015
AbstractAbstract
[en] Monte Carlo burnup calculation is development trend of reactor physics, there would be a lot of work to be done for engineering applications. Based on Monte Carlo burnup code MOI, non-fuel burnup calculation methods and critical search suggestions will be mentioned in this paper. For non-fuel burnup, mixed burnup mode will improve the accuracy of burnup calculation and efficiency. For critical search of control rod position, a new method called ABN based on ABA which used by MC21 will be proposed for the first time in this paper. (author)
Primary Subject
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); International Atomic Energy Agency, Vienna (Austria); 48.3 Megabytes; ISBN 978-1-926773-20-9; ; 2015; [8 p.]; 7. International Conference on Modelling and Simulation in Nuclear Science and Engineering; Ottawa, Ontario (Canada); 18-21 Oct 2015; Available from the Canadian Nuclear Society, 700 University Avenue, 4th Floor, Toronto, Ontario, Canada; Paper 7ICMSNSE-011. 10 refs., 7 figs.
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A tightly coupled multi-physics model for MSR (Molten Salt Reactor) system involving the reactor core and the rest of the primary loop has been developed and employed in an in-house developed computer code TANG-MSR. In this paper, the computer code is used to simulate the behavior of steady state operation and transient for our redesigned TMSR. The presented simulation results demonstrate that the models employed in TANG-MSR can capture major physics phenomena in MSR and the redesigned TMSR has excellent performance of safety and sustainability. (author)
Primary Subject
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); International Atomic Energy Agency, Vienna (Austria); 48.3 Megabytes; ISBN 978-1-926773-20-9; ; 2015; [13 p.]; 7. International Conference on Modelling and Simulation in Nuclear Science and Engineering; Ottawa, Ontario (Canada); 18-21 Oct 2015; Available from the Canadian Nuclear Society, 700 University Avenue, 4th Floor, Toronto, Ontario, Canada; Paper 7ICMSNSE-39. 26 refs., 2 tabs., 20 figs.
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] In dilute fluid-solid two phase flow, particle motion in sudden contraction and sudden expansion structure is studied. CFX is used to simulate both fluid field and particle motion. Four different turbulence models are compared with each other and k-e model is proved to be efficient to calculate this situation. Four different particle injection regions are set to observe particle motion. The influence of particle diameter and virtual mass force are studied, separately. (author)
Primary Subject
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); International Atomic Energy Agency, Vienna (Austria); 48.3 Megabytes; ISBN 978-1-926773-20-9; ; 2015; [11 p.]; 7. International Conference on Modelling and Simulation in Nuclear Science and Engineering; Ottawa, Ontario (Canada); 18-21 Oct 2015; Available from the Canadian Nuclear Society, 700 University Avenue, 4th Floor, Toronto, Ontario, Canada; Paper 7ICMSNSE-6. 3 refs., 10 figs.
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Jamieson, T., E-mail: Terry.Jamieson@cnsc-ccsn.gc.ca
Seventh International conference on modelling and simulation in nuclear science and engineering2015
Seventh International conference on modelling and simulation in nuclear science and engineering2015
AbstractAbstract
[en] 'Full text:' The current and future regulatory challenges associated with deterministic safety analysis are reviewed, including: 1. The CNSC's and safety control areas. 2. Traditional safety analysis approach. 3. Experience gained and impact. 4. Current analysis and regulatory approaches. 5. Current status. 6. Complexity and challenges In particular, the technical, regulatory and strategic aspects of these challenges are discussed. (author)
Primary Subject
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); International Atomic Energy Agency, Vienna (Austria); 48.3 Megabytes; ISBN 978-1-926773-20-9; ; 2015; [1 p.]; 7. International Conference on Modelling and Simulation in Nuclear Science and Engineering; Ottawa, Ontario (Canada); 18-21 Oct 2015; Available from the Canadian Nuclear Society, 700 University Avenue, 4th Floor, Toronto, Ontario, Canada; Paper 7ICMSNSE-Plenary2-1. Short communication. Abstract available only, full text entered in this record.
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Lorencez, C., E-mail: carlos.lorencez@opg.com
Seventh International conference on modelling and simulation in nuclear science and engineering2015
Seventh International conference on modelling and simulation in nuclear science and engineering2015
AbstractAbstract
[en] 'Full text:' In general terms, we associate the words 'modeling and simulation' with semi-ideal mathematical models reproducing complex Engineering problems. However, the use of modeling and simulation is much more extensive than that: it is applied on a daily basis in almost every front of Science, from sociology and biology to climate change, medicine, robotics, war strategies, etc. It is also being applied by our frontal lobe when we make decisions. The results of these exercises on modeling and simulation have had invaluable benefits on our well being, and we are just at the beginning. (author)
Primary Subject
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); International Atomic Energy Agency, Vienna (Austria); 48.3 Megabytes; ISBN 978-1-926773-20-9; ; 2015; [1 p.]; 7. International Conference on Modelling and Simulation in Nuclear Science and Engineering; Ottawa, Ontario (Canada); 18-21 Oct 2015; Available from the Canadian Nuclear Society, 700 University Avenue, 4th Floor, Toronto, Ontario, Canada; Paper 7ICMSNSE-Plenary2-1. Short communication. Abstract available only, full text entered in this record.
