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18429.pdf (2.16 MB)
ETD Abstract Container
Abstract Header
Monte Carlo Simulation Research on the Spontaneous Fission Yield of 240Pu
Author Info
Xie, Tianyou
ORCID® Identifier
http://orcid.org/0000-0003-1004-742X
Permalink:
http://rave.ohiolink.edu/etdc/view?acc_num=ucin1448275275
Abstract Details
Year and Degree
2015, PhD, University of Cincinnati, Engineering and Applied Science: Nuclear and Radiological Engineering.
Abstract
This research describes results of mathematical simulations to predict the spontaneous fission yield of
240
Pu 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
240
Pu as a radiochronometer. However, the fission product inventory from the spontaneous fission of
240
Pu 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
240
Pu 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
240
Pu. 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
240
Pu. Minimizing variations in the source geometry should stabilize the combined fission product yield and provide a means to determine the spontaneous fission probability for
240
Pu. This research has identified that the combined fission product yields from
97
Zr and
138
Xe exhibit less sensitivity to the physical source parameters than other fission products making them good candidates as radiochronometers for age dating weapons-grade plutonium.
Committee
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)
Pages
100 p.
Subject Headings
Engineering
Keywords
Pu
;
spontaneous fission
;
induced fission
;
radiochronomiter
Recommended Citations
Refworks
EndNote
RIS
Mendeley
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)
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Document number:
ucin1448275275
Download Count:
966
Copyright Info
© 2015, all rights reserved.
This open access ETD is published by University of Cincinnati and OhioLINK.