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Title: Short Communication on “Direct compositional quantification of (U-Th)O 2 - MOX nuclear fuel using ns-UV-LIBS and chemometric regression models”

Authors:
; ORCiD logo; ;
Publication Date:
Sponsoring Org.:
USDOE Office of Science (SC), Basic Energy Sciences (BES) (SC-22)
OSTI Identifier:
1396856
Grant/Contract Number:
AC02-05CH11231
Resource Type:
Journal Article: Publisher's Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 484; Journal Issue: C; Related Information: CHORUS Timestamp: 2017-10-04 15:30:23; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
Netherlands
Language:
English

Citation Formats

Singh, Manjeet, Sarkar, Arnab, Mao, Xianglei, and Russo, Richard E. Short Communication on “Direct compositional quantification of (U-Th)O 2 - MOX nuclear fuel using ns-UV-LIBS and chemometric regression models”. Netherlands: N. p., 2017. Web. doi:10.1016/j.jnucmat.2016.11.025.
Singh, Manjeet, Sarkar, Arnab, Mao, Xianglei, & Russo, Richard E. Short Communication on “Direct compositional quantification of (U-Th)O 2 - MOX nuclear fuel using ns-UV-LIBS and chemometric regression models”. Netherlands. doi:10.1016/j.jnucmat.2016.11.025.
Singh, Manjeet, Sarkar, Arnab, Mao, Xianglei, and Russo, Richard E. Wed . "Short Communication on “Direct compositional quantification of (U-Th)O 2 - MOX nuclear fuel using ns-UV-LIBS and chemometric regression models”". Netherlands. doi:10.1016/j.jnucmat.2016.11.025.
@article{osti_1396856,
title = {Short Communication on “Direct compositional quantification of (U-Th)O 2 - MOX nuclear fuel using ns-UV-LIBS and chemometric regression models”},
author = {Singh, Manjeet and Sarkar, Arnab and Mao, Xianglei and Russo, Richard E.},
abstractNote = {},
doi = {10.1016/j.jnucmat.2016.11.025},
journal = {Journal of Nuclear Materials},
number = C,
volume = 484,
place = {Netherlands},
year = {Wed Feb 01 00:00:00 EST 2017},
month = {Wed Feb 01 00:00:00 EST 2017}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record at 10.1016/j.jnucmat.2016.11.025

Citation Metrics:
Cited by: 1work
Citation information provided by
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  • The relative concentrations of oxygen in the unrestructured regions of several irradiated fuel elements of the composition (U,Pu)O/sub 2-x/ have been measured by electron microprobe methods. Fluctuations were found between closely spaced points, which indicate that hyperstoichiometric diffusion paths may well be formed and may greatly facilitate oxygen transport from the interior to the edge of the elements. In some cases, average expected radial oxygen gradients were computed for the unrestructured regions, using literature data. The results indicate that a very small excess of oxygen, above the stoichiometric amount, is sufficient to account for the observed transport. (NL)
  • Optimized breeding performances of three breeder strategies are compared. The first strategy is the normal mixed plutonium-uranium oxide fuel cycle, which is used as a reference case. The second is based on the use of the light water reactor generated plutonium in interim Pu-Th (metallic fuel) breeders cooled with sodium to build up /sup 233/U inventory for use in liquid-metal fast breeder reactors fueled with metallic /sup 233/U-Th. The third is based on a combination cycle involving two reactor types, Pu-Th and /sup 233/U/sup 238/U, both using metallic fuel and sodium as a coolant. These reactors will operate simultaneously; themore » excess /sup 233/U generated in the Pu-Th reactors is used to fuel the /sup 233/U-/sup 238/U reactors and the plutonium generated in the /sup 233/U-/sup 238/U reactors is used to fuel the Pu-Th reactors. The combination cycle has obvious antiproliferation characteristics. The breeding performance as measured by optimized compound system doubling time for nominal 1000-MW(electric) systems was 8.8 years for the combination system of Pu-Th and /sup 233/U-/sup 238/U reactors, 31.4 years for the /sup 233/U-Th reactor, and 14 years for the (Pu-U)O/sub 2/ reactor. The corresponding optimum fuel pin diameters were 0.30, 0.37, and 0.28 in., respectively. The ..delta..k/k change associated with the removal of all the sodium from the inner core (inner to outer core volume ratio is 60:40) was +0.03, +1.01, +1.23, and +2.60% for the /sup 233/U-Th, /sup 233/U-/sup 238/U, Pu-Th, and (Pu-U)O/sub 2/ reactors, respectively. Preliminary calculations indicate that it is possible to design the /sup 233/U-/sup 238/U reactors to operate on an extended cycle such that once the reactor is built, it only needs natural uranium as feed fuel for the rest of the lifetime of the reactor. Estimates of the fuel cycle costs of each reactor show that the cost of the extended burnup cycle is about35% less than the (Pu-U)O/sub 2/ cycle.« less
  • For refabrication of high-temperature reactor fuel elements, a process for producing dense ThO/sub 2/ and (Th,U)O/sub 2/ microspheres has been developed. The process is an external gelation process and takes full advantage of the gelation features of thorium hydroxide for formation of particles. Unlike other external gelation methods, neither viscosity increase by adding other substances (e.g., organic polymers) to the broth nor drop formation in organic liquids is employed. The method uses few process steps and only simple process equipment. A pilot plant has been constructed that operation with one nozzle can produce 1 kg/h of (Th,U)O/sub 2/ microspheres 500more » ..mu..m in diameter.« less