RAST-K v2—Three-Dimensional Nodal Diffusion Code for Pressurized Water Reactor Core Analysis by Jinsu Park, Jaerim Jang, Hanjoo Kim, Jiwon Choe, Dongmin Yun, Peng Zhang, Alexey Cherezov, Deokjung Lee

“…A depletion chain containing 22 actinides and 15 fission products and burnable absorbers was solved using the Chebyshev rational approximation method. …”
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Advances in Chemical and Electrochemical Oxidation of Americium by JIANG Hui, YAN Xin, LIU Zi-yi, WANG Dong-qi

“…Efficient trivalent actinides/lanthanides(Am3+/Ln3+) separation is one of the key components of advanced nuclear fuel cycle. …”
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Development of a new method for the detection of illicit materials based on the Active Photon Interrogation Method and photo-neutron spectrometry by Besnard-Vauterin C., Blideanu V., Rapp B.

“…Active photon interrogation methods have also been overlooked but they are currently limited to actinides detection using photo-fission reactions. …”
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Neutronic Evaluation of MSBR System Using MCNP Code by Clarysson Alberto Mello da Silva, Alana Lima Vieira, Isabella Resende Magalhães, Claubia Pereira

“…Current studies analyze the fuel transition from 235U/Th or Pu/Th to 233U/Th and, in this context, the present work evaluates the criticality and the neutron flux of MSBR (Molten Salt Breeder Reactor) considering the fuel: (i) mix of Th and enriched U; (ii) the combination of Th and reprocessed Pu; and (iii) matrix of reprocessed Pu/minor actinides (MAs) and Th. The goal is to verify which of these fuels can be used as initial fissile supply. …”
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A comparison of crystalline and molten structures of zirconolite (CaZrTi₂O₇), a potential plutonium wasteform medium, by molecular dynamics simulation and topological analysis by Rich, Sarah Celeste

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Identifikasi Radioisotop Teras Untuk Karakterisasi Inventory Produk Fisi Reaktor Riset 2 MW Dengan Menggunakan Program ORIGEN2.1 by Maharani, Tiolita

“…Nilai-nilai yang dianalisis tersebut berasal dari unsur U-235; U-238; Al; dan Si pada tiga bagian, yaitu Fission Products, Actinides & Daughters, dan Activation Products. Simulasi tersebut dijalankan dengan program ORIGEN2.1. …”
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Investigation on the effect of 238U replacement with 232Th in small modular reactor (SMR) fuel matrix by Uguru, Edwin Humphrey, Sani, Siti Fairus Abdul, Khandaker, Mayeen Uddin, Rabir, Mohamad Hairie

“…Large amount of 239Pu and actinides were produced from UO2 fuel due to the impact of 238U. …”

Did a Kilonova Set Off in Our Galactic Backyard 3.5 Myr ago? by Leonardo Chiesa, Albino Perego, Federico Maria Guercilena

“…While ^60 Fe is usually attributed to standard core-collapse supernovae, actinides are r -process nucleosynthesis yields, which are believed to be synthesized in rare events, such as special classes of supernovae or binary mergers involving at least one neutron star. …”
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Assessment of the Concentration of 51 Elements in the Liver and in Various Parts of the Human Brain—Profiling of the Mineral Status by Jacek Baj, Beata Kowalska, Wojciech Flieger, Elżbieta Radzikowska-Büchner, Alicja Forma, Marcin Czeczelewski, Paweł Kędzierawski, Kaja Karakuła, Michał Flieger, Dariusz Majerek, Grzegorz Teresiński, Ryszard Maciejewski, Jolanta Flieger

“…In addition, males had a significantly (<i>p</i> < 0.05) higher brain content of lanthanides and actinides than females. The results of this study show that the inhabitants of south-eastern Poland are exposed to a fairly uniform accumulation of aluminum and vanadium in the brain, which have the highest affinity to the thalamus dorsalis. …”
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Solubility and Valence Variation of Ce in Low-Alkali Borosilicate Glass and Glass Network Structure Analysis by Liu Yang, Yongchang Zhu, Jichuan Huo, Zhu Cui, Xingquan Zhang, Xuanjiang Dong, Jie Feng

“…Low-alkali borosilicate glass was used as the immobilization substrate, and Ce was used to replicate the trivalent and tetravalent actinides, in order to create simulated waste glass through melt heat treatment. …”
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Establishment of DeCART/MIG stochastic sampling code system and Application to UAM and BEAVRS benchmarks by Ho Jin Park, Jin Young Cho

“…For the S.S. calculations, a sample of 500 DeCART multi-group cross section sets for two major actinides, i.e., 235U and 238U, were generated by the MIG code and covariance data from the ENDF/B-VII.1 evaluated nuclear data library. …”
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Transmutation of MAs and LLFPs with a lead-cooled fast reactor by X. Y. Sun, L. H. Han, X. X. Li, B. L. Hu, W. Luo, L. Liu

“…These nuclear wastes include minor actinides (MAs: 237Np, 241Am, 243Am, 244Cm and 245Cm) and long-lived fission products (LLFPs: 79Se, 93Zr, 99Tc, 107Pd, 129I and 135Cs), and yet are hard to be handled. …”
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Enhancing Nuclear Security Concepts and Principles on Advanced Nuclear Reactor Courses by Harto, Andang Widi

“…To solve these problems, the advanced nuclear reactor designs must have breeding capability to utilize the far more plentiful fertile fuel resources (U-238 and Th-232) and capability to transmute trans-uranium nuclides or minor actinides. Learning on accidents occurred in some previous nuclear reactor, increasing safety aspect is needed for the next nuclear reactor design. …”
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Results of the 244Cm, 246Cm and 248Cm neutron-induced capture cross sections measurements at EAR1 and EAR2 of the n_TOF facility by Alcayne V., Mendoza E., Cano-Ott D., Kimura A., Aberle O., Amaducci S., Andrzejewski J., Audouin L., Babiano-Suarez V., Bacak M., Barbagallo M., Bécares V., Bečvář F., Bellia G., Berthoumieux E., Billowes J., Bosnar D., Brown A. S., Busso M., Caamaño M., Caballero L., Calviani M., Calviño F., Casanovas A., Cerutti F., Chen Y. H., Chiaveri E., Colonna N., Cortés G. P., Cortés-Giraldo M. A., Cosentino L., Cristallo S., Damone L. A., Diakaki M., Dietz M., Domingo-Pardo C., Dressler R., Dupont E., Durán I., Eleme Z., Fernández-Domíngez B., Ferrari A., Ferro-Gonçalves I., Finocchiaro P., Furman V., Garg R., Gawlik A., Gilardoni S., Glodariu T., Göbel K., González-Romero E., Guerrero C., Gunsing F., Heinitz S., Heyse J., Jenkins D. G., Jericha E., Kadi Y., Käppeler F., Kivel N., Kokkoris M., Kopatch Y., Krtička M., Kurtulgil D., Ladarescu I., Lederer-Woods C., Lerendegui-Marco J., Lo Meo S., Lonsdale S.-J., Macina D., Manna A., Martínez T., Masi A., Massimi C., Mastinu P. F., Mastromarco M., Matteucci F., Maugeri E., Mazzone A., Mengoni A., Michalopoulou V., Milazzo P. M., Mingrone F., Musumarra A., Negret A., Nolte R., Ogállar F., Oprea A., Patronis N., Pavlik A., Perkowski J., Piersanti L., Porras I., Praena J., Quesada J. M., Radeck D., Ramos Doval D., Reifarth R., Rochman D., Rubbia C., Sabaté-Gilarte M., Saxena A., Schillebeeckx P., Schumann D., Smith A. G., Sosnin N., Stamatopoulos A., Tagliente G., Tain J. L., Talip Z., Tarifeño-Saldivia A. E., Tassan-Got L., Torres-Sánchez P., Tsinganis A., Ulrich J., Urlass S., Valenta S., Vannini G., Variale V., Vaz P., Ventura A., Vlachoudis V., Vlastou R., Wallner A., Woods P. J., Wright T. J., Žugec P.

“…Accurate neutron capture cross section data for minor actinides (MAs) are required to estimate the production and transmutation rates of MAs in light water reactors, critical fast reactors like Gen-IV systems, and other innovative reactor systems such as accelerator driven systems (ADS). …”
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Recovery of Rare Earth Elements from Coal Fly Ash with Betainium Bis(trifluoromethylsulfonyl)imide: Different Ash Types and Broad Elemental Survey by Ting Liu, James C. Hower, Ching-Hua Huang

“…The process performance was evaluated for a broad range of elements (33 total), including 15 REEs, two actinides, six bulk elements, and 10 trace metals. …”
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Evaluation of core compositions for use in breed and burn reactors and limited-separations fuel cycles by Petroski, Robert, Forget, Benoit, Forsberg, Charles

“…Doubling times were calculated for a reactor fleet consisting of B&B reactors operating in a limited-separations fuel cycle; i.e., a fuel cycle with no chemical separation of actinides. The effects of different cooling times and removal of fission products using a melt refining process are evaluated. …”
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Table Top Exercise for Improving Risk Analysis Knowledge in Nuclear Reactor Design by Harto, Andang Widi

“…The MSR usually designed to have breeding capability to utilize the far more plentiful fertile fuel resources (U-238 and Th-232) and capability to transmute trans-uranium nuclides or minor actinides. The breeding and transmuting capability means the advanced reactor operation need advanced nuclear fuel cycle and fuel management. …”
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Gelation behavior and microstructure of ThxZr1-xO2 inert matrix fuel prepared by an external gelation process by HUANG He, WANG Peng, YAN Chao, YU Xiaohe, CAO Changqing, LIN Jun, ZHU Zhiyong

“…BackgroundInert matrix fuel (IMF) can efficiently convert plutonium and long-lived minor actinides used for preventing the proliferation of nuclear weapons and improving spent fuel disposal, hence has been becoming a hot research topic in recent years. …”
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Irradiated fuel salt data library for a molten salt reactor produced with Serpent2 and SOURCES 4C codes by Vaibhav Mishra, Zsolt Elter, Erik Branger, Sophie Grape, Sorouche Mirmiran

“…The dataset comprises isotopic mass densities of 1362 isotopes (including fission products and major and minor actinides) and their corresponding contributions to decay heat, gamma activity, and spontaneous fission rates computed by Serpent 2.1.32 as well as overall neutron emission rates from spontaneous fission and (ɑ, n) reactions computed by SOURCES 4C. …”
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Development and Validation of Burnup Library for PWR by WU Xiaofei;WU Haicheng;LIU Ping;GE Zhigang;WEN Lili;XIAO Yue

“…Fissionproduct yields data contain 60 datasets from 36 fissionable actinides. When yield data are not available for an isotope identified in the library as fissionable, 239Pu fast yield set is given for neutron induced fission and 252Cf spontaneous fission yield set is given for spontaneous fission. …”
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