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[SI]: 33100 Main Heat Transport System Documents

Documents below are listed chronologically. Use the links on the left or below to filter documents by keyword. Use the links above to jump to a specific year on this page.

Number of files: 64

    1969-01-02---------Jump to [Top]
  1. The Effect of Bypass Characteristics on Parallel Channel Flow Instabilities, by M.B. Carver, AECL, 1969-01-02. Doc type: Paper.
    Summary: This article is definitive because nobody could figure out why all the instability codes gave stability thresholds well below the measured threshold power in the experiments done at Canadian Westinghouse. The paper determines analytically that this is because the small bypass stabilized the experimental system as it could not maintain a constant pressure drop, which all the codes assumed at step 1.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System [Discipline] Mathematics Mechanical Engineering [Topic] Basic Equations Collections Conceptual Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Proceedings of the Institution of Mechanical Engineers, Volume 184, 1969 BYPASS PIME_CONF_1969_184_083_02.pdf (703 kb)
    2. 1978-01-01---------Jump to [Top]
  2. Efficient Integration over Discontinuities in Ordinary Differential Equation Simulation, by M.B. Carver, AECL, 1978-01-01. Doc type: Paper.
    Summary: Efficient integration algorithms for ordinary differential equations take integration steps that are as large as the error control criteria permit. Events or discontinuities in equation definition are often implicitly defined to occur when a variable reaches a critical value, for example a fuel rod surface reaching saturation temperature, and this requires the integrator to basically restart the calculation precisely at the point of change. Instead integrators will "hunt" for the discontinuity wasting a lot of computer time, and will eventually "step over" the discontinuity using integration points either side of the event. This paper shows that if the discontinuity is defined and monitored as an additional part of the equation set, such a restart can be optimized, thus ensuring that the event will be defined as an integration restart point.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Mathematics and Computers in Simulation, XX, 1978 efficient-integration-over-discontinuities-in-ordinary-differential-equation.pdf (467 kb)
    3. 1978-08-01---------Jump to [Top]
  3. The method of lines and the advective equation, by M.B. Carver and H.W. Hinds, AECL, 1978-08-01. Doc type: Paper.
    Summary: This article showed that the common approach of first order differencing, used in almost all thermalhydraulic computer programs, would not properly solve the simplest hyperbolic PDE on the market. Despite the errata, it is Carver's most cited publication and laid the foundations for many higher order analyses by others, and Carver's pseudo-characteristic method of lines (PCMOL) solution of the thermalhydraulic conservation equations.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Basic Equations Modelling Process Systems Thermalhydraulics [Phase] Concept Design Analysis Safety Analysis [Audience] Engineer Grad
    - Simulation, August,1978. Also published as AECL 6155 AdvectiveEqn.pdf (804 kb)
    4. 1980-01-01---------Jump to [Top]
  4. Pseudo-characteristic method of lines solution of first-order hyperbolic equation systems, by M.B. Carver, AECL, 1980-01-01. Doc type: Paper.
    Summary: This paper introduced a new concept, pseudo-characteristics, which allows the directionality dictated by the method of characteristics to be applied on a fixed grid basis. This is the method that N.P. Kolev Nuclear Institute of Bulgaria and M. B. Carver used to apply to the EVUT form of the thermalhydraulic conservation equations at the OECD/CSNI conference on two phase flow, Pasedena, 1981. In this MACS paper, discretization of the PDEs is discussed, using higher order upwind biased derivatives of each of the Lagrange polynomials and the Hermite polynomials. Results are shown for incompressible flow in a hydraulic jump and for compressible flow in the EVET thermalhydraulic conservation equations.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Mathematics and Computers in Simulation, 22, 1980 pseudo-characteristic-method-of-lines-solution-of-first-order-hyperbolic-equation.pdf (455 kb)
    5. 1982-01-01---------Jump to [Top]
  5. A Method of Limiting Intermediate Volume Fraction in Iterative Two-Fluid Computations, by M.B. Carver, AECL, 1982-01-01. Doc type: Paper.
    Summary: This is seminal and the core contribution in Carver's thesis. The ICE guys, Harlow & Amsden and the IPSA guys, Spalding & Patankar had not got it quite right for air/water conditions where the water totally dominates the pressure field calculation when it is based on mass flux balance, as this is dominated by the water component and neglects continuity of the air. Herein, a volumetric balance fixes that and the calculation also converges better with the constraint mentioned in the title.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Journal of Mechanical Engineering Science, Vol. 24, No. 2, 1982 limiting_volume_fraction_JMES_JOUR_1982.pdf (374 kb)
    6. 1984-12-01---------Jump to [Top]
  6. Two Dimensional Modelling of the Homogenizing Effects of Flow Obstructions in Two Fluid Flow, by M.B. Carver and M. E. Salcudean, AECL, 1984-12-01. Doc type: Paper.
