The Solution Method for Ultra-Fine Group Slowing-Down Equations Applicable to Stochastic Media.
- Published in:
- Mathematics (2227-7390), 2025, v. 13, n. 11, p. 1857, doi. 10.3390/math13111857
- By:
- Publication type:
- Article
Works matching DE "MIXED oxide fuels (Nuclear engineering)"
Results: 107
1
2
Neutron Cross-Section Uncertainty and Reactivity Analysis in MOX and Metal Fuels for Sodium-Cooled Fast Reactor.
- Published in:
- Atoms (2218-2004), 2025, v. 13, n. 5, p. 41, doi. 10.3390/atoms13050041
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- Publication type:
- Article
3
A mathematical model of nanoparticulate mixed oxide pseudocapacitors; part II: the effects of intrinsic factors.
- Published in:
- Journal of Solid State Electrochemistry, 2011, v. 15, n. 1, p. 115, doi. 10.1007/s10008-010-1072-2
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- Publication type:
- Article
4
Preliminary investigation on the sodium fast reactor concave cores with near‐zero or negative sodium void reactivity.
- Published in:
- International Journal of Energy Research, 2020, v. 44, n. 10, p. 8025, doi. 10.1002/er.4913
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- Publication type:
- Article
5
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>.
- Published in:
- Catalysis Letters, 2009, v. 127, n. 3/4, p. 270, doi. 10.1007/s10562-008-9640-0
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- Publication type:
- Article
6
Waste-Reducing Catalysis for Acylation of a Secondary Amine: Synthesis of DEET.
- Published in:
- Catalysis Letters, 2004, v. 98, n. 2/3, p. 69, doi. 10.1007/s10562-004-7933-5
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- Publication type:
- Article
7
Nuclear or not? The complex and uncertain politics of Japan’s post-Fukushima energy policy.
- Published in:
- Bulletin of the Atomic Scientists, 2011, v. 67, n. 5, p. 19, doi. 10.1177/0096340211421475
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- Publication type:
- Article
8
Comparative Estimation of the Plutonium (238Pu, 239+240Pu) and Radiocesium (137Cs) Content in Bottom Sediments and Hydrobionts of the Yenisei River.
- Published in:
- Doklady Earth Sciences, 2020, v. 492, n. 2, p. 434, doi. 10.1134/S1028334X20060227
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- Publication type:
- Article
9
MOX FUEL CHARACTERIZATION FOR BURNUP CREDIT APPLICATION: EXTENSION OF NONDESTRUCTIVE METHOD QUALIFIED FOR LEU FUELS.
- Published in:
- Nuclear Technology, 2006, v. 154, n. 2, p. 186, doi. 10.13182/NT06-A3727
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- Publication type:
- Article
10
PLUTONIUM RECYCLING IN LIGHT WATER REACTORS AT FRAMATOME ANP: STATUS AND TRENDS.
- Published in:
- Nuclear Technology, 2005, v. 151, n. 2, p. 159, doi. 10.13182/NT05-A3640
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- Publication type:
- Article
11
PYROPROCESSING OF LIGHT WATER REACTOR SPENT FUELS BASED ON AN ELECTROCHEMICAL REDUCTION TECHNOLOGY.
- Published in:
- Nuclear Technology, 2005, v. 150, n. 2, p. 153, doi. 10.13182/NT05-A3613
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- Publication type:
- Article
12
The Plutonium Issue: Terrorism vs Human Rights.
- Published in:
- 1997
- By:
- Publication type:
- Editorial
13
Birlešmiš Milletler Deniz Hukuku Sözlešmesi Uyannca Uyušmazliklarin Çözümü: Mox Plant Davasi ve Yargi Yetkilerinin Örtüšmesi.
- Published in:
- Review of International Law & Politics / Uluslararasi Hukuk ve Politika, 2008, v. 4, n. 16, p. 57
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- Publication type:
- Article
14
M0x returned amid protests.
- Published in:
- International Power Generation, 2002, v. 25, n. 8, p. 5
- Publication type:
- Article
15
Ireland vows to fight UK government over Sellafield MOx decision.
- Published in:
- International Power Generation, 2002, v. 25, n. 1, p. 4
- Publication type:
- Article
16
Military MOX fuel for US nuclear plant.
- Published in:
- International Power Generation, 1999, v. 22, p. 7
- Publication type:
- Article
17
Safeguards-by-Design (SBD) Concepts for Thorium-based Fuel Fabrication Facilities.
- Published in:
- Journal of the Institute of Nuclear Materials Management, 2012, v. 41, n. 1, p. 43
- By:
- Publication type:
- Article
18
NNSA Announces Letter of Intent Signed by MOX Services and the TVA.
- Published in:
- Journal of the Institute of Nuclear Materials Management, 2009, v. 38, n. 1, p. 57
- Publication type:
- Article
19
Measurement and Characterization of Nuclear Material at Idaho National Laboratory.
- Published in:
- Journal of the Institute of Nuclear Materials Management, 2009, v. 38, n. 1, p. 40
- By:
- Publication type:
- Article
20
Contract Awarded for Construction of NNSA's Waste Solidification Building at SRS.
- Published in:
- Journal of the Institute of Nuclear Materials Management, 2009, v. 38, n. 1, p. 57
- Publication type:
- Article
21
Structural investigation of Ce<sub>2</sub>Zr<sub>2</sub>O<sub>8</sub> after redox treatments which lead to low temperature reduction.
- Published in:
- Topics in Catalysis, 2007, v. 41, n. 1-4, p. 35, doi. 10.1007/s11244-006-0092-8
- By:
- Publication type:
- Article
22
On the Burning of Plutonium Originating from Light Water Reactor Use in a Fast Molten Salt Reactor--A Neutron Physical Study.
- Published in:
- Energies (19961073), 2015, v. 8, n. 11, p. 12557, doi. 10.3390/en81112328
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- Publication type:
- Article
23
ELECTRICAL PROPERTIES OF Nb-DOPED Pb(Zr<sub>0.52</sub>Ti<sub>0.48</sub>)O<sub>3</sub> CERAMICS.
- Published in:
- International Journal of Modern Physics B: Condensed Matter Physics; Statistical Physics; Applied Physics, 2009, v. 23, n. 1, p. 105, doi. 10.1142/S0217979209049711
- By:
- Publication type:
- Article
24
Feasibility Study of 1/3 Thorium-Plutonium Mixed Oxide Core.
- Published in:
- Science & Technology of Nuclear Installations, 2014, p. 1, doi. 10.1155/2014/709415
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- Publication type:
- Article
25
Economic Evaluation on the MOX Fuel in the Closed Fuel Cycle.
- Published in:
- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/698019
- By:
- Publication type:
- Article
26
IMPLICATIONS OF PLUTONIUM ISOTOPIC SEPARATION ON CLOSED FUEL CYCLES AND REPOSITORY DESIGN.
- Published in:
- Nuclear Technology, 2015, v. 189, n. 1, p. 63, doi. 10.13182/NT13-137
- By:
- Publication type:
- Article
27
A STYLIZED THREE-DIMENSIONAL PRESSURIZED WATER REACTOR BENCHMARK PROBLEM WITH UO<sub>2</sub> AND MOX FUEL.
- Published in:
- Nuclear Technology, 2013, v. 184, n. 1, p. 1, doi. 10.13182/NT11-124
- By:
- Publication type:
- Article
28
EFFECTS OF NUCLEAR DATA UNCERTAINTIES ON THE NEA/OECD PWR MOX/UO<sub>2</sub> CORE ROD EJECTION BENCHMARK.
- Published in:
- Nuclear Technology, 2013, v. 183, n. 3, p. 464, doi. 10.13182/NT183-464
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- Publication type:
- Article
29
WIMS/PANTHER ANALYSIS OF UO<sub>2</sub>/MOX CORES USING EMBEDDED SUPERCELLS.
- Published in:
- Nuclear Technology, 2013, v. 183, n. 3, p. 398, doi. 10.13182/NT13-A19428
- By:
- Publication type:
- Article
30
DESIGN STUDY TO INCREASE PLUTONIUM CONVERSION RATIO OF HC-FLWR CORE.
- Published in:
- Nuclear Technology, 2012, v. 179, n. 3, p. 309, doi. 10.13182/NT12-A14165
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- Publication type:
- Article
31
IRRADIATION TEST OF MOX FUEL RODS FABRICATED BY ATTRITION-MILLING AND ANALYSIS OF IN-PILE DATA WITH COSMOS CODE.
- Published in:
- Nuclear Technology, 2010, v. 172, n. 3, p. 246, doi. 10.13182/NT10-A10933
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- Publication type:
- Article
32
FEASIBILITY STUDY ON A SIMPLIFIED MOX PELLET FABRICATION PROCESS, THE SHORT PROCESS FOR FAST BREEDER REACTOR FUEL.
- Published in:
- Nuclear Technology, 2009, v. 167, n. 3, p. 348, doi. 10.13182/NT09-A9075
- By:
- Publication type:
- Article
33
ASSESSING THE PROLIFERATION RESISTANCE OF NUCLEAR FUEL CYCLE SYSTEMS USING A FUZZY LOGIC-BASED BARRIER METHOD.
- Published in:
- Nuclear Technology, 2008, v. 162, n. 3, p. 293, doi. 10.13182/NT08-A3957
- By:
- Publication type:
- Article
34
RECOVERY OF U-Pu ALLOY FROM MOX USING A PYROPROCESS SERIES.
- Published in:
- Nuclear Technology, 2008, v. 162, n. 2, p. 118, doi. 10.13182/NT08-A3937
- By:
- Publication type:
- Article
35
CHARACTERISTICS AND SINTERABILITY OF MOX POWDER PREPARED BY THE MICROWAVE HEATING DENITRATION METHOD.
