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Monte Carlo Simulation Research on the Spontaneous Fission Yield of 240Pu

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2015, PhD, University of Cincinnati, Engineering and Applied Science: Nuclear and Radiological Engineering.
This research describes results of mathematical simulations to predict the spontaneous fission yield of 240Pu thereby guiding selection of a suitable fission product for use as a radiochronometer for weapons grade plutonium. The PUREX process is effective in separating plutonium and uranium in irradiated nuclear fuel from fission products, which may make it possible to use one or more of the spontaneous fission products from 240Pu as a radiochronometer. However, the fission product inventory from the spontaneous fission of 240Pu reported in the literature is quite variable. The non-uniform induced fission probability at multiple neutron energies makes the induced fission yield too complex to be listed as a single value. The neutron flux distribution from a source containing 240Pu is a combination of both spontaneous and induced fissions. Fission products generated in this source are due to a combination of spontaneous and induced fission processes, each with a unique neutron energy distribution and fission product yield. The physical conditions of the source (i.e., size, shape, etc.) will have a significant influence on the neutron flux distribution and the induced fission probability associated with 240Pu. Thus, it is likely that there is a relationship between the combined (spontaneous and induced) fission yield and the physical conditions of the source. Exploring this relationship, a table of values will be generated to predict the combined fission product yield for any source geometry containing 240Pu. Minimizing variations in the source geometry should stabilize the combined fission product yield and provide a means to determine the spontaneous fission probability for 240Pu. This research has identified that the combined fission product yields from 97Zr and 138Xe exhibit less sensitivity to the physical source parameters than other fission products making them good candidates as radiochronometers for age dating weapons-grade plutonium.
Henry Spitz, Ph.D. (Committee Chair)
Zhongyun Dong, M.D. Ph.D. (Committee Member)
Sam Glover, Ph.D. (Committee Member)
Bingjing Su, Ph.D. (Committee Member)
100 p.

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Citations

  • Xie, T. (2015). Monte Carlo Simulation Research on the Spontaneous Fission Yield of 240Pu [Doctoral dissertation, University of Cincinnati]. OhioLINK Electronic Theses and Dissertations Center. http://rave.ohiolink.edu/etdc/view?acc_num=ucin1448275275

    APA Style (7th edition)

  • Xie, Tianyou. Monte Carlo Simulation Research on the Spontaneous Fission Yield of 240Pu. 2015. University of Cincinnati, Doctoral dissertation. OhioLINK Electronic Theses and Dissertations Center, http://rave.ohiolink.edu/etdc/view?acc_num=ucin1448275275.

    MLA Style (8th edition)

  • Xie, Tianyou. "Monte Carlo Simulation Research on the Spontaneous Fission Yield of 240Pu." Doctoral dissertation, University of Cincinnati, 2015. http://rave.ohiolink.edu/etdc/view?acc_num=ucin1448275275

    Chicago Manual of Style (17th edition)