    Summary: It is well known that obstructions in two fluid flow have the effect of homogenizing the two fluid mixture, resulting not only in a more uniform phase distribution, but also in a significant reduction of the ratio of fluid velocities. This paper describes a 2D, 2Fluid computer program written by the first author to do proof of principal studies of 2fluid redistribution around bends and past obstacles. The details necessary for modelling air/water flows in these geometries have been introduced here before extending the work to 3D. The paper shows that these phase redistribution effects can be modelled using the two fluid computer program, and compares results to those obtained in a recent experiment on flow past obstructions.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System [Discipline] Mathematics#Mechanical Engineering [Topic] Modelling Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Mathematics and Computers in Simulation 26(6):pp 475–484, December 1984 two-dimensional-modelling-of-the-homogenizing-effects-of-flow-obstructions.pdf (1202 kb)
    7. 1987-04-01---------Jump to [Top]
  7. Development and Application of a Three-Dimensional Two-Fluid Numerical Algorithm for Simulation of Phase Redistribution by Bends and Obstructions, by M.B. Carver, AECL, 1987-04-01. Doc type: Other.
    Summary: Mike completed his Ph.D in parallel to his full time position at AECL as branch head of Applied Mathematics at CRNL. Upon completion he was appointed adjunct professor at McMaster and was co-supervisor of two degrees.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System [Discipline] Mathematics#Mechanical Engineering [Topic] Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Ph.D Thesis, Department of Mechanical Engineering, University of Ottawa, April 1987 ThesisNL56352.pdf (4350 kb)
    8. 1987-06-01---------Jump to [Top]
  8. Nuclear Journal of Canada, 1987 Vol 1 No. 2, by G.H. Archinoff, J.e. Luxat, P.O. Lowe, K.E. Locke and A.P. Muzumdar, CNS-, 1987-06-01. Doc type: Paper.
    Summary: The computer code SMARTT (Simulation Method for Azimuthal and Radial Temperature Transients) is used in safety analysis of Ontario Hydro's CANDU reactors to predict fuel and pressure tube thermal and mechanical behaviour under asymmetric coolant conditions, such as stratified flow. This paper presents comparisons of SMARTT predictions, with preliminary results of two experiments in which large temperature nonuniformities developed on pressure tubes undergoing heatup and transverse strain at 1.0 MPa internal pressure.
    Keywords: [Concept] Materials [SI] 33100 Main Heat Transport System [Discipline] Materials Engineering [Topic] Performance [Phase] Operation Safety Analysis [Audience] Engineer Grad Ugrad
    - Simulation Methodology for Pressure Tube Integrity Analysis and Comparison with Experiments NJC-1-2-07.pdf (575 kb)
    - The Drift Flux Model in the ASSERTSubchannel Code, by M.B. Carver, R.A. Judd, J.E. Kiteley, and A. Tahir, NJC-1-2-08.pdf (742 kb)
    9. 1987-09-01---------Jump to [Top]
  9. Nuclear Journal of Canada, 1987 Vol 1 No. 3, by J.P. Mallory and P.J. Ingham, CNS-, 1987-09-01. Doc type: Paper.
    Summary: Under some postulated accident conditions, decay heat is removed from a reactor core by 2-phase natural circulation or 'thermosiphoning' of the primary coolant. To assess the ability of the computer code CATHENA to predict such events, simulations were performed of thermosiphoning tests conducted in the RD-14 facility at the Whiteshell Nuclear Research Establishment.
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Safety Thermalhydraulics [Phase] Safety Analysis [Audience] College Engineer Grad Technician Ugrad
    - CATHENA Simulation of Thermosiphoning in a Pressurized-Water Test Facility NJC-1-3-05.pdf (615 kb)
    10. 1987-12-01---------Jump to [Top]
  10. Nuclear Journal of Canada, 1987 Vol 1 No. 4, by Matija Cenanovic and Hugo Maureira, CNS-, 1987-12-01. Doc type: Paper.