- Published in:
- Nuclear Technology, 2008, v. 162, n. 3, p. 265, doi. 10.13182/NT08-A3955
- By:
- Publication type:
- Article
36
IMPROVEMENT OF FUEL PERFORMANCE CODE COSMOS WITH RECENT IN-PILE DATA FOR MOX AND UO<sub>2</sub> FUELS.
- Published in:
- Nuclear Technology, 2007, v. 157, n. 1, p. 53, doi. 10.13182/NT07-A3801
- By:
- Publication type:
- Article
37
ASSESSMENT OF A MOX FUEL ASSEMBLY DESIGN FOR A BWR MIXED RELOAD.
- Published in:
- Nuclear Technology, 2006, v. 156, n. 3, p. 247, doi. 10.13182/NT06-A3788
- By:
- Publication type:
- Article
38
Kinetics of dissolution of simulated (U–Ce) MOX fuel pellet in nitric acid.
- Published in:
- Journal of Radioanalytical & Nuclear Chemistry, 2022, v. 331, n. 11, p. 4529, doi. 10.1007/s10967-022-08582-w
- By:
- Publication type:
- Article
39
Analysis of auto gamma images of plutonium bearing fuels: a comparative study of experimental and simulation methods.
- Published in:
- Journal of Radioanalytical & Nuclear Chemistry, 2021, v. 327, n. 2, p. 913, doi. 10.1007/s10967-020-07561-3
- By:
- Publication type:
- Article
40
Determination of cerium concentration in samples obtained during dissolution of CeO<sub>2</sub> and (Ce, U)O<sub>2</sub> mixed oxide.
- Published in:
- Journal of Radioanalytical & Nuclear Chemistry, 2019, v. 319, n. 3, p. 891, doi. 10.1007/s10967-018-6398-8
- By:
- Publication type:
- Article
41
Analysis of Th and U in thorium-based mixed-oxide fuel using wavelength dispersive X-ray fluorescence spectrometer.
- Published in:
- Journal of Radioanalytical & Nuclear Chemistry, 2019, v. 319, n. 3, p. 775, doi. 10.1007/s10967-018-6387-y
- By:
- Publication type:
- Article
42
Reductive dissolution studies of CeO<sub>2</sub> and simulated mixed oxide fuel of (Ce, U)O<sub>2</sub> in nitric acid medium.
- Published in:
- Journal of Radioanalytical & Nuclear Chemistry, 2019, v. 319, n. 3, p. 1127, doi. 10.1007/s10967-018-6372-5
- By:
- Publication type:
- Article
43
New approaches to reprocessing of oxide nuclear fuel.
- Published in:
- Journal of Radioanalytical & Nuclear Chemistry, 2013, v. 296, n. 2, p. 1127, doi. 10.1007/s10967-012-2260-6
- By:
- Publication type:
- Article
44
Mechanochemically induced synthesis of UO and uranium-thorium mixed oxides from sol-gel produced precursors.
- Published in:
- Journal of Radioanalytical & Nuclear Chemistry, 2011, v. 287, n. 2, p. 519, doi. 10.1007/s10967-010-0707-1
- By:
- Publication type:
- Article
45
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.
- Published in:
- Journal of Radioanalytical & Nuclear Chemistry, 2009, v. 279, n. 2, p. 481, doi. 10.1007/s10967-007-7314-4
- By:
- Publication type:
- Article
46
Application of neutron well coincidence counting for plutonium determination in mixed oxide fuel fabrication plant.
- Published in:
- Journal of Radioanalytical & Nuclear Chemistry, 2008, v. 277, n. 2, p. 419, doi. 10.1007/s10967-007-7083-5
- By:
- Publication type:
- Article
47
Extraction and separation of uranium, plutonium and americium from MOX fuel rejected waste and analytical phosphoric acid based waste using organophosphorus extractants.
- Published in:
- Journal of Radioanalytical & Nuclear Chemistry, 2003, v. 256, n. 2, p. 185, doi. 10.1023/A:1023960612091
- By:
- Publication type:
- Article
48
上钠腔设计对大型MOX燃料快堆冷却剂沸腾瞬态的影响研究.
- Published in:
- Atomic Energy Science & Technology, 2024, v. 58, n. 9, p. 1866, doi. 10.7538/yzk.2024.youxian.0294
- By:
- Publication type:
- Article
49
超临界二氧化碳冷却反应堆空泡反应性研究.
- Published in:
- Atomic Energy Science & Technology, 2023, v. 57, n. 9, p. 1699, doi. 10.7538/yzk.2023.youxian.0272
- By:
- Publication type:
- Article
50
种基于本征正交分解的并群方法.
- Published in:
- Atomic Energy Science & Technology, 2023, v. 57, n. 8, p. 1575, doi. 10.7538/yzk.2022.youxian.0832
- By:
- Publication type:
- Article