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Auteur : Grafiati

Publié le 4 mai 2024

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1

Boulyga, Sergei F., Andreas Koepf, Stefanie Konegger-Kappel, Zsuzsanna Macsik et Guillaume Stadelmann. « Uranium isotope analysis by MC-ICP-MS in sub-ng sized samples ». Journal of Analytical Atomic Spectrometry 31, n^o 11 (2016) : 2272–84. http://dx.doi.org/10.1039/c6ja00238b.

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This study describes the multi-collector inductively coupled plasma mass spectrometry (MC-ICP-MS) method for the determination of n(²³³U)/n(²³⁸U), n(²³⁴U)/n(²³⁸U), n(²³⁵U)/n(²³⁸U), and n(²³⁶U)/n(²³⁸U) isotope ratios in purified uranium solutions.

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Varga, Z., M. Krachler, A. Nicholl, M. Ernstberger, T. Wiss, M. Wallenius et K. Mayer. « Accurate measurement of uranium isotope ratios in solid samples by laser ablation multi-collector inductively coupled plasma mass spectrometry ». Journal of Analytical Atomic Spectrometry 33, n^o 6 (2018) : 1076–80. http://dx.doi.org/10.1039/c8ja00006a.

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A multi-collector inductively coupled plasma mass spectrometer (MC-ICP-MS) coupled to a 213 nm ns-laser was used to measure uranium isotope ratios (²³⁴U/²³⁸U, ²³⁵U/²³⁸U, and ²³⁶U/²³⁸U) in six solid nuclear certified reference materials (CRMs).

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Arnason, John G., Christine N. Pellegri et Patrick J. Parsons. « Determination of total uranium and uranium isotope ratios in human urine by ICP-MS:results of an interlaboratory study ». Journal of Analytical Atomic Spectrometry 30, n^o 1 (2015) : 126–38. http://dx.doi.org/10.1039/c4ja00235k.

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Interlaboratory performance is reported for nine participants analyzing six well-characterized urine reference materials supplemented with ²³⁴U, ²³⁵U, ²³⁶U, and ²³⁸U.

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Sudarmono, E. P. Hastuti, A. Rohanda, A. S. Ekariansyah, Y. Kasesaz et Suwoto. « Study Analysis of Multiplication Factor on ADS Transmutation System ». Journal of Physics : Conference Series 2328, n^o 1 (1 août 2022) : 012008. http://dx.doi.org/10.1088/1742-6596/2328/1/012008.

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Abstract New research technology for partition and transmutation (P-T) of minor actinide (MA) contained in high-level waste (HLW) has been carried out to design accelerator-based transmutation system or commonly known as Accelerator Driven Subcritical (ADS) device. The objective of this system is to eliminate or minimize high-level radioactive waste that has long half-life and to develop long-term safety assurance in HLW management. Analysis done by using Origen2.1 and mCnP6 codes. As matrix, Th-232 with optimum weight 75% is used.. Comparing with , analysis results using MCNP shows that the use of PWR nuclear spent fuel for ADS device can be done by reprocessing to eliminate U-238 nuclide, which is the source of the formation of plutonium nuclide and minor actinides. From the results and discussion, it can be concluded that observation on transmutation of transuranic nuclides using ORIGEN2.1 Code on ADS device has been conducted successfully with LMFBR library. 15%-Th232 fuel has been justified as the most optimum ADS fuel based on K-inf reached at EOC on various fuel types. Mass reduction occurs at EOC for U-236, U-235, U-234, Th-232, Np-237, Pu-238, Am-241, Pu-242, and Cm 244. Radionuclides that experience mass changes during cooling time are Pu-238, Pu-240, Am-241, Pa-233, and Cm-244.

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Oettingen, Mikołaj, et Jerzy Cetnar. « Comparative analysis between measured and calculated concentrations of major actinides using destructive assay data from Ohi-2 PWR ». Nukleonika 60, n^o 3 (1 septembre 2015) : 571–80. http://dx.doi.org/10.1515/nuka-2015-0102.

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Abstract In the paper, we assess the accuracy of the Monte Carlo continuous energy burnup code (MCB) in predicting final concentrations of major actinides in the spent nuclear fuel from commercial PWR. The Ohi-2 PWR irradiation experiment was chosen for the numerical reconstruction due to the availability of the final concentrations for eleven major actinides including five uranium isotopes (U-232, U-234, U-235, U-236, U-238) and six plutonium isotopes (Pu-236, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242). The main results were presented as a calculated-to-experimental ratio (C/E) for measured and calculated final actinide concentrations. The good agreement in the range of ±5% was obtained for 78% C/E factors (43 out of 55). The MCB modeling shows significant improvement compared with the results of previous studies conducted on the Ohi-2 experiment, which proves the reliability and accuracy of the developed methodology.

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Воробьев, А. С., А. М. Гагарский, О. А. Щербаков, Л. А. Вайшнене, А. Л. Барабанов et Т. Е. Кузьмина. « Анизотропия угловых распределений осколков деления 232 Th, 233 U, 235 U, 238 U, 239 Pu, 237 Np, Pb и 209 Bi нейтронами промежуточных энергий 1–200 МэВ ». Известия Российской академии наук. Серия физическая 84, n^o 10 (2020) : 1451–57. http://dx.doi.org/10.31857/s0367676520100294.

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Andersen, M. B., D. Vance, J. L. Morford, E. Bura-Nakić, S. F. M. Breitenbach et L. Och. « Closing in on the marine 238 U/ 235 U budget ». Chemical Geology 420 (janvier 2016) : 11–22. http://dx.doi.org/10.1016/j.chemgeo.2015.10.041.

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Susdarwono, Endro Tri. « Reaksi Fisi dan Reaksi Fusi dalam Mekanisme Bom Atom dan Senjata Termonuklir ». VEKTOR : Jurnal Pendidikan IPA 2, n^o 1 (28 mai 2021) : 16–30. http://dx.doi.org/10.35719/vektor.v2i1.19.

