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Journal articles on the topic 'Reactores de fisión nuclear'

Author: Grafiati

Published: 4 June 2021

Last updated: 1 February 2022

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1

Delepine, David, Edgar Casimiro Linares, José-Antonio Hernández Valencia, and Gerardo Moreno. "Uso de detectores de neutrinos para el monitoreo de reactores nucleares." Acta Universitaria 19, no. 3 (2009): 5–8. http://dx.doi.org/10.15174/au.2009.80.

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Se estudia la factibilidad del uso de los detectores de antineutrinos para el monitoreo de reactores nