Jump to year -> [1987-06-01] [2009-05-30]
[Author]: A.P. Muzumdar 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: 3

    1987-06-01---------Jump to [Top]
  1. 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)
    2. 2009-05-30---------Jump to [Top]
  2. 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)
  3. 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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