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Tujuan penelitian ini membahas mengenai reaksi fisi dan fusi pada bom atom dan senjata termonuklir. Penelitian ini adalah penelitian kualitatif, jenis penelitiannya menggunakan studi analitik komprehensif. Bagian paling vital dari ledakan fisi yang terjadi dalam bom atom tak lain adalah material yang berfisi itu sendiri. Ada dua unsur radioaktif yang biasa dipakai, yakni uranium dan plutonium, masing-masing dengan aneka isotopnya. Mulai dari U-232, U-234, U-235, dan U-238 untuk uranium, hingga Pu-238, Pu-239, dan Pu240 untuk plutonium. Elemen pemicu ledak yang dipakai dalam ledakan termonuklir ialah deuterium (D) alias hydrogen berat atau yang juga popular dengan sebutan ‘air berat’ (heavy water). Dari setiap 5000 atom hydrogen, bisa dipastikan satu isotop di antaranya dalam bentuk deuterium. Inti deuterium (deutron) terdiri dari satu proton (p) dan satu neutron (n). saat berpasangan, dua deutron membentuk inti atom helium (He-4) yang relatif stabil. Dalam semua jenis reaksi ini, inti atom berat terbentuk melalui proses fusi. Kata Kunci: bom atom, reaksi fisi, reaksi fusi, senjata termonuklir The purpose of this research is to discuss fission and fusion reactions in atomic bombs and thermonuclear weapons. This research is a qualitative research. This type of research uses a comprehensive analytical study. The most vital part of the fission explosion that occurs in an atomic bomb is none other than the fission material itself. There are two radioactive elements in common use, uranium and plutonium, each with its different isotopes. They range from U-232, U-234, U-235, and U-238 for uranium, to Pu-238, Pu-239, and Pu240 for plutonium. The explosive trigger element used in thermonuclear explosions is deuterium (D) heavy hydrogen or also popularly known as "heavy water" (heavy water). For every 5000 hydrogen atoms, one can be sure of one of them in the form of deuterium. The nucleus of heuterium (deutron) consists of one proton (p) and one neutron (n). When paired, the two deutrons form a relatively stable nucleus of helium (He-4). In all of these types of reactions, heavy atomic nuclei are formed by fusion. Keywords: atomic bombs, fission reactions, fusion reactions, thermonuclear weapons

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Seifritz, W. « Some comments on Herndon’s nuclear georeactor ». Kerntechnik 68, n^o 4 (1 août 2003) : 193–96. http://dx.doi.org/10.1515/kern-2003-0079.

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Abstract Light was thrown on the nuclear aspects of Herndon’s georeactor. His thesis is that a power producing droplet of liquid uranium, possessing a radius of about 5 km, operated during the last 4.5 billions of years in the center of the Earth and producing 3–6 TW of thermal power. It could be shown that indeed initial criticality was possible due to the high U-235/U-238 enrichment of approximately 30% at that time. Furthermore, the U-238/Pu-239/U-235 conversion cycle guarantees also a stabilized U-235/U-238 enrichment of about 10% during the whole history of Earth. For this, a constant critical neutron flux in the realm of 108 n/(cm2s) has to be present to convert U-238 via the Pu-239 route and its eddecay into U-235 with a conversion ratio of exactly unity. Herndon’s georeactor is compared with other exotic fission reactors in Nature, too, but the decisive answer whether such a georeactor really exists needs further – particularly chemical, thermodynamical and geological – research work.

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Голубев, В. Н., Н. Н. Тарасов, И. В. Чернышев, А. В. Чугаев, Г. В. Очирова et Б. Т. Кочкин. « Пострудные процессы миграции урана в месторождениях “песчаникового” типа : 234 U/ 238 U, 238 U/ 235 U и U–Pb-изотопная систематика руд месторождения Намару, Витимский район, Северное Забайкалье ». Геология рудных месторождений 63, n^o 4 (2021) : 297–310. http://dx.doi.org/10.31857/s001677702104002x.

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Pop, O. M., M. V. Stets, V. T. Maslyuk, B. V. Matskiv, R. V. Khomutnyk et P. S. Penyak. « Nuclear chronometry of standard sets of nuclides of the 232-Th, 235-U, 238-U series ». Nuclear Physics and Atomic Energy 17, n^o 3 (25 septembre 2016) : 232–39. http://dx.doi.org/10.15407/jnpae2016.03.232.

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Fort, E., V. Zammit-Averlant, M. Salvatores, A. Filip et J.-F. Lebrat. « Recommended values of the delayed neutron yield for : U-235 ; U-238 and Pu-239 ». Progress in Nuclear Energy 41, n^o 1-4 (juillet 2002) : 317–59. http://dx.doi.org/10.1016/s0149-1970(02)00017-3.

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Kochetkov, Anatoly, Antonín Krása, Luc Borms, Edouard Malambu, Guido Vittiglio, Jan Wagemans et Jeroen Willems. « Calibration of CFUL01 fission chambers in the standard neutron fields of the BR1 reactor at SCK CEN ». EPJ Web of Conferences 253 (2021) : 04025. http://dx.doi.org/10.1051/epjconf/202125304025.

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Recent subcritical VENUS-F experiments showed that fission chambers with a threshold deposit like U-238 can essentially improve the on-line sub-criticality measurments with the beam interruption method, which is currently supposed to be the main method for the ADS MYRRHA. To suppress the uncertainty caused by fissions in the U-235 impurities, the fraction of U-235 in the U deposit should be accurately known. Three PHOTONIS CFUL01 type fission chambers with U-238 deposit were purchased for sub-critical experiments in the VENUS-F reactor. To verify the purity of their deposits, the effective U-235 masses were measured in the empty cavity of the BR1 reactor with a well-known thermal neutron spectrum. It turned out that the measured effective U-235 mass in two fission chambers is lower than the declared mass (as it should be), but this is not the case for the third fission chamber. Then, the effective U-238 mass in these FCs was measured in the well-known fast spectrum of the MARK-III convertor in the BR1 reactor. Finally, the isotopic composition was obtained and it was found that the purity of two CFUL01 FCs is in agreement with the values declared in the certificates but it is not the case for the third fission chamber. As the length of the deposit is bigger than the length of the MARK-III convertor, necessary corrections were calculated with MCNP. The developed procedure using the BR1 standard irradiation fields can be applied for calibration and impurity determination of large fission chambers.