    Summary: Proper spacing between the pressure tube and the surrounding calandria tube of the fuel channels in CANDU reactors is maintained by spacers (garter springs). It was established that many garter springs are no longer in their correct positions in Ontario Hydro's operating reactors. A novel AC device was developed at Ontario Hydro Research Division to reposition the garter springs without any harmful effect on the fuel channel integrity.
    Keywords: [Concept] Mechanical [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] - [Phase] Operation [Audience] College Engineer Grad Manager Technician Ugrad
    - The AC Device for Repositioning of Garter Springs in CANDU Reactors NJC-1-4-09.pdf (696 kb)
    11. 1995-08-01---------Jump to [Top]
  11. Numerical Solution of the Thermalhydraulic Conservation Equations from Fundamental Concepts to Multidimensional Analysis, by M.B. Carver, , 1995-08-01. Doc type: Report.
    Summary: This material was presented as part of a short course in Two-Phase Flow and Heat Transfer at McMaster University and is documented in report form for further reference. The discussion briefly establishes some requisite concepts of differential equation theory, and applies these to describe methods for numerical solution of the thennalhydraulic conservation equations in their various forms. The intent is to cover the general methodology without obscuring the principles with details. As a short overview of computational thermalhydraulics, the material provides an introductory foundation, so that those working on the application of thennalhydraulic codes can begin to understand the many intricacies involved without having to locate and read the references given. Those intending to work in code development will need to read and understand all the references.
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Basic Equations Collections Conceptual Modelling Process Systems Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Grad
    - AECL-11387, ARD-TD-550, Revision 1 (2017) to the original (1995) Carver AECL-11387[3628]-WithAddendum.pdf (6457 kb)
    12. 1996-02-01---------Jump to [Top]
  12. Reactor Thermalhydraulics Design, Course 2.1, by Wm.J. Garland, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary: This course is concerned with the thennalhydraulic design of the process systems that are required to transport heat energy away from the nuclear reactor source and transform this heat energy into useful work (generally electrical energy).
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Basic Equations Important Parameters Process Systems Thermalhydraulics [Phase] Concept Design Design Analysis Design Evolution Design Process [Audience] Engineer Ugrad
    - Title and Table of Contents 20043701.pdf (170 kb)
    - Foreword and Glossary, by Wm.J. Garland, 20043702.pdf (74 kb)
    - Chapter 1 - Introduction, by Wm.J. Garland, 20043703.pdf (130 kb)
    - Chapter 2 - Design Requirements and Engineering Considerations, by Wm.J. Garland, 20043704.pdf (1189 kb)
    - Chapter 3 - Heat Transport System Thermalhydrauilics, by Wm.J. Garland, 20043705.pdf (447 kb)
    - Chapter 4 - Thermodynamics, by Wm.J. Garland, 20043706.pdf (309 kb)
    - Chapter 5 - Fuel Coolant Heat Transfer, by Wm.J. Garland, 20043707.pdf (245 kb)
    - Chapter 6 - Control, by Wm.J. Garland, 20043708.pdf (313 kb)
    - Chapter 7 - The Design Process, by Wm.J. Garland, 20043709.pdf (419 kb)
    - Chapter 8 - Process Design and Optimization, by Wm.J. Garland, 20043710.pdf (441 kb)
    - Appendix 1 - Comparison of Bruce A, B, & Darlington, by Wm.J. Garland, 20043711.pdf (223 kb)
  13. Thermal Study of Nuclear Reactors, Course 2.2, by A. Tapucu, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Design Design Analysis [Audience] Engineer Grad Ugrad
    - Title and Table of Contents 20043801.pdf (96 kb)
    - Chapter 1 - Fundamental Concepts, by A. Tapucu, 20043802.pdf (234 kb)
    - Chapter 2 - Single Phase Fluid Equations, by A. Tapucu, 20043803.pdf (200 kb)
    - Chapter 3 - Principles of Heat Transfer, by A. Tapucu, 20043804.pdf (1061 kb)
    - Chapter 4 - Forced Convection Heat Transfer, by A. Tapucu, 20043805.pdf (1624 kb)
    - Chapter 7 - Heat Removal from Nuclear Reactors, by A. Tapucu, 20043806.pdf (1557 kb)
    - Appendix 1 - Tensors, by A. Tapucu, 20043807.pdf (49 kb)
    - Appendix 2 - Stress in a Fluid, by A. Tapucu, 20043808.pdf (256 kb)
    - Appendix 3 - A Short Summary of Orthogonal Functions Used in Chapter 4, by A. Tapucu, 20043809.pdf (178 kb)
    - Workbook, Chapter 4, by A. Tapucu, 20043810.pdf (2301 kb)
    - Workbook, Chapter 7, by A. Tapucu, 20043811.pdf (2043 kb)
  14. Reactor Thermalhydraulics Analysis, Course 2.3, by Wm.J. Garland, Chulalongkorn University, 1996-02-01. Doc type: Course.
    Summary: Fundamentals of thermalhydraulic analysis (heat transfer and fluid mechanics)of the heat transport system.
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Title and Table of Contents 20043901.pdf (144 kb)
    15. 1997-04-01---------Jump to [Top]
  15. Software Quality Assurance: Practical Procedures to Meet CSA Standards, by M.B. Carver, CNSC, 1997-04-01. Doc type: Report.
    Summary: In the Canadian nuclear industry at the time, only the ASSERT code team and the NUCIRC team used definitive SQA (Software Quality Assurance), which identifies exactly what version of the computer code is being used for a given application, and every component used to build that version. A drive to apply such standards to all computer programs started in the 1990s, and Mike co-authored the 1995 AECL Reactor Development SQA manual. Upon his retirement, representatives of the then AECB (now CNSC) asked him to write a SQA guide for the industry that would bring all computer codes teams in line with CSA standards ( N286.7 & Q936).This report is CNSC-info-0669, 1997. To date the ASSERT-PV development team has followed these standards, the CATHENA team has not. Source attribution: Archived in the public domain at http://www.nuclearsafety.gc.ca/eng/about/past/timeline-dev/resources/documents/infohistorical/info-0669.pdf .
    Keywords: [Concept] - [SI] 03000 Engineering Science and Technology 30000 Reactor, Steam Generators and Auxiliaries 33100 Main Heat Transport System 36000 Steam Generator Steam and Water Systems [Discipline] Mathematics#Mechanical Engineering [Topic] Modelling Thermalhydraulics [Phase] Design Analysis Safety Analysis [Audience] Engineer Grad
    - Atomic Energy Control Board, Report INFO-0699, April 1997, http://www.nuclearsafety.gc.ca info-0669.pdf (3262 kb)
    16. 1998-02-01---------Jump to [Top]
  16. Reactor Thermalhydraulics Analysis, Course 2.3, by Wm.J. Garland, Chulalongkorn University, 1998-02-01. Doc type: Course.
    Summary:
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Glossary and Foreword 20043902.pdf (152 kb)
    - Chapter 1 - Course Overview, by Wm.J. Garland, 20043903.pdf (140 kb)
    - Chapter 2 - Basic Equations for Thermalhydraulic Systems Analysis, by Wm.J. Garland, 20043904.pdf (561 kb)
    - Chapter 3 - Nodalization, by Wm.J. Garland, 20043905.pdf (303 kb)
    - Chapter 4 - Equation of State, by Wm.J. Garland, 20043906.pdf (338 kb)
    - Chapter 5 - The Rate Form of the Equation of State, by Wm.J. Garland, 20043907.pdf (512 kb)
    - Chapter 6 - Thermalhydraulic Network Simulation, by Wm.J. Garland, 20043908.pdf (343 kb)
    - Chapter 7 - Empirical Correlations, by Wm.J. Garland, 20043909.pdf (532 kb)
    - Chapter 8 - On Design Tools, by Wm.J. Garland, 20043910.pdf (481 kb)
    - Workbook, Chapter 1, by Wm.J. Garland, 20043911.pdf (151 kb)
    - Workbook Chapter, 2, by Wm.J. Garland, 20043912.pdf (767 kb)
    - Workbook Chapter 3, by Wm.J. Garland, 20043913.pdf (466 kb)
    - Workbook Chapter 4, by Wm.J. Garland, 20043914.pdf (604 kb)
    - Workbook Chapter 5, by Wm.J. Garland, 20043915.pdf (847 kb)
    - Workbook Chapter 6, by Wm.J. Garland, 20043916.pdf (614 kb)
    - Workbook Chapter 7, by Wm.J. Garland, 20043917.pdf (719 kb)
    - Workbook Chapter 8, by Wm.J. Garland, 20043918.pdf (903 kb)
    - Workbook Figures, by Wm.J. Garland, 20043919.pdf (509 kb)
  17. Reactor Thermalhydraulics Analysis, Supplementary, Course 2.3a, by Wm.J. Garland, Chulalongkorn University, 1998-02-01. Doc type: Course.
