STP1228

    Dosimetry Aspects of the New Canadian MAPLE-X10 Reactor

    Published: Jan 1994


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    Abstract

    Atomic Energy of Canada Limited is building the 10-MWt MAPLE-X10 reactor facility as a dedicated producer of medical and industrial radioisotopes. Dosimetry aspects of the MAPLE-X10 nuclear design include the calculated thermal and fast neutron flux distributions throughout the reactor assembly and the rate of heat generation in reactor materials and components. Examples of the resolution of design issues are also presented, such as the use of fission counters and ion chambers to provide diverse methods of detecting neutron flux levels and the use of the difference between photon and neutron signals to guard against the effects of downgrading of the heavy-water reflector. Computer codes employed in the calculations include MCNP, ONEDANT, WIMS-AECL, and 3DDT.

    Keywords:

    Research reactor, medical radioisotope production, neutron and photon flux distributions, energy deposition in reactor components


    Author Information:

    Lidstone, RF
    ManagerPhysics Analysis Group Leader, Reactor Technology Branch, AECL Research, Whiteshell Laboratories, Pinawa, MB

    Wilkin, GB
    ManagerPhysics Analysis Group Leader, Reactor Technology Branch, AECL Research, Whiteshell Laboratories, Pinawa, MB


    Paper ID: STP15154S

    Committee/Subcommittee: E10.04

    DOI: 10.1520/STP15154S


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