journal article·2009-03Open access

Characterization of minor actinide mixed oxide fuel

A.D. Neuman, C.C. Davis, T.A. Nothwang, F.G. Hampel, S.L. Voit, M.R. Lopez, A.C. Martinez

Journal of Nuclear Materials· Volume 385· Issue 1

Abstract

Abstract The global nuclear energy partnership (GNEP) was created in order for ‘fuel-cycle supplier’ nations to provide assured supplies of nuclear fuel to ‘fuel-cycle customer’ nations. The customer nations would utilize the fuel for electricity generation and subsequently return it to the supplier nation after it is spent. This spent fuel would then be reprocessed by the supplier nation in order to recycle the actinide constituents, mainly uranium and plutonium, in advanced nuclear power reactors, and thus reduce waste volumes [1] , [2] . The International Atomic Energy Agency would control the nuclear materials. One of the thrust areas for the GNEP program is the development of these actinide bearing fuels for transmutation in a fast reactor.
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Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Fusion materials and technologies

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (11)

Show source-provided references
1. Keiser · JOM · 2008 · 60 · 1410.1007/s11837-008-0004-4 ↗
2. Global Nuclear Energy Partnership Technology Development Plan Report 25 July 2007 (GNEP-TECH-TR-PP-2007-00020, Rev 0), p. 177.
3. Sheppard · American Ceramic Society Bulletin · 2008 · 87 · 20
4. Lessing · Materials for Radiation Service · 2006 · 94 · 838
5. Chang · Reactor Physics Design, Validation, and Operating Experience · 2006 · 94 · 589
6. Chang · Journal of Alloys and Compounds · 2007 · 444–445 · 43410.1016/j.jallcom.2007.02.158 ↗
7. B.A. Hilton et al., US Plans for the Next Fast Reactor Transmutation Fuels Irradiation Test, Global 2007, Boise, Idaho, 2007, p. 1688.
8. Mouney · Comptes Rendus Physique · 2002 · 3 · 77310.1016/S1631-0705(02)01374-9 ↗
9. Koyama · Journal of Nuclear Science and Technology · 1998 · 35 · 40610.3327/jnst.35.406 ↗
10. A.D. Neuman et al., Characterization of Tru-MOX powders and pellets, in: REWAS 2008 Proceedings on CD-ROM, 2008.
11. T.A. Nothwang et al., Particle Size and Morphology of MA-MOX Precursor Powders, in: REWAS 2008 Proceedings on CD-ROM, 2008.