    Summary: Supplementary info for thermalhydraulic analysis (heat transfer and fluid mechanics)of the heat transport system.
    Keywords: [Concept] Thermalhydraulics [SI] 33100 Main Heat Transport System [Discipline] Mechanical Engineering [Topic] Basic Equations Fluid Mechanics Thermalhydraulics [Phase] Concept Design Design Analysis [Audience] Engineer Grad Ugrad
    - Appendices 1 - 4 1 - Time Derivatives 2 - The Reynolds Transport Theorem 3 - Rearrangement of Independent Variables 4 - Fast Calculation of Light-Water Properties 20044001.pdf (647 kb)
    - Calculation of Water Properties, by Wm.J. Garland, 20044002.pdf (947 kb)
    - THSIM User Manual, by Wm.J. Garland, 20044003.pdf (733 kb)
    - A Pedagogical Look at Fully- and Semi-Implicit Solutions to T-H Eq'ns, by Wm.J. Garland, 20044004.pdf (320 kb)
    - Basic Equations for T-H Systems Analysis, by Wm.J. Garland, 20044005.pdf (590 kb)
    - Miscellaneous Figures and Equations, by Wm.J. Garland, 20044006.pdf (315 kb)
    18. 2001-02-01---------Jump to [Top]
  18. CANDU Origins and Evolution, by Gordon L. Brooks, AECL, 2001-02-01. Doc type: Paper.
    Summary: This monograph discusses the origins and early evolution of the basic "figure of 8" heat transport system arrangement that has been employed in most CANDU reactors to date.
    Keywords: [Concept] Overview [SI] 03000 Engineering Science and Technology 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Conceptual Important Parameters Intro and Overview [Phase] Concept Design Design Evolution [Audience] Manager
    - Figure of 8 20010303.pdf (111 kb)
    19. 2004-07-17---------Jump to [Top]
  19. CANDU fuel channel 1-D temperature calculation, by Wm.J. Garland, McMaster University, 2004-07-17. Doc type: Other.
    Summary: CANDU fuel channel 1-D temperature calculation spreadsheet.
    Keywords: [Concept] - [SI] 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Heat Transfer Modelling [Phase] Design Analysis [Audience] College; #Engineer; #Grad; #Manager; #Technician; #Ugrad
    - channel1 (511 kb)
    20. 2009-05-30---------Jump to [Top]
  20. Large LOCA Margins in CANDU Reactors - An Overview of the COG Report, by A.P. Muzumdar and D.A. Meneley, COG, 2009-05-30. Doc type: Paper.
    Summary: This paper discusses the background and conclusions of the 2007 COG report on Large LOCA Safety Margins in CANDU Reactors, and the various initiatives that have resulted from this study since its release. The COG study challenged the notion that positive void reactivity itself is a design weakness, raised as an issue at the Convention on Nuclear Safety, to demonstrate the safety of operating CANDUs worldwide when compared to other certified LWR designs. The paper will briefly describe a new perspective on how the seemingly complex analytical results on reactor safety parameters can be compared on a level playing field, in such a manner that the non-specialist is able to understand. The paper is presented together with a companion paper that focuses on the comparison of reactivity initiated events in CANDU with some other internationally accepted LWR reactor designs.
    Keywords: [Concept] - [SI] 31000 Reactor 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Safety [Phase] Safety Safety Analysis [Audience] College Engineer Grad Manager Technician Ugrad Vendor
    - 20090101.pdf (89 kb)
  21. Power Reactor Safety Comparison - A Limited Review, by D.A. Meneley and A.P. Muzumdar, COG, 2009-05-30. Doc type: Paper.
    Summary: A large amount of attention has been paid to avoiding positive coolant void reactivity in LWR reactors. This can be justified due to specific accident events that could lead to severe consequences. Somewhat less attention has been paid to other accident sequences that can lead to positive reactivity addition. Other designs, for example the CANDU-PHWR, exhibit positive coolant void reactivity but include both inherent and engineered systems that compensate for this undesirable characteristic. This paper represents the beginning of a long-term process intended to enable a balanced and fair comparison of the real safety of all reactor types.
    Keywords: [Concept] - [SI] 31000 Reactor 33100 Main Heat Transport System [Discipline] Nuclear Engineering [Topic] Safety [Phase] Safety Safety Analysis [Audience] College Engineer Grad Manager Technician Ugrad Vendor
    - 20090201.pdf (170 kb)
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