Works matching DE "MIXED oxide fuels (Nuclear engineering)"
Results: 85
Separation of U, Pu, and Am recovered from mixed oxide (MOX) fuel by countercurrent chromatography.
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- Radiochemistry, 2007, v. 49, n. 2, p. 162, doi. 10.1134/S1066362207020117
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Simulation of LEU and MOX fuels in Russian VVER-1000 reactor with the OpenMC code and recent data libraries.
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- Annals of the University of Craiova, Physics, 2022, v. 32, p. 1
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Birlešmiš Milletler Deniz Hukuku Sözlešmesi Uyannca Uyušmazliklarin Çözümü: Mox Plant Davasi ve Yargi Yetkilerinin Örtüšmesi.
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- Review of International Law & Politics / Uluslararasi Hukuk ve Politika, 2008, v. 4, n. 16, p. 57
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Plutonium plans in limbo.
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- Nature, 2011, v. 476, n. 7359, p. 140, doi. 10.1038/476140a
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Japan anticipates green light for nuclear plants.
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- Nature, 2006, v. 440, n. 7081, p. 138, doi. 10.1038/440138a
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Improved <sup>242</sup>Pu(n,γ) thermal cross section combining activation and prompt gamma analysis.
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- European Physical Journal A -- Hadrons & Nuclei, 2019, v. 55, n. 5, p. N.PAG, doi. 10.1140/epja/i2019-12730-6
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Comparative Estimation of the Plutonium (238Pu, 239+240Pu) and Radiocesium (137Cs) Content in Bottom Sediments and Hydrobionts of the Yenisei River.
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- Doklady Earth Sciences, 2020, v. 492, n. 2, p. 434, doi. 10.1134/S1028334X20060227
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New approaches to reprocessing of oxide nuclear fuel.
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- Journal of Radioanalytical & Nuclear Chemistry, 2013, v. 296, n. 2, p. 1127, doi. 10.1007/s10967-012-2260-6
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Mechanochemically induced synthesis of UO and uranium-thorium mixed oxides from sol-gel produced precursors.
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- Journal of Radioanalytical & Nuclear Chemistry, 2011, v. 287, n. 2, p. 519, doi. 10.1007/s10967-010-0707-1
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Non-destructive assay technique for the determination of <sup>238</sup>U/<sup>232</sup>Th ratio in the mixed oxides of uranium and thorium using prompt gamma-ray neutron activation.
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- Journal of Radioanalytical & Nuclear Chemistry, 2009, v. 279, n. 2, p. 481, doi. 10.1007/s10967-007-7314-4
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Application of neutron well coincidence counting for plutonium determination in mixed oxide fuel fabrication plant.
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- Journal of Radioanalytical & Nuclear Chemistry, 2008, v. 277, n. 2, p. 419, doi. 10.1007/s10967-007-7083-5
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Extraction and separation of uranium, plutonium and americium from MOX fuel rejected waste and analytical phosphoric acid based waste using organophosphorus extractants.
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- Journal of Radioanalytical & Nuclear Chemistry, 2003, v. 256, n. 2, p. 185, doi. 10.1023/A:1023960612091
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Sellafield MOX plant to close.
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- TCE: The Chemical Engineer, 2011, n. 843, p. 10
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Using Coupled Mesoscale Experiments and Simulations to Investigate High Burn-Up Oxide Fuel Thermal Conductivity.
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- JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2014, v. 66, n. 12, p. 2569, doi. 10.1007/s11837-014-1160-3
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Effect of composition on the surface and electrocatalytic properties of Ti/IrO<sub> x </sub>+RhO<sub> x </sub> electrodes: H<sub>2</sub> evolution from acidic solution.
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- Journal of Applied Electrochemistry, 2005, v. 35, n. 12, p. 1213, doi. 10.1007/s10800-005-9032-8
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A mathematical model of nanoparticulate mixed oxide pseudocapacitors; part II: the effects of intrinsic factors.
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- Journal of Solid State Electrochemistry, 2011, v. 15, n. 1, p. 115, doi. 10.1007/s10008-010-1072-2
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UK plans for coping with plutonium waste fail to impress.
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- Nature, 1997, v. 390, n. 6659, p. 435, doi. 10.1038/37205
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Safeguards-by-Design (SBD) Concepts for Thorium-based Fuel Fabrication Facilities.
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- Journal of the Institute of Nuclear Materials Management, 2012, v. 41, n. 1, p. 43
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NNSA Announces Letter of Intent Signed by MOX Services and the TVA.
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- Journal of the Institute of Nuclear Materials Management, 2009, v. 38, n. 1, p. 57
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Contract Awarded for Construction of NNSA's Waste Solidification Building at SRS.
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- Journal of the Institute of Nuclear Materials Management, 2009, v. 38, n. 1, p. 57
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Measurement and Characterization of Nuclear Material at Idaho National Laboratory.
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- Journal of the Institute of Nuclear Materials Management, 2009, v. 38, n. 1, p. 40
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Catalytic Removal of Toluene over Co<sub>3</sub>O<sub>4</sub>–CeO<sub>2</sub> Mixed Oxide Catalysts: Comparison with Pt/Al<sub>2</sub>O<sub>3</sub>.
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- Catalysis Letters, 2009, v. 127, n. 3/4, p. 270, doi. 10.1007/s10562-008-9640-0
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ELECTRICAL PROPERTIES OF Nb-DOPED Pb(Zr<sub>0.52</sub>Ti<sub>0.48</sub>)O<sub>3</sub> CERAMICS.