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] A study was performed using a CATHENA based generic model of a CANDU6 reactor to demonstrate the sensitivity of system response to single and two-stage break opening characteristics following a Reactor Inlet Header Large Break LOCA. Figures of merit for the analysis were the power pulse amplitude and the 5 second integrated normalized power. The analysis demonstrates in a qualitative manner a threshold time for 'instantaneous' break opening, and a threshold initial break size above which shutdown system trip times remain unchanged. The analysis also attempts to establish the relative impacts of initial and second stage opening times on figures of merit. (author)
Primary Subject
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); International Atomic Energy Agency, Vienna (Austria); 48.3 Megabytes; ISBN 978-1-926773-20-9; ; 2015; [13 p.]; 7. International Conference on Modelling and Simulation in Nuclear Science and Engineering; Ottawa, Ontario (Canada); 18-21 Oct 2015; Available from the Canadian Nuclear Society, 700 University Avenue, 4th Floor, Toronto, Ontario, Canada; Paper 7ICMSNSE-69. 2 refs., 6 tabs., 14 figs.
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Dranga, R.; McRae, G.A., E-mail: ruxandra.dranga@carleton.ca, E-mail: glenn.mcRae@carleton.ca
Seventh International conference on modelling and simulation in nuclear science and engineering2015
Seventh International conference on modelling and simulation in nuclear science and engineering2015
AbstractAbstract
[en] Gamma radiation sources are being used for an array of everyday applications, from portal monitors for homeland security to blood sterilization, and as calibration sources in nuclear medicine. This paper presents the preliminary feasibility study of a source that allows the gamma radiation to be turned on and off. The gamma radiation is produced via a sequence of nuclear reactions: an (α, n) reaction, followed by an (n, γ) reaction. Parametric studies in MCNP5 were performed to investigate the effect of different moderators, neutron absorbers, and geometries on the gamma flux and gamma dose produced. The results of the feasibility study are discussed in the context of nuclear medicine applications. (author)
Primary Subject
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); International Atomic Energy Agency, Vienna (Austria); 48.3 Megabytes; ISBN 978-1-926773-20-9; ; 2015; [11 p.]; 7. International Conference on Modelling and Simulation in Nuclear Science and Engineering; Ottawa, Ontario (Canada); 18-21 Oct 2015; Available from the Canadian Nuclear Society, 700 University Avenue, 4th Floor, Toronto, Ontario, Canada; Paper 7ICMSNSE-37. 16 refs., 10 figs.
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Kallikragas, D.; Svishchev, I., E-mail: dimitrioskallikragas@trentu.ca, E-mail: isvishchev@trentu.ca
Seventh International conference on modelling and simulation in nuclear science and engineering2015
Seventh International conference on modelling and simulation in nuclear science and engineering2015
AbstractAbstract
[en] Atomistic modelling is ideal for the study of corrosion phenomena, particularly at the extreme conditions of the Supercritical Water Cooled Reactor (SCWR). Understanding the behavior of supercritical water and species such as chloride and oxygen is needed for developing a corrosion control strategy. Molecular Dynamics simulations have been employed to study the properties of aqueous systems in nanometer-spaced iron hydroxide surfaces. Atomic density profiles as well as diffusion coefficients and hydration numbers within these surfaces are provided. These surface configurations simulate the environment of proto-cracks in the passivation layer of components in the SCWR. (author)
Primary Subject
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); International Atomic Energy Agency, Vienna (Austria); 48.3 Megabytes; ISBN 978-1-926773-20-9; ; 2015; [12 p.]; 7. International Conference on Modelling and Simulation in Nuclear Science and Engineering; Ottawa, Ontario (Canada); 18-21 Oct 2015; Available from the Canadian Nuclear Society, 700 University Avenue, 4th Floor, Toronto, Ontario, Canada; Paper 7ICMSNSE-9. 24 refs., 2 tabs., 3 figs.
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Altiparmakov, D., E-mail: dimitar@bell.net
Seventh International conference on modelling and simulation in nuclear science and engineering2015
Seventh International conference on modelling and simulation in nuclear science and engineering2015
AbstractAbstract
[en] This paper presents a new method for approximate solution of the multigroup neutron transport equation. The R-function theory is applied to describe the geometric shape of material regions analytically. Resulting formulae form a basis for a mesh-free approximation of the spatial neutron flux distribution. The method of moments is applied to transform the integral transport equation into a system of linear algebraic equations. Calculations of characteristic two dimensional CANDU lattice problems show that the method is capable of accurate modeling of the neutron transport with a significant reduction of the number of unknowns compared to standard mesh-based approximations. (author)
Primary Subject
Source
Canadian Nuclear Society, Toronto, Ontario (Canada); International Atomic Energy Agency, Vienna (Austria); 48.3 Megabytes; ISBN 978-1-926773-20-9; ; 2015; [12 p.]; 7. International Conference on Modelling and Simulation in Nuclear Science and Engineering; Ottawa, Ontario (Canada); 18-21 Oct 2015; Available from the Canadian Nuclear Society, 700 University Avenue, 4th Floor, Toronto, Ontario, Canada; Paper 7ICMSNSE-72. 10 refs., 1 tab., 8 figs.
Record Type
Miscellaneous
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
1 | 2 | 3 | Next |