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Tissot, François L. H., Mauricio Ibanez-Mejia, Patrick Boehnke, Nicolas Dauphas, David McGee, Timothy L. Grove et T. Mark Harrison. « 238U/235U measurement in single-zircon crystals : implications for the Hadean environment, magmatic differentiation and geochronology ». Journal of Analytical Atomic Spectrometry 34, n^o 10 (2019) : 2035–52. http://dx.doi.org/10.1039/c9ja00205g.

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15

Capote, R., A. Trkov, M. Sin, M. T. Pigni, V. G. Pronyaev, J. Balibrea, D. Bernard et al. « IAEA CIELO Evaluation of Neutron-induced Reactions on 235 U and 238 U Targets ». Nuclear Data Sheets 148 (février 2018) : 254–92. http://dx.doi.org/10.1016/j.nds.2018.02.005.

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16

Pelloni, Sandro, et Dimitri Rochman. « Testing JENDL-5 data for U-235, Pu-239 and U-238 above the resolved resonance region ». Annals of Nuclear Energy 182 (mars 2023) : 109603. http://dx.doi.org/10.1016/j.anucene.2022.109603.

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Guirguis, Laila A., Nagdy M. Farag et Adham K. Salim. « Accurate fast method with high chemical yield for determination of uranium isotopes ( 234 U, 235 U, 238 U) in granitic samples using alpha spectroscopy ». Nuclear Instruments and Methods in Physics Research Section A : Accelerators, Spectrometers, Detectors and Associated Equipment 777 (mars 2015) : 211–17. http://dx.doi.org/10.1016/j.nima.2015.01.016.

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Krachler, M., A. Bulgheroni, A. I. Martinez Ferri, Y. Ma, A. Miard et Ph Garcia. « Single shot laser ablation MC-ICP-MS for depth profile analysis of U isotopes in UO2 single crystals ». Journal of Analytical Atomic Spectrometry 34, n^o 10 (2019) : 1965–74. http://dx.doi.org/10.1039/c9ja00212j.

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Depth profiling of the n(²³⁵U)/n(²³⁸U) amount ratio in UO₂ single crystals employing LA-MC-ICP-MS, a dual beam focused ion beam and confocal laser scanning profilometry.

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TAKEDA, Seiji, et Hideo KIMURA. « Clearance Levels for U-234, U-235 and U-238 Derived on the Basis of Dose Calculation Approach in IAEA Safety Reports Series No.44 ». Japanese Journal of Health Physics 45, n^o 4 (2010) : 342–56. http://dx.doi.org/10.5453/jhps.45.342.

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Al-Alawy, Iman Tarik, et Ronak Ikram Ali. « Optical Model Potential Using CINDA Library for Neutron Induced Cross Section Reactions for Spherical Uranium-235,238 Isotopes ». International Letters of Chemistry, Physics and Astronomy 60 (septembre 2015) : 66–73. http://dx.doi.org/10.18052/www.scipress.com/ilcpa.60.66.

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The calculation are based mainly on the nuclear optical model potential and relevant parameters are collected and selected from References Input Parameter Library (RIPL) which is being developed under the international project coordinated by the International Atomic Energy Agency (IAEA). The analyzing of a complete energy range has done starting from threshold energy for each reaction. The cross sections are reproduced in fine steps of incident neutron energy with 0.01MeV intervals with their corresponding errors. The recommended cross sections for available experimental data taken from CINDA library have been calculated for all the considered neutron induced reactions for spherical U-235 and U-238 isotopes. The calculated results are analyzed and compared with the experimental data. The optimized optical potential model parameters give a very good agreement with the experimental data over the energy range 0.001-20MeV for neutron induced cross section reactions (n,f), (n,tot), (n,el), (n,inl), (n,2n), (n,3n), and (n,γ) for spherical U-235 and U-238 target elements.

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Al-Alawy, Iman Tarik, et Ronak Ikram Ali. « Optical Model Potential Using CINDA Library for Neutron Induced Cross Section Reactions for Spherical Uranium-235,238 Isotopes ». International Letters of Chemistry, Physics and Astronomy 60 (30 septembre 2015) : 66–73. http://dx.doi.org/10.56431/p-do685h.

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The calculation are based mainly on the nuclear optical model potential and relevant parameters are collected and selected from References Input Parameter Library (RIPL) which is being developed under the international project coordinated by the International Atomic Energy Agency (IAEA). The analyzing of a complete energy range has done starting from threshold energy for each reaction. The cross sections are reproduced in fine steps of incident neutron energy with 0.01MeV intervals with their corresponding errors. The recommended cross sections for available experimental data taken from CINDA library have been calculated for all the considered neutron induced reactions for spherical U-235 and U-238 isotopes. The calculated results are analyzed and compared with the experimental data. The optimized optical potential model parameters give a very good agreement with the experimental data over the energy range 0.001-20MeV for neutron induced cross section reactions (n,f), (n,tot), (n,el), (n,inl), (n,2n), (n,3n), and (n,γ) for spherical U-235 and U-238 target elements.

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Yunanda, Winka Wino, et Mohammad Ali Shafii. « Analisis Koefisien Difusi Neutron terhadap Jarak Ekstrapolasi dalam Persamaan Difusi Multigrup Satu Dimensi ». Jurnal Fisika Unand 8, n^o 4 (26 novembre 2019) : 362–67. http://dx.doi.org/10.25077/jfu.8.4.362-367.2019.

