A methodology for determination of detector response for inspection of a spent fuel pool

William J. Walters, Alireza Haghighat, Michael Wenner, Shivakumar Sitaraman, Young Ham

    Research output: Chapter in Book/Report/Conference proceedingConference contribution

    7 Citations (Scopus)

    Abstract

    In this paper we examine the predicted response of a fission chamber detector in the spent fuel pool at the Atucha-I reactor using the adjoint methodology with the aim of detecting proliferation. Burnup calculations to determine material composition and intrinsic neutron source are performed using the ORIGEN-ARP depletion code. Sub-critical multiplication is modeled using a simplified fission-matrix method. Fission-matrix coefficients are determined using MCNP for several burnups and decay times, which can be interpolated to arbitrary values. This method can quickly and accurately calculate the subcritical multiplication for a pool of any size, assembly burnup and cooling time. Adjoint function calculations for a fission chamber placed in the pool were performed using the PENTRAN Sn code. These results show that the detector field-of-view (FOV) is relatively insensitive to detector position within the pool, assembly burnup and cooling time. The adjoint results are coupled with the source calculations to predict the detector response in the spent fuel pool under both normal and proliferation scenarios. Two spent fuel diversion scenarios are examined, including substitution with dummy assemblies and attempted masking of a dummy assembly using a high-burnup assembly. Both assembly diversion scenarios show a predicted deviation from unperturbed response by at least 20%.

    Original languageEnglish (US)
    Title of host publicationInternational Conference on the Physics of Reactors 2010, PHYSOR 2010
    Pages3412-3425
    Number of pages14
    StatePublished - Dec 1 2010
    EventInternational Conference on the Physics of Reactors 2010, PHYSOR 2010 - Pittsburgh, PA, United States
    Duration: May 9 2010May 14 2010

    Publication series

    NameInternational Conference on the Physics of Reactors 2010, PHYSOR 2010
    Volume4

    Other

    OtherInternational Conference on the Physics of Reactors 2010, PHYSOR 2010
    CountryUnited States
    CityPittsburgh, PA
    Period5/9/105/14/10

    Fingerprint

    spent fuels
    Spent fuels
    inspection
    assembly
    Inspection
    fission
    methodology
    Detectors
    detectors
    dummies
    multiplication
    chambers
    cooling
    Cooling
    neutron sources
    masking
    matrix methods
    Neutron sources
    assemblies
    field of view

    All Science Journal Classification (ASJC) codes

    • Nuclear Energy and Engineering
    • Nuclear and High Energy Physics

    Cite this

    Walters, W. J., Haghighat, A., Wenner, M., Sitaraman, S., & Ham, Y. (2010). A methodology for determination of detector response for inspection of a spent fuel pool. In International Conference on the Physics of Reactors 2010, PHYSOR 2010 (pp. 3412-3425). (International Conference on the Physics of Reactors 2010, PHYSOR 2010; Vol. 4).
    Walters, William J. ; Haghighat, Alireza ; Wenner, Michael ; Sitaraman, Shivakumar ; Ham, Young. / A methodology for determination of detector response for inspection of a spent fuel pool. International Conference on the Physics of Reactors 2010, PHYSOR 2010. 2010. pp. 3412-3425 (International Conference on the Physics of Reactors 2010, PHYSOR 2010).
    @inproceedings{1744f15cba6c440c9092436943f96b63,
    title = "A methodology for determination of detector response for inspection of a spent fuel pool",
    abstract = "In this paper we examine the predicted response of a fission chamber detector in the spent fuel pool at the Atucha-I reactor using the adjoint methodology with the aim of detecting proliferation. Burnup calculations to determine material composition and intrinsic neutron source are performed using the ORIGEN-ARP depletion code. Sub-critical multiplication is modeled using a simplified fission-matrix method. Fission-matrix coefficients are determined using MCNP for several burnups and decay times, which can be interpolated to arbitrary values. This method can quickly and accurately calculate the subcritical multiplication for a pool of any size, assembly burnup and cooling time. Adjoint function calculations for a fission chamber placed in the pool were performed using the PENTRAN Sn code. These results show that the detector field-of-view (FOV) is relatively insensitive to detector position within the pool, assembly burnup and cooling time. The adjoint results are coupled with the source calculations to predict the detector response in the spent fuel pool under both normal and proliferation scenarios. Two spent fuel diversion scenarios are examined, including substitution with dummy assemblies and attempted masking of a dummy assembly using a high-burnup assembly. Both assembly diversion scenarios show a predicted deviation from unperturbed response by at least 20{\%}.",
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    Walters, WJ, Haghighat, A, Wenner, M, Sitaraman, S & Ham, Y 2010, A methodology for determination of detector response for inspection of a spent fuel pool. in International Conference on the Physics of Reactors 2010, PHYSOR 2010. International Conference on the Physics of Reactors 2010, PHYSOR 2010, vol. 4, pp. 3412-3425, International Conference on the Physics of Reactors 2010, PHYSOR 2010, Pittsburgh, PA, United States, 5/9/10.

    A methodology for determination of detector response for inspection of a spent fuel pool. / Walters, William J.; Haghighat, Alireza; Wenner, Michael; Sitaraman, Shivakumar; Ham, Young.

    International Conference on the Physics of Reactors 2010, PHYSOR 2010. 2010. p. 3412-3425 (International Conference on the Physics of Reactors 2010, PHYSOR 2010; Vol. 4).

    Research output: Chapter in Book/Report/Conference proceedingConference contribution

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    N2 - In this paper we examine the predicted response of a fission chamber detector in the spent fuel pool at the Atucha-I reactor using the adjoint methodology with the aim of detecting proliferation. Burnup calculations to determine material composition and intrinsic neutron source are performed using the ORIGEN-ARP depletion code. Sub-critical multiplication is modeled using a simplified fission-matrix method. Fission-matrix coefficients are determined using MCNP for several burnups and decay times, which can be interpolated to arbitrary values. This method can quickly and accurately calculate the subcritical multiplication for a pool of any size, assembly burnup and cooling time. Adjoint function calculations for a fission chamber placed in the pool were performed using the PENTRAN Sn code. These results show that the detector field-of-view (FOV) is relatively insensitive to detector position within the pool, assembly burnup and cooling time. The adjoint results are coupled with the source calculations to predict the detector response in the spent fuel pool under both normal and proliferation scenarios. Two spent fuel diversion scenarios are examined, including substitution with dummy assemblies and attempted masking of a dummy assembly using a high-burnup assembly. Both assembly diversion scenarios show a predicted deviation from unperturbed response by at least 20%.

    AB - In this paper we examine the predicted response of a fission chamber detector in the spent fuel pool at the Atucha-I reactor using the adjoint methodology with the aim of detecting proliferation. Burnup calculations to determine material composition and intrinsic neutron source are performed using the ORIGEN-ARP depletion code. Sub-critical multiplication is modeled using a simplified fission-matrix method. Fission-matrix coefficients are determined using MCNP for several burnups and decay times, which can be interpolated to arbitrary values. This method can quickly and accurately calculate the subcritical multiplication for a pool of any size, assembly burnup and cooling time. Adjoint function calculations for a fission chamber placed in the pool were performed using the PENTRAN Sn code. These results show that the detector field-of-view (FOV) is relatively insensitive to detector position within the pool, assembly burnup and cooling time. The adjoint results are coupled with the source calculations to predict the detector response in the spent fuel pool under both normal and proliferation scenarios. Two spent fuel diversion scenarios are examined, including substitution with dummy assemblies and attempted masking of a dummy assembly using a high-burnup assembly. Both assembly diversion scenarios show a predicted deviation from unperturbed response by at least 20%.

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    Walters WJ, Haghighat A, Wenner M, Sitaraman S, Ham Y. A methodology for determination of detector response for inspection of a spent fuel pool. In International Conference on the Physics of Reactors 2010, PHYSOR 2010. 2010. p. 3412-3425. (International Conference on the Physics of Reactors 2010, PHYSOR 2010).