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- International Journal of Modern Physics B: Condensed Matter Physics; Statistical Physics; Applied Physics, 2009, v. 23, n. 1, p. 105, doi. 10.1142/S0217979209049711
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Structural and Magnetic Investigations of Fe[sub 2]O[sub 3]-B[sub 2]O[sub 3]-CaF[sub 2] Glass System.
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- International Journal of Modern Physics B: Condensed Matter Physics; Statistical Physics; Applied Physics, 2003, v. 17, n. 13, p. 2633, doi. 10.1142/S0217979203018430
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M0x returned amid protests.
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- International Power Generation, 2002, v. 25, n. 8, p. 5
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Ireland vows to fight UK government over Sellafield MOx decision.
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- International Power Generation, 2002, v. 25, n. 1, p. 4
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Military MOX fuel for US nuclear plant.
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- International Power Generation, 1999, v. 22, p. 7
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Nuclear Power Plants in India.
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- Indian Journal of Power & River Valley Development, 2020, v. 70, n. 5/6, p. 103
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On the Consistent Spatial Homogenization Method in Neutron Transport Theory.
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- Journal of Computational & Theoretical Transport, 2014, v. 43, n. 1-7, p. 240, doi. 10.1080/00411450.2014.913185
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The MOX Plant Case: The Question of "Supplemental Jurisdiction" for International Environmental Claims Under UNCLOS.
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- Texas International Law Journal, 2006, v. 42, n. 1, p. 211
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Thermal‐hydraulic analysis of UO2 and MOX fuel considering different cladding materials at various burnup levels in pressurized water reactor.
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- Heat Transfer, 2021, v. 50, n. 7, p. 7215, doi. 10.1002/htj.22225
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Multi-physics DONJON5 reactor models for improved fuel cycle simulation with CLASS.
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- EPJ Nuclear Sciences & Technologies, 2024, v. 10, p. 1, doi. 10.1051/epjn/2024008
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Spent nuclear fuel management, characterisation, and dissolution behaviour: progress and achievement from SFC and DisCo.
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- EPJ Nuclear Sciences & Technologies, 2023, v. 9, p. 1, doi. 10.1051/epjn/2022029
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Development of a MOX equivalence Python code package for ANICCA.
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- EPJ Nuclear Sciences & Technologies, 2021, v. 7, p. 1, doi. 10.1051/epjn/2021023
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Three-component U-Pu-Th fuel for plutonium irradiation in heavy water reactors.
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- EPJ Nuclear Sciences & Technologies, 2016, v. 2, p. 1, doi. 10.1051/epjn/2016022
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Will MOX fuel guarantee a glowing future?
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- Business & Society Review (00453609), 1996, n. 98, p. 4
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Nuclear or not? The complex and uncertain politics of Japan’s post-Fukushima energy policy.
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- Bulletin of the Atomic Scientists, 2011, v. 67, n. 5, p. 19, doi. 10.1177/0096340211421475
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Should the United States resume reprocessing? A pro and con.
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- Bulletin of the Atomic Scientists, 2009, v. 65, n. 6, p. 30, doi. 10.2968/065006003
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Nukes without borders.
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- Bulletin of the Atomic Scientists, 2004, v. 60, n. 1, p. 8
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Thorium: A way out?
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- Bulletin of the Atomic Scientists, 2003, v. 59, n. 5, p. 48
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Between MOX and a hard place.
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- Bulletin of the Atomic Scientists, 2003, v. 59, n. 5, p. 46
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PLUTONIUM Can Germany swear off?
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- Bulletin of the Atomic Scientists, 2001, v. 57, n. 3, p. 63, doi. 10.1080/00963402.2001.11460459
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JAPAN'S nuclear twilight zone.
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- Bulletin of the Atomic Scientists, 2001, v. 57, n. 3, p. 58, doi. 10.1080/00963402.2001.11460458
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Plutonium disposal, the third way.
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- Bulletin of the Atomic Scientists, 2001, v. 57, n. 3, p. 53, doi. 10.1080/00963402.2001.11460456
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Bury the stuff.
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- Bulletin of the Atomic Scientists, 1997, v. 53, n. 2, p. 45
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Japanese Plutonium Stockpiles: A Transportation, Storage, and Public Relations Challenge.
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- Journal of Environment & Development, 2003, v. 12, n. 1, p. 99, doi. 10.1177/1070496502250441
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Neutron field characterisation at mixed oxide fuel plant.
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- Radiation Protection Dosimetry, 2012, v. 150, n. 2, p. 231, doi. 10.1093/rpd/ncr390
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Development of a hand-held fast neutron survey meter.
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- Radiation Protection Dosimetry, 2011, v. 146, n. 1-3, p. 72, doi. 10.1093/rpd/ncr114
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Kinetics of dissolution of simulated (U–Ce) MOX fuel pellet in nitric acid.
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- Journal of Radioanalytical & Nuclear Chemistry, 2022, v. 331, n. 11, p. 4529, doi. 10.1007/s10967-022-08582-w
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Analysis of auto gamma images of plutonium bearing fuels: a comparative study of experimental and simulation methods.
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- Journal of Radioanalytical & Nuclear Chemistry, 2021, v. 327, n. 2, p. 913, doi. 10.1007/s10967-020-07561-3
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