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Telah dilakukan analisis koefisien difusi neutron terhadap jarak ekstrapolasi dalam persamaan difusi multigrup satu dimensi. Penelitian ini bertujuan untuk menentukan distribusi fluks neutron yang selanjutnya digunakan sebagai nilai masukan untuk menghitung koefisien difusi neutron sebagai fungsi 70 grup energi. Jenis reaktor yang digunakan dalam penelitian ini adalah reaktor cepat dengan teras berbentuk slab dan bahan bakar yang digunakan adalah U-PuN. Pada penelitian ini dilakukan perhitungan distribusi fluks neutron dan koefisien difusi neutron untuk 20 grup energi yaitu hanya pada grup energi tinggi saja. Hasil penelitian menunjukkan bahwa nilai koefisien difusi pada 20 grup terhadap jarak ekstrapolasi pada grup energi cepat untuk bahan bakar U-235 dan Pu-239 diperoleh nilai yang hampir sama yaitu antara 1x10-4cm sampai 5x10-4 cm hal ini terjadi karena U-235 dan Pu-239 merupakan bahan fisil, sedangkan nilai koefisien difusi neutron pada U-238 jauh lebih kecil yaitu antara 5x10-5cm sampai 25x10-5 cm, perbedaan nilai ini terjadi karena U-238 merupakan bahan fertil.Kata kunci: distribusi fluks neutron, grup energi, jarak ekstrapolasi, koefisien difusi neutron

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Wen, Jie, Yiwei Yang, Zhongwei Wen, Rong Liu, Xingyan Liu, Zijie Han, Qiping Chen et al. « Measurement of the U-238/U-235 fission cross section ratio at CSNS – Back-n WNS ». Annals of Nuclear Energy 140 (juin 2020) : 107301. http://dx.doi.org/10.1016/j.anucene.2019.107301.

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Zakyia, Imra, et Mohammad Ali Shafii. « Analisis Distribusi Fluks Neutron pada Reaktor Berbentuk Slab Menggunakan Persamaan Difusi Multigrup Satu Dimensi dengan Metode Gauss-Seidel ». Jurnal Fisika Unand 9, n^o 3 (14 août 2020) : 388–93. http://dx.doi.org/10.25077/jfu.9.3.388-393.2020.

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Telah dilakukan penelitian mengenai distribusi fluks neutron dalam persamaan difusi neutron multigrup satu dimensi. Jenis reaktor yang digunakan adalah reaktor cepat dengan teras berbentuk slab dan bahan bakar yang digunakan yaitu U-PuN. Penelitian ini menggunakan penampang lintang makroskopik di level sel bahan bakar sebagai masukan awal untuk 70 grup energi. Data library yang digunakan adalah JFS-3-J33 70 grup energi neutron yang merupakan data dari kode komputer SLAROM dari JAEA Jepang. Rentang energi dibagi ke dalam tiga daerah grup energi yaitu grup energi cepat, grup energi menengah dan grup energi termal. Metode iterasi yang digunakan dalam penelitian ini adalah metode iterasi Gauss-Seidel. Hasil penelitian menunjukkan bahwa distribusi fluks neutron pada grup energi cepat untuk bahan bakar U-235 dan Pu-239 berkisar antara 32,96 n/s cm2 sampai 121,95 n/s cm2, sedangkan pada grup energi menengah terjadi tumpang tindih antar grup energi dan pada grup energi termal distribusi fluks neutron untuk U-238 lebih rendah dibandingkan dengan U-235 dan Pu-239. Perbedaan nilai ini terjadi karena U-238 merupakan bahan fertil. Distribusi fluks neutron pada grup energi cepat memiliki nilai lebih akurat dibandingkan dengan grup energi menengah dan termalkarena penelitian ini didesain untuk reaktor cepat. Research on the distribution of the neutron flux in the one-dimensional multigroup neutron diffusion equation has been done. The type of reactor used is a fast reactor with a slab-shaped reactor core, and the fuel used is U-PuN. The study used macroscopic cross-sections at the fuel cell level as initial input for 70 neutron energy groups. The data library used is JFS-3-J33 70 energy groups, the library data of SLAROM computer codes from JAEA Japan. The energy range is divided into three regions of neutron energy groups, namely fast, medium, and thermal energy groups. The iteration method used in this study is the Gauss-Seidel iteration method. The results showed that the flux distribution in the fast energy group for U-235 and Pu-239 fuels ranged from 32.96 n/s cm2 to 121.95 n/s cm2, whereas in the intermediate neutron energy group overlaps each other and in the thermal energy group the U-238 neutron flux distribution is lower than U-235 and Pu-239. This difference in value occurs because U-238 is fertile material. The distribution of neutron flux in the fast energy group has a more accurate value compared to the medium and thermal energy groups because this study is designed for fast reactors.

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Ni, Youyi, Wenting Bu, Xiaotong Ding, Ke Xiong, Hailong Wang, Chuting Yang, Sheng Hu et Wu Men. « Automated method for concurrent determination of thorium (²³⁰Th, ²³²Th) and uranium (²³⁴U, ²³⁵U, ²³⁸U) isotopes in water matrices with ICP-MS/MS ». Journal of Analytical Atomic Spectrometry 37, n^o 4 (2022) : 919–28. http://dx.doi.org/10.1039/d1ja00450f.

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Jassby, D. L., H. W. Hendel et H. ‐S Bosch. « Relative intensities of 2.5‐ and 14‐MeV source neutrons from comparative responses of U‐238 and U‐235 detectors ». Review of Scientific Instruments 59, n^o 8 (août 1988) : 1688–90. http://dx.doi.org/10.1063/1.1140134.

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Поп, О. М. « Time dependence of interferences of analytical lines of radioactive ²³²Th, ²³⁵U та ²³⁸U series ». Scientific Herald of Uzhhorod University.Series Physics 32 (31 décembre 2012) : 45–50. http://dx.doi.org/10.24144/2415-8038.2012.32.45-50.

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Liu, Xiaobo. « REVIEW ON THE NEUTRON SOURCE STRENGTH OF HEU METAL BURST REACTOR ». EPJ Web of Conferences 247 (2021) : 07004. http://dx.doi.org/10.1051/epjconf/202124707004.

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There were two similar series of burst waiting time experiments carried out on Godiva-II and Caliban respectively and analyzed for neutron initiation study, unfortunately both the strength of spontaneous fission neutron source given in the published papers are not consistent with the spontaneous fission data of U-235 and U-238. In this paper, the discrepancies of spontaneous fission data of U-235 and U-238 from different references are reviewed and clarified and the correct strength of spontaneous fission neutron source for Godiva-II and Caliban are calculated respectively, then the multiplication equivalence method of arbitrary source is introduced and the equivalent fundamental-mode(EFM) co-efficiencies of spontaneous fission neutron source for Godiva-II and Caliban are calculated with MC software, lastly the strength of neutron source for these two HEU metal burst reactor in EFM are deduced. The EFM neutron strength of this two burst reactors are much less than proposed values used for burst waiting investigation in published papers respectively, and with the new data, the inconsistency of burst waiting time to the published results is presented and discussed.

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Shafii, Mohammad Ali, Jakaria Usman, Seni H. J. Tongkukut et Ade Gafar Abdullah. « The Pij matrix and flux calculation of one-dimensional neutron transport in the slab geometry of nuclear fuel cell using collision probability method ». MATEC Web of Conferences 197 (2018) : 02006. http://dx.doi.org/10.1051/matecconf/201819702006.

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Calculation of Pij matrix of one-dimensional neutron transport in the slab geometry of the nuclear fuel cell using Collision Probability (CP) method has been done. Pij matrix is one of important parameters within the distribution of neutron flux in the nuclear fuel cell. The CP method is the most efficient methods to solve the neutron transport equation in the reactor core. The study is focused on neutron interaction with nuclear fuel cell of U-235 and U-238 for homogeneous condition. The parameters to calculate the Pij matrix are the cross section of nuclear fuel, width of the region and number of regions. A lattice of slabs have been constructed using void boundary conditions for model of finite system to calculate the collision probabilities. If the Pij matrix has been calculated then neutron flux can be determined. The results show that total value of Pij matrix using CP method for U-235 and U-238 is less than one, respectively. This is in accordance with the definition of void boundary conditions for finite slab geometry. Along with Pij matrix, neutron flux is also appropriate with the reference.

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Carrel, Frédérick, Mathieu Agelou, Mehdi Gmar, Frédéric Laine, Joël Loridon, Jean-Luc Ma, Christian Passard et Bénédicte Poumarede. « New Experimental Results on the Cumulative Yields From Thermal Fission of $^{235} {\rm U}$ and $^{239}{\rm Pu}$ and From Photofission of $^{235} {\rm U}$ and $^{238} {\rm U}$ Induced by Bremsstrahlung ». IEEE Transactions on Nuclear Science 58, n^o 4 (août 2011) : 2064–72. http://dx.doi.org/10.1109/tns.2011.2157169.

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Skierszkan, Elliott K., John W. Dockrey, Jordi Helsen, Laura-Lee Findlater, Clément P. Bataille, Ghislain de Laplante, Joyce M. McBeth, K. Ulrich Mayer et Roger D. Beckie. « Persistence of Uranium in Old and Cold Subpermafrost Groundwater Indicated by Linking ²³⁴U-²³⁵U-²³⁸U, Groundwater Ages, and Hydrogeochemistry ». ACS Earth and Space Chemistry 5, n^o 12 (1 décembre 2021) : 3474–87. http://dx.doi.org/10.1021/acsearthspacechem.1c00307.

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Nabila, Putri, Mohammad Ali Shafii et Seni Herlina J. Tongkukut. « Neutron Mean Free Path in the Slab Reactor Core using One-Dimensional Multi-group Diffusion Equation ». Computational And Experimental Research In Materials And Renewable Energy 5, n^o 1 (31 mai 2022) : 56. http://dx.doi.org/10.19184/cerimre.v5i1.31566.

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Analysis of the neutron mean free path in the slab reactor core has been carried out using one-dimensional multi-group diffusion equation. This study aims to determine the neutron mean free path in the slab reactor core with the neutron diffusion coefficient calculation using macroscopic cross-section data in the nuclear fuel cell level and the neutron flux distribution. The type of reactor used in this research is a fast reactor with nuclear fuel is uranium-plutonium nitride (U-PuN). The neutron mean free path is calculated for 70 energy groups of neutron by dividing the energy groups, namely the fast energy group, the intermediate energy group and the thermal energy group. The results showed that the neutron mean free path value for U-235 and Pu-239 fuels were obtained almost the same in all energy groups, namely in the fast energy group ranging from 0.11.10-2 to 0.17.10-2 cm, in the intermediate energy group 0.16.10-2 to 1.78.10-2 cm, and in the thermal energy group 0.4.0-2 to 8.04.10-2 cm. The neutron mean free path value for U-238 fuel is much smaller than that for U-235 and Pu-239 fuel, ranging from 0.03.10-2 to 0.36.10-2 cm. These results can be confirmed, because U-238 fuel is a fertile material. Keywords: Neutron mean free path, diffusion equation, neutron flux, slab reactor core

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Hussian, Hussian, et Kamal Ali. « Natural and Artificial Radionuclides Distribution in Surface Soil in Baghdad International Airport Region ». Iraqi Geological Journal 57, n^o 1B (29 février 2024) : 214–28. http://dx.doi.org/10.46717/igj.57.1b.17ms-2024-2-26.

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This is the first time that radiological assessment achieved in the Baghdad International Airport (BIA) in Iraq. Twenty-three sites were sampled from upper 5 cm of the surface soil within the BIA to be analyzed for the radioactivity of natural radionuclides Ra-226, Th-232 and K-40 and the artificial radionuclide, Cs-137 using gamma spectroscopy based on Hyper pure Germanium detector (HPGe). Ten samples out of the 23 samples were analyzed for U-238, U-235 using the Neutron Activation Analysis method. To determine the percentage of DU [DU (%)] which is calculated from the 235U/238U isotope ratio. The study showed that there is a possibility of slight contamination with depleted uranium in two sites out of the 23 sites that were examined. The average activities of Ra-226, Th-232, and K-40 in the study area are within the limits of world averages, while there are evidences that new feeding of Cs-137 in the region, reaches about 19 Bq/kg, from the new global fallout after Chernobyl accident. The measured and calculated absorbed doses in the study area were within international limits and no need for farther monitoring. Annual effective dose equivalent due to resuspension of Ra-226 is estimated to be 1.0E-10Sv, and this value is negligible compared with 1 mSv permissible value for public recommended by ICRP.

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Warren, Glen A., Joseph A. Caggiano, William Bertozzi, Stephen E. Korbly, Robert J. Ledoux et William H. Park. « On the Search for Nuclear Resonance Fluorescence Signatures of $^{235}{\rm U}$ and $^{238}{\rm U}$ Above 3 MeV ». IEEE Transactions on Nuclear Science 57, n^o 1 (février 2010) : 317–22. http://dx.doi.org/10.1109/tns.2009.2038470.

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Liem, Peng Hong, Zuhair et Donny Hartanto. « Nuclear data sensitivity and uncertainty analyses on the first core criticality of the RSG GAS multipurpose research reactor ». EPJ Web of Conferences 239 (2020) : 22011. http://dx.doi.org/10.1051/epjconf/202023922011.

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The results of criticality, sensitivity and uncertainty (S\U) analyses on the first core criticality of the Indonesian 30 MWth Multipurpose Reactor RSG GAS (MPR-30) using the recent nuclear data libraries (ENDF/B-VII.1 and JENDL-4.0) and analytical tools available at present (WHISPER-1.1) are presented. Two groups of criticality benchmark cases were carefully selected from the experiments conducted during the first criticality approach and control rod calibrations. The C/E values of effective neutron multiplication factor (k) for the worst case was found around 1.005. Large negative sensitivities were found in (n,e-mail:γ) reaction of H-1, U-235, Al-27, U-238 and Be-9 while large positive sensitivities were found in U-235 (total nu and fission), H-1 (elastic), Be-9 (free gas, elastic) and H-1 S(α,β) (lwtr.20t, inelastic). The S\U analysis results concluded that the uncertainties of k originated from the nuclear data were found around 0.6% which covered well the [C/E-1] values. Differences in the sensitivities amongst the two nuclear data libraries were also identified, and recommendation for improving the nuclear data library was given.

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Mihaljev, Željko, Sandra Jakšić, Milica Živkov Baloš et Nenad Popov. « RADIOACTIVE RESIDUE IN HONEY ». Archives of Veterinary Medicine 14, n^o 2 (31 décembre 2021) : 49–60. http://dx.doi.org/10.46784/eavm.v14i2.290.

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The concentration of radioactive isotopes in honey is an important bioindicator of environmental contamination. For that purpose, a total of 66 samples of different types of honey (acacia, meadow, linden, sunflower, flower, forest, oilseed rape, chestnut) were examined. The samples were collected during 2020 and 2021 at different localities in the Republic of Serbia (Vojvodina, Central Serbia, Kosovo). Gamma spectrometric analysis was used to determine natural radionuclides 40K, 232Th, 226Ra, 238U, 235U and 22Na and anthropogenic radionuclide 137Cs. The obtained results indicate that the predominant radionuclide in all the analyzed honey samples is natural K-40, whose average activity was 74 Bq / kg. The activity of other tested radionuclides ranged as follows: Th-232: <1-2.0; Ra-226: 1.9-15.6; U-238: <1-31.4; U-235: <0.2-1.61 and Na-22: <0.2-2.4 Bq / kg. The activity of the artificial radionuclide Cs-137 was measured in 53% of the tested samples from the territory of Kosovo with the maximum value of 3.63 Bq / kg. Regarding the determined level of radioactive residues, it can be concluded that the honey produced in the Republic of Serbia is healthy and environmentally safe food. Key words: honey, natural radionuclides, artificial radionuclides

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Chen, Yonghao, Yiwei Yang, Zhizhou Ren, Wei Jiang, Ruirui Fan, Han Yi, Rong Liu et al. « Measurement of neutron-induced fission cross sections of ²³⁵U and ²³⁸U relative to n-p scattering at CSNS Back-n facility ». EPJ Web of Conferences 284 (2023) : 01013. http://dx.doi.org/10.1051/epjconf/202328401013.

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235U and 238U are very important isotopes in the nuclear energy system. Their neutron-induced fission cross sections have been measured intensively and evaluated as standard up to 200 MeV. However, as a matter of fact, the experimental data in the high-energy region are scarce. This work reports the measurement of 235, 238U(n, f) cross sections relative to n-p scattering performed at the China Spallation Neutron Source (CSNS) back-streaming neutron facility (Back-n). Preliminary results of 235, 238U(n, f) cross sections from 10 to 66 MeV are obtained, which are generally following the shape of the IAEA standard. However, significant discrepancies are observed at some given energies, which will be further studied.

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Goto, Kosuke T., Ariel D. Anbar, Gwyneth W. Gordon, Stephen J. Romaniello, Gen Shimoda, Yutaro Takaya, Ayaka Tokumaru et al. « Uranium isotope systematics of ferromanganese crusts in the Pacific Ocean : Implications for the marine 238 U/ 235 U isotope system ». Geochimica et Cosmochimica Acta 146 (décembre 2014) : 43–58. http://dx.doi.org/10.1016/j.gca.2014.10.003.

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Usman, Jakaria, et Shafii Ali Mohammad. « Perhitungan Matriks Pij dan Distribusi Fluks Neutron pada Sel Bahan Bakar Nuklir U-235 dan U-238 Berbentuk Slab Menggunakan MOC ». Jurnal Fisika Unand 6, n^o 1 (5 janvier 2017) : 74–80. http://dx.doi.org/10.25077/jfu.6.1.74-80.2017.

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Telah dilakukan perhitungan matriks Pij serta distribusi fluks neutron di dalam geometri slab pada sel bahan bakar nuklir U-235 dan U-238 dalam kondisi homogen dan tidak homogen. Penelitian ini bertujuan untuk memperoleh nilai fluks skalar dan nilai Pij yang menggunakan Method of Characteristic (MOC). Besarnya fluks neutron dan nilai Pij bergantung pada penampang lintang bahan bakar nuklir, lebar region, jumlah region dan parameter input lainnya. Hasil penelitian ini secara umum telah sesuai dengan teori yaitu nilai Pij total pada beberapa region bernilai ≈ 1. Nilai Pij dan distribusi fluks neutron pada keadaan homogen lebih baik dan seragam dibandingkan pada keadaan tidak homogen, hal ini terlihat dari bentuk distribusi fluks pada slab sesuai dengan penelitian yang dilakukan oleh Karriem (2012) Kata kunci: Matriks Pij, fluks neutron, Method of Characteristic(MOC), homogen, tidak homogen

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Tovesson, F., D. Duke, V. Geppert-Kleinrath, B. Manning, D. Mayorov, S. Mosby et K. Schmitt. « Fission fragment yields and total kinetic energy release in neutron-induced fission of235,238U,and239Pu ». EPJ Web of Conferences 169 (2018) : 00024. http://dx.doi.org/10.1051/epjconf/201816900024.

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Different aspects of the nuclear fission process have been studied at Los Alamos Neutron Science Center (LANSCE) using various instruments and experimental techniques. Properties of the fragments emitted in fission have been investigated using Frisch-grid ionization chambers, a Time Projection Chamber (TPC), and the SPIDER instrument which employs the 2v-2E method. These instruments and experimental techniques have been used to determine fission product mass yields, the energy dependent total kinetic energy (TKE) release, and anisotropy in neutron-induced fission of U-235, U-238 and Pu-239.

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Huang, Gan, Chao Yang, Jichong Lei, Lingling Su, Zhenping Chen et Tao Yu. « Study on Fuel Selection for a Long-Life Small Lead-Based Reactor ». Sustainability 14, n^o 24 (15 décembre 2022) : 16840. http://dx.doi.org/10.3390/su142416840.

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The choice of an appropriate fuel can effectively prolong the refueling cycle of a reactor core. The Th-U cycle and U-Pu cycle are commonly used fuel breeding cycles. Oxide fuels, nitride fuels, and metal fuels are the primary candidate fuels for lead-based reactors. For fuel selection, a core model of a 60 MWt reactor was established. The results show that the breeding performance of the breeding fuel Th-232 is better than that of U-238, and the driving performance of the driving fuel Pu-239 is better than that of U-235. Therefore, PuO2-ThO2, PuN-ThN, and Pu-Th-Zr fuels may have good performance. By comparing the reactivity loss of three types of fuel, it was found that the reactivity loss of PuN-ThN fuel is the smallest. Hence, using PuN-ThN fuel as a core fuel can result in a longer refueling cycle. On this basis, PuN-ThN fuel was used in the preliminary design of the 120 MWt core physical model. It can be seen that when PuN-ThN fuel is used as the core fuel, a smaller reactivity swing (1408 pcm), smaller power peak factor, and super long refueling cycle (more than 30 years) can be obtained.

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Goulding, Paul, Christine Räisänen, Pia Köhlmyr, Arne Olofsson, John Brovik, Helena Bergmann, Mall Stålhammar et al. « Reviews and notices ». Moderna Språk 90, n^o 2 (1 décembre 1996) : 222–47. http://dx.doi.org/10.58221/mosp.v90i2.9967.

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Includes the following reviews: p. 222. Paul Goulding. Giles, J. & Middleton, T. (eds.), Writing Englishness 1900-1950. p. 223. Christine Räisänen. McGee, A., Read to Write Well. + McGee, A., Read to Write Well Answer Key. pp. 224-235. Pia Köhlmyr. Falonius, T. & Karlsson, B., Highlights A. + Falonius, T. & Karlsson, B., Highlights of English Grammar. + Falonius, T. & Karlsson, B., Highlights B. pp. 225-226. Paul Goulding. Shakespear, W., Macbeth. pp. 226-228. Arne Olofsson. Törnqvist, L., Engelsk-svensk namnordbok. pp. 228-230. John Brovik. Stone, R., Outerbridge Reach. pp. 230-231. Helena Bergmann. Conde, M., La migration des Coeurs. p. 231. Mall Stålhammar. Translation Perspectives IX 1996: Translation Horizions. p. 232. Dan Landmark. Woolf, S., Nationalism in Europe 1815 to the present. A Reader. pp. 232-233. Pascale Voillet. Lo-Johansson, I., Peddling My Wares. pp. 233-. Ronald Paul. Hobsbawn, E., The Age of Extremes: the short twentieth century 1914-1991. pp. 235-237. Gustav Korlén. Kluge, F., Etymologisches Wörterbuch der deutschen Sprache. pp. 237-239. Lars-Olof Nyhlén. Ammon, U., Die deutsches Sprache in Deutschland, Österreich und der Schweiz. pp. 239-240. Edelgard Biedermann. Delius, F.C., Der Spaziergang von Rostock nach Syrakus. pp. 240-243. Klaus Rossenbeck. Svensson, G., Tyskland. Kalla fakta. pp. 243-244. Tom Conner. Tiersky, R., France in the New Europe. Changing yet Steadfast. pp. 244-247. Tom Conner. Porch, D., The French Secret Services. From the Dreyfus Affair to the Gulf War.

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Fulsom, Bryan. « Bragg curve spectroscopy for improved fission fragment identification ». EPJ Web of Conferences 242 (2020) : 01006. http://dx.doi.org/10.1051/epjconf/202024201006.

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We report on the development of Bragg curve spectroscopy techniques to improve fission fragment identification in the measurement of independent fission product yields. The NIFFTE collaboration’s fissionTPC detector provides ionization energy and particle tracking information from neutroninduced fission targets. A joint effort between PNNL, LLNL, LANL, and the Colorado School of Mines is investigating the ionization profiles deposited by U-235, U-238, and Pu-239 fission products in this detector, with the goal of including additional stopping power information beyond a standard 2E analysis. The aim is to improve the determination of fragment atomic and mass numbers with this information, via methods such as parametric fits and machine learning techniques.

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Tamashiro, Aaron, Jason Burke, Stephen Padgett, Sean Burcher, Todd Palmer et Camille Palmer. « New Fission Product Yield Measurements at Oregon State University ». EPJ Web of Conferences 242 (2020) : 01010. http://dx.doi.org/10.1051/epjconf/202024201010.

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Cumulative fast fission product yields for 235 U and 238 U were measured at Godiva-IV in burst mode. Data was collected starting 45 minutes after the prompt irradiation. Data analysis codes were developed to analyze gammarays and calculate fission product yields with their respective uncertainties. Due to uncertainties in the branching ratios, different γ-rays from the same isotope led to different fission yield. This led to an effort at Oregon State University (OSU) to utilize the Rabbit facility at their 1 MegaWatt Training, Research, Isotopes, General Atomics (TRIGA) nuclear research reactor. The new experimental setup will allow us to measure branching ratio data and short-lived fission product yields starting seconds after a prompt irradiation.

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Landsberger, S., A. Sharp, S. Wang, Y. Pontikes et A. H. Tkaczyk. « Characterization of bauxite residue (red mud) for 235 U, 238 U, 232 Th and 40 K using neutron activation analysis and the radiation dose levels as modeled by MCNP ». Journal of Environmental Radioactivity 173 (juillet 2017) : 97–101. http://dx.doi.org/10.1016/j.jenvrad.2016.12.008.

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Paicu, Marius, et Ning Zhu. « Global well-posedness of 3D inhomogeneous Navier–Stokes system with small unidirectional derivative ». Nonlinearity 36, n^o 5 (30 mars 2023) : 2403–34. http://dx.doi.org/10.1088/1361-6544/acc37a.

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Abstract In Liu and Zhang (2020 Arch. Ration. Mech. Anal. 235 1405–44); Liu et al (2020 Arch. Ration. Mech. Anal. 238 805–43), the authors proved that as long as the one-directional derivative of the initial velocity is sufficiently small in some scaling invariant spaces, then the (anisotropic) Navier–Stokes (NS) system has a unique global solution. The goal of this paper is to extend this type of result to the 3D inhomogeneous (density-dependent) NS system. More precisely, given initial density such that a 0 ≜ 1 ρ 0 − 1 ∈ B p , 1 3 p ( R 3 ) and the initial velocity u 0 = ( u 0 h , u 0 3 ) ∈ B p , 1 − 1 + 2 p , 1 p ( R 3 ) , with u 0 h belonging to H 1 ( R 3 ) , then the inhomogeneous NS system has a unique global solution provided that ( ∥ a 0 ∥ B p , 1 3 p + ∥ Λ h − 1 ∂ 3 u 0 ∥ B p , 1 − 1 + 2 p , 1 p ) ⋅ f ( u 0 ) being sufficiently small for some bounded function f depending on ∥ u 0 ∥ p , 1 − 1 + 2 p , 1 p and ∥ u 0 h ∥ H 1 . This provide a more general result that of Chemin et al (2014 Commun. Math. Phys. 272 529–66); Chemin and Zhang (2015 Commun. PDE 40 878–96).

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Foucher, Joséphine. « Book review : Decolonization and Feminisms in Global Teaching and Learning, edited by Sara de Jong, Rosalba Icaza, and Olivia U. Rutazibwa ». Scholarship of Teaching and Learning in the South 4, n^o 2 (28 septembre 2020) : 235. http://dx.doi.org/10.36615/sotls.v4i2.146.

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In this review of Decolonization and Feminisms in Global Teaching and Learning edited by Sara de Jong, Rosalba Icaza and Olivia U. Rutazibwa, book reviewer Joséphine Foucher explains how this book serves as a compelling resource and toolbox for adopting decolonial and feminist thought in the development of critical pedagogies. Keywords: Decolonization, Feminisms, Epistemic justice, Praxis, Critical pedagogyHow to cite this article:Foucher, J. 2020. Book review: Decolonization and Feminisms in Global Teaching and Learning, edited by Sara de Jong, Rosalba Icaza, and Olivia U. Rutazibwa. Scholarship of Teaching and Learning in the South. 4(2): 235-238. https://doi.org/10.36615/sotls.v4i2.146.This work is licensed under the Creative Commons Attribution 4.0 International License. To view a copy of this license, visit http://creativecommons.org/licenses/by/4.0/

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Putri, Suci Claudia, Menik Ariani, Idha Royani, Arsali et Fiber Monado. « The calculation of uranium metallic Fuel (U-10%wtZr) cell with helium coolant using SRAC 2K6 ». Journal of Physics : Conference Series 2126, n^o 1 (1 novembre 2021) : 012001. http://dx.doi.org/10.1088/1742-6596/2126/1/012001.

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Abstract In this study, pin-shaped natural metallic uranium fuel cells with a diameter of 1.4 cm were designed with and without enrichment of 2-10% by using helium as a coolant. The calculations were conducted by using SRAC software and the results show that the greater the enrichment level, the more significant the value of the infinite-multiplication-factor (kinf), meanwhile the conversion ratio is smaller. Basically, uranium exists in two isotopic forms namely, U-235 and U-238 which are transformed into other element such as Pu-239 when they both go through fission and transmutation reactions in the reactor core. Therefore, to obtain the optimum reactor core design, the performance information of nuclear fuel cells from the variations of burn-up time needs to be taken into consideration.

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Поп, Оксана М., М. В. Стець et В. Т. Маслюк. « Method of standard nuclide sets of ³²Th, ²³⁵U, ²³⁸U, series, and its some metrological сharacteristics ». Scientific Herald of Uzhhorod University.Series Physics 38 (1 juillet 2015) : 88–95. http://dx.doi.org/10.24144/2415-8038.2015.38.88-95.

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Baldwin, David P., Daniel S. Zamzow et Arthur P. D'Silva. « High-Resolution Spectroscopy Using an Acousto-Optic Tunable Filter and a Fiber-Optic Fabry-Perot Interferometer ». Applied Spectroscopy 50, n^o 4 (avril 1996) : 498–503. http://dx.doi.org/10.1366/0003702963906032.

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A compact, solid-state, high-resolution spectrometer consisting of an acousto-optic tunable filter (AOTF) and a fiber-optic Fabry-Perot (FFP) interferometer has been developed. The system has been designed for high-resolution inductively coupled plasma atomic emission spectroscopy (ICP-AES) applications. A description of the AOTF-FFP and its performance is presented. The resolution of the AOTF-FFP was determined by measuring the physical widths of ICP emission lines using a 1.5-m-focal-length grating spectrometer and deconvoluting the physical line shapes from the acquired AOTF-FFP spectra. Over the optimum range of the FFP mirror coatings, the resolution is sufficient for the determination of isotopic and hyperfine emission features in ICP-AES experiments, and approaches that of the 1.5-m spectrometer. The application of the AOTF-FFP to the determination of uranium isotopes (U-235 and U-238) introduced into the ICP is presented.

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