Multiple Monoenergetic Gamma Radiography (MMGR) using compact superconducting cyclotron by Lee, Hin Yeung.

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Assessment of innovative fuel designs for high performance light water reactors by Carpenter, David Michael

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Micro-heterogeneous thorium based fuel concepts for pressurized water reactions by Zhao, Xianfeng, 1971-

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Monazite-Type SmPO₄ as Potential Nuclear Waste Form: Insights into Radiation Effects from Ion-Beam Irradiation and Atomistic Simulations by Julia M. Leys, Yaqi Ji, Martina Klinkenberg, Piotr M. Kowalski, Hartmut Schlenz, Stefan Neumeier, Dirk Bosbach, Guido Deissmann

“…Single-phase monazite-type ceramics are considered as potential host matrices for the conditioning of separated plutonium and minor actinides. Sm-orthophosphates were synthesised and their behaviour under irradiation was investigated with respect to their long-term performance in the repository environment. …”
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Perspective Compounds for Immobilization of Spent Electrolyte from Pyrochemical Processing of Spent Nuclear Fuel by Svetlana A. Kulikova, Sergey S. Danilov, Anna V. Matveenko, Anna V. Frolova, Kseniya Y. Belova, Vladimir G. Petrov, Sergey E. Vinokurov, Boris F. Myasoedov

“…Immobilization of spent electrolyte–radioactive waste (RW) generated during the pyrochemical processing of mixed nitride uranium–plutonium spent nuclear fuel is an acute task for further development of the closed nuclear fuel cycle with fast neutron reactors. …”
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Thermomechanical analysis of innovative nuclear fuel pin designs by Lerch Andrew (Andrew J.)

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Probabilistic transient analysis of fuel choices for sodium fast reactors by Denman, Matthew R

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Sensitivity analysis and optimization of the nuclear fuel cycle : a systematic approach by Passerini, Stefano

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KEBIJAKAN LUAR NEGERI AMERIKA SERIKAT TERHADAP MASALAH NUKLIR KOREA UTARA by , Uni Claritha Cendrawati Warembai, , Prof. Dr. Ichlasul Amal

“…Dated in December 27, 2002, North Korea told the IAEA surprisingly announced that they will reprocess reactor opening and allowing them to produce plutonium-based weapons in a few months. At the same time, the temperature of the conflict between the United States and North Korea are heating up colored by the attitude of some countries other than the United States who have an interest in North Korea. …”

Advances in Materials Science for Environmental and Nuclear Technology II / by Sundaram, S. K., 1958-, editor 521478

Control Experiences Regarding Clearable Materials from Nuclear Power Plants and Nuclear Installations: Scaling Factors Determination and Measurements’ Acceptance Criteria Definitio... by Luca Albertone, Massimo Altavilla, Manuela Marga, Laura Porzio, Giuseppe Tozzi, Pierangelo Tura

“…As a key nuclide, Co-60 was chosen for the activation products (Fe-55, Ni-59, Ni-63) and Cs-137 for fission products (Sr-90) and plutonium (Pu- 238, Pu-239/Pu-240, and Pu-241). The presence of very low radioactivity concentrations, often below the detection limits, can make it difficult to determine the related scaling factors. …”
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Rethinking the light water reactor fuel cycle by Shwageraus, Evgeni

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Core design and reactor physics of a breed and burn gas-cooled fast reactor by Yarsky, Peter

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Ssessment methodology for proliferation resistant fast breeder reactor by Singh, Mohit, S.M. Massachusetts Institute of Technology

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Modeling the performance of high burnup thoria and urania PWR fuel by Long, Yun, 1972-

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Heavy water and nonproliferation : topical report by Miller, M.

“…Also considered is the use of heavy water in plutonium production reactors as well as the broader issue of the relative nuclear leverage that suppliers can bring to bear on countries with natural ura- nium-fueled reactors as compared to those using enriched designs. …”
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Advanced design concepts for PWR and BWR high-performance annular fuel assemblies by Ellis, Tyler Shawn

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A fission-fusion hybrid reactor in steady-state L-mode tokamak configuration with natural uranium by Reed, Mark Wilbert

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A strategy for transition from a uranium fueled, open cycle SFR to a transuranic fueled, closed cycle sodium cooled fast reactor by Richard, Joshua (Joshua Glenn)

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Silicon carbide performance as cladding for advanced uranium and thorium fuels for light water reactors by Sukjai, Yanin

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