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Journal articles on the topic 'CURIUM ISOTOPES'

Author: Grafiati

Published: 4 June 2021

Last updated: 1 February 2022

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1

Kurosaki, H., J. R. Cadieux, and S. B. Clark. "An alternative method for chronometric determinations involving curium." J. Anal. At. Spectrom. 29, no. 12 (2014): 2419–23. http://dx.doi.org/10.1039/c4ja00256c.

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A method for quantifying ratios of isotopes of plutonium (Pu), americium (Am), and curium (Cm) using inductively coupled plasma mass spectrometry (ICP-MS) is described that does not require radiochemical separations or a chemical yield monitor.

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2

Lee, M. H., J. H. Park, and K. Song. "Determination of plutonium, uranium and americium/curium isotopes in environmental samples with anion exchange, UTEVA, Sr and DGA resin." Proceedings in Radiochemistry 1, no. 1 (2011): 189–94. http://dx.doi.org/10.1524/rcpr.2011.0034.

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AbstractThis study presents a quantitative sequential radiochemical separation method for the Pu, U, Sr and Am/Cm isotopes with an anion exchange resin, UTEVA resin, Sr resin and DGA resin in environmental samples. After the radionuclides were leached from samples with 8 M HNO3, the Pu, U, Sr and Am/Cm isotopes were sequentially adsorbed on the anion exchange column, UTEVA column connected with Sr Spec column and DGA column. The Pu isotopes were purified from other nuclides through the anion exchange column, and the uranium isotopes were separated from other nuclides through the UTEVA column.

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3

Block, Robert C., Donald R. Harris, Harry T. Maguire, et al. "Intermediate structure in the fission cross sections of the even curium isotopes." Radiation Effects 92, no. 1-4 (1986): 305–9. http://dx.doi.org/10.1080/00337578608208340.

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4

OSAKA, Masahiko, Shin-ichi KOYAMA, Katsufumi MOROZUMI, Takashi NAMEKAWA, and Toshiaki MITSUGASHIRA. "Analysis of Curium Isotopes in Mixed Oxide Fuel Irradiated in Fast Reactor." Journal of Nuclear Science and Technology 38, no. 10 (2001): 912–14. http://dx.doi.org/10.1080/18811248.2001.9715116.

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5

Chechev, V. P., and V. V. Chechev. "Evaluation of the nuclear-physics characteristics and decay schemes of curium isotopes." Measurement Techniques 56, no. 6 (2013): 712–20. http://dx.doi.org/10.1007/s11018-013-0270-6.

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6

Habibi, Azza, Roselyne Le Corre, Christèle Wampach Aubert, et al. "Quantification of curium isotopes in environmental samples: drawbacks, speciation and specific tracer." Journal of Radioanalytical and Nuclear Chemistry 329, no. 2 (2021): 545–54. http://dx.doi.org/10.1007/s10967-021-07751-7.

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7

Gorietti, D., I. Giardina, D. Arginelli, and P. Battisti. "Determination of plutonium, americium and curium isotopes in radioactive metal wastes deriving from nuclear decommissioning." Journal of Radioanalytical and Nuclear Chemistry 314, no. 3 (2017): 1785–92. http://dx.doi.org/10.1007/s10967-017-5553-y.

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8

Lukyan, E. I., G. L. Khorasanov, and А. М. Terekhova. "Estimation of the Amounts of Curium and Americium Isotopes in SNF of the BN-600 Reactor." KnE Engineering 3, no. 3 (2018): 460. http://dx.doi.org/10.18502/keg.v3i3.1646.

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The neutron-physical characteristics of curium and americium in spent nuclear fuel (SNF) of the BN-600 reactor were considered in the work. With the help of the Serpent software complex, several models of the BN-600 reactor fuel assembly with different enrichment of fuel by U-235 were built. In BN-600, with the probability of dividing Am-241 by no more than 15%, incomplete burning of minor actinides (MA) occurs and even the accumulation of Cm-244, which is dangerous for storage.

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9

Nafee, S. S., S. A. Shaheen, and A. M. Al-Ramady. "Numerical approach for predicting the decay heat contribution of curium isotopes in the mixed oxide nuclear fuel." Nuclear Engineering and Design 262 (September 2013): 246–50. http://dx.doi.org/10.1016/j.nucengdes.2013.04.040.

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10

Lee, M. H., Y. S. Jeon, and K. Song. "Determination of activity concentrations and activity ratios of plutonium, americium and curium isotopes in radioactive waste samples." Journal of Radioanalytical and Nuclear Chemistry 280, no. 3 (2009): 457–65. http://dx.doi.org/10.1007/s10967-008-7442-x.

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11

Kaye, J. H., R. S. Strebin, and R. D. Orr. "Rapid, quantitative analysis of americium, curium and plutonium isotopes in Hanford samples using extraction chromatography and precipitation plating." Journal of Radioanalytical and Nuclear Chemistry Articles 194, no. 1 (1995): 191–96. http://dx.doi.org/10.1007/bf02037627.

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12

Fomushkin, Eduard, Gleb Novoselov, Vyacheslav Gavrilov, et al. "Investigations of Neutron Characteristics for Salt Blanket Models; Integral Fission Cross Section Measurements of Neptunium, Plutonium, Americium and Curium Isotopes." Journal of Nuclear Science and Technology 39, sup2 (2002): 1213–16. http://dx.doi.org/10.1080/00223131.2002.10875321.

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13

Tsinganis, A., A. Stamatopoulos, N. Colonna, et al. "Neutron induced fission cross-section of 240Pu(n,f): first results from n_TOF (CERN) Experimental Area II." HNPS Proceedings 23 (March 8, 2019): 22. http://dx.doi.org/10.12681/hnps.1902.

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The accurate knowledge of neutron cross-sections of a variety of plutonium isotopes and other minor actinides, such as neptunium, americium and curium, is crucial for feasibility and performance studies of advanced nuclear systems (Generation-IV reactors, Accelerator Driven Systems). In this context, the 240Pu(n,f) cross-section was measured with the time-of-flight technique at the CERN n_TOF facility at incident neutron energies ranging from thermal to several MeV. The present measurement is the first to have been performed at n_TOF's newly commissioned Experimental Area II (EAR-2), which is

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14

Stanisz, Przemysław, Jerzy Cetnar, and Mikołaj Oettingen. "Radionuclide neutron source trajectories in the closed nuclear fuel cycle." Nukleonika 64, no. 1 (2019): 3–9. http://dx.doi.org/10.2478/nuka-2019-0001.

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Abstract The highest efficiency in the usage of nuclear energy resources can be implemented in fast breeder reactors of generation IV. It is achieved thanks to the ability of consuming minor actinides (MAs) in energy production. One of the options to use this benefit is full recycling of MAs to close the nuclear fuel cycle. Monte Carlo burn up (MCB), an integrated burn-up calculation code, deals with the complexity of the burn-up process which is applied to the European Lead-cooled Fast Reactor (ELFR). MCB uses continuous energy representation of cross section and spatial effects of full core

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15

Dai, Xiongxin, Marcus Christl, Sheila Kramer-Tremblay, and Hans-Arno Synal. "Determination of Atto- to Femtogram Levels of Americium and Curium Isotopes in Large-Volume Urine Samples by Compact Accelerator Mass Spectrometry." Analytical Chemistry 88, no. 5 (2016): 2832–37. http://dx.doi.org/10.1021/acs.analchem.5b04546.

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16

Alberts, J. J., J. E. Halverson, and K. A. Orlandini. "The distribution of plutonium, Americium and curium isotopes in pond and stream sediments of the Savannah river plant, South Carolina, USA." Journal of Environmental Radioactivity 3, no. 4 (1986): 249–71. http://dx.doi.org/10.1016/0265-931x(86)90002-0.

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17

Kurosaki, Hiromu, Daniel I. Kaplan, and Sue B. Clark. "Impact of Environmental Curium on Plutonium Migration and Isotopic Signatures." Environmental Science & Technology 48, no. 23 (2014): 13985–91. http://dx.doi.org/10.1021/es500968n.

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18

Shiokawa, Y., K. Suzuki, S. Suzuki, and M. Yagi. "Determination of isotopic ratios of plutonium and curium by internal conversion electron spectrometry." Journal of Radioanalytical and Nuclear Chemistry Articles 143, no. 1 (1990): 135–41. http://dx.doi.org/10.1007/bf02117555.

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19

Wahyono, Puradwi Ismu, and Syarip . "Analisis Produksi 99Mo Berbasis Waktu Iradiasi Larutan Uranil Nitrat Pada Fasilitas Reaktor Kartini." Risalah Fisika 4, no. 1 (2020): 15–18. http://dx.doi.org/10.35895/rf.v4i1.172.

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Abstrak – Selama ini produksi isotop 99Mo sebagai generator 99mTc untuk diagnosis nuklir dalam bidang kedokteran adalah berbasis metode iradiasi 6-days curie. Pada makalah ini disajikan suatu analisis produksi 99Mo berbasis waktu iradiasi target berupa uranil-nitrat (UN), tanpa harus menunggu 6 hari waktu iradiasi. Metode yang digunakan adalah perhitungan pembentukan radioisotop produk fisi dengan bantuan paket program komputer ORIGEN-2. Perhitungan dilakukan untuk sampel ukuran standar volume 0,395 liter dengan variasi waktu iradiasi dan fluks neutron sesuai dengan fleksibilitas operasi reakt

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20

Gourgiotis, A., H. Isnard, M. Aubert, et al. "Accurate determination of Curium and Californium isotopic ratios by inductively coupled plasma quadrupole mass spectrometry (ICP-QMS) in 248Cm samples for transmutation studies." International Journal of Mass Spectrometry 291, no. 3 (2010): 101–7. http://dx.doi.org/10.1016/j.ijms.2010.02.002.

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21

Svasek, J. N., and H. Engel. "USE OF A RADIO-ACTIVE TRACER FOR THE MEASUREMENT OF SEDIMENT TRANSPORT IN THE NETHERLANDS." Coastal Engineering Proceedings 1, no. 7 (2011): 25. http://dx.doi.org/10.9753/icce.v7.25.

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The "Rijkswaterstaat" has developed a method based on the use of radio-active tracers for the evaluation of sediment transport due to the combined action of waves and currents. The results of preparatory studies and a laboratory test were published in a previous report by J.J. Arlman, P. Santema and J.N. Svasek [1]. The main principles of the method were 1. Detection by a sledge-mounted unit towed by a survey vessel and continuous registration on board of the radio-activity measured on the sea bottom. 2. Employment of low specific radio-activity of tracer material and a large quantity thereof.

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22

Cooper, Ronald. "The History and Development of Radiation Chemistry." Australian Journal of Chemistry 64, no. 7 (2011): 864. http://dx.doi.org/10.1071/ch11142.

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Stemming from the discovery and isolation of radioactive elements by the Curies came observations of chemical and physical changes produced by ‘emanations’. From ~1900 AD, observations were sporadic and spread across a range of chemical systems. Several conflicting results from irradiated water were reported – one recording no decomposition, whereas another study observed hydrogen and hydrogen peroxide formation. The field progressed slowly while the only practical source of radiation was X-rays. After the mid-1940s, the isotope output from nuclear reactors gave chemists high-activity radiatio

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23

Machi, Sueo. "Trends for Electron Beam Accelerator Applications in Industry." Reviews of Accelerator Science and Technology 04, no. 01 (2011): 1–10. http://dx.doi.org/10.1142/s1793626811000562.

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Electron beam (EB) accelerators are major pieces of industrial equipment used for many commercial radiation processing applications. The industrial use of EB accelerators has a history of more than 50 years and is still growing in terms of both its economic scale and new applications. Major applications involve the modification of polymeric materials to create value-added products, such as heat-resistant wires, heat-shrinkable sheets, automobile tires, foamed plastics, battery separators and hydrogel wound dressing. The surface curing of coatings and printing inks is a growing application for

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24

Gϋemes, Maria, Sofia Asim Rahman, Ritika R. Kapoor, et al. "Hyperinsulinemic hypoglycemia in children and adolescents: Recent advances in understanding of pathophysiology and management." Reviews in Endocrine and Metabolic Disorders 21, no. 4 (2020): 577–97. http://dx.doi.org/10.1007/s11154-020-09548-7.

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Abstract Hyperinsulinemic hypoglycemia (HH) is characterized by unregulated insulin release, leading to persistently low blood glucose concentrations with lack of alternative fuels, which increases the risk of neurological damage in these patients. It is the most common cause of persistent and recurrent hypoglycemia in the neonatal period. HH may be primary, Congenital HH (CHH), when it is associated with variants in a number of genes implicated in pancreatic development and function. Alterations in fifteen genes have been recognized to date, being some of the most recently identified mutation

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25

Yamamoto, M., J. Kuwabara, and D. J. Assinder. "Curium Isotopes and Americium-242m in Irish Sea Sediment." Radiochimica Acta 83, no. 3 (1998). http://dx.doi.org/10.1524/ract.1998.83.3.121.

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26

Rudisill, T. S., J. M. Pareizs, and W. G. Ramsey. "Americium/Curium Extraction from a Lanthanide Borosilicate Glass." MRS Proceedings 465 (1996). http://dx.doi.org/10.1557/proc-465-111.

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ABSTRACTA solution containing kilogram quantities of highly radioactive isotopes of amerícium and curium (Am/Cm) and lanthanide fission products is currently stored in a process tank at the Department of Energy's Savannah River Site (SRS). This tank and its vital support systems are old, subject to deterioration, and prone to possible leakage. For this reason, a program has been initiated to stabilize this material as a lanthanide borosilicate (LBS) glass.1 The Am/Cm has commercial value and is desired for use by the heavy isotope programs at the Oak Ridge National Laboratory (ORNL).A recovery

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27

Rudisill, Tracy S., David K. Peeler, and Thomas B. Edwards. "Demonstration of the Feasibility of Recovering Americium and Curium Isotopes from a Lanthanide Borosilicate Glass." MRS Proceedings 713 (2002). http://dx.doi.org/10.1557/proc-713-jj11.69.

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ABSTRACTA solution containing kilogram quantities of highly radioactive isotopes of americium and curium (Am/Cm) is currently stored in a process tank at the Department of Energy's Savannah River Site. This tank and its vital support systems are old, subject to deterioration, and prone to possible leakage. To address the stabilization of this material, vitrification of the isotopes has been considered. Potentially, the glass could be shipped to the isotope production and distribution programs at the Oak Ridge National Laboratory for californium-252 production and use by the transplutonium rese

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28

Kawase, Shoichiro, Atsushi Kimura, Hideo Harada, et al. "Neutron capture cross sections of curium isotopes measured with ANNRI at J-PARC." Journal of Nuclear Science and Technology, January 4, 2021, 1–23. http://dx.doi.org/10.1080/00223131.2020.1864492.

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29

Peuget, Sylvain, Christophe Jégou, Véronique Broudic, Danièle Roudil, Xavier Deschanels, and Jean-Michel Bart. "Effect of Alpha Decay on Nuclear Borosilicate Glass Properties." MRS Proceedings 824 (2004). http://dx.doi.org/10.1557/proc-824-cc5.5.

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AbstractThe properties of actinide glasses are studied in the context of high-level waste management programs. Reprocessing high burnup fuels in particular will increase the minor actinide content in the glass package, resulting in higher cumulative alpha decay doses in the glass, and raising the question of the glass matrix behavior and especially its containment properties. The effect of alpha self-irradiation on the glass behavior is evaluated by doping the glass with a short-lived actinide (244Cm) to reach in several years the alpha dose received by the future glass packages over several t

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30

Webster, Jeffrey A., Alexander Hagen, Brian C. Archambault, Nicholas Hume, and Rusi Taleyarkhan. "High-Efficiency Gamma-Beta Blind Alpha Spectrometry for Nuclear Energy Applications." Journal of Nuclear Engineering and Radiation Science 1, no. 3 (2015). http://dx.doi.org/10.1115/1.4029926.

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A novel, centrifugally tensioned metastable fluid detector (CTMFD) sensor technology has been developed over the last decade to demonstrate high selective sensitivity and detection efficiency to various forms of radiation for wide-ranging conditions (e.g., power, safeguards, security, and health physics) relevant to the nuclear energy industry. The CTMFD operates by tensioning a liquid with centrifugal force to weaken the bonds in the liquid to the point whereby even femtoscale nuclear particle interactions can break the fluid and cause a detectable vaporization cascade. The operating principl

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31

Huntley, M. W. "Sequential separation of americium, curium, plutonium, neptunium and uranium in various matrices from the electrometallurgic treatment of spent-nuclear fuel." Radiochimica Acta 89, no. 10 (2001). http://dx.doi.org/10.1524/ract.2001.89.10.605.

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The separation of americium-241, curium-242/244, plutonium-238/239, neptunium-237, and uranium-234/235/238, in the same sample aliquot of clear acidic solution resulting from the electrometallurgical treatment of spent nuclear fuel has been investigated. Using ion exchange techniques in 10 M HCl media, it was determined that good separation can be achieved to resolve each isotope via alpha spectroscopy. The resin used was AG 1-x8 chloride form supplied by BioRad® Laboratories. The retention and eluting conditions for each isotope were determined using tracer techniques and will be presented. B

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32

Advocat, T., F. Jorion, T. Marcillat, et al. "Fabrication of 239/238Pu-Zirconolite Ceramic Pellets by Natural Sintering." MRS Proceedings 807 (2003). http://dx.doi.org/10.1557/proc-807-267.

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ABSTRACTZirconolite is a potential inorganic matrix that is currently investigated in France, in the framework of the 1991 radioactive waste management law, with a view to provide durable containment of the trivalent and tetravalent minor actinides like neptunium, curium, americium and small quantities of unrecyclable plutonium separated from other nuclear waste. To confirm the actinide loading capacity of the zirconolite calcium site and to study the physical and chemical stability of this type of ceramic when subjected to alpha self-irradiation, zirconolite ceramic pellets were fabricated wi

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33

Munir, Syed, Dania Abu-Jubara, Musa Abu-Jubara, Carla Antypas, and Cameron Petro-Sakuma. "A New Skin Manifestation at the Site of a Previously Healed Dermatosis: A Case of Wolf’s Isotopic Response." Cureus, November 8, 2020. http://dx.doi.org/10.7759/cureus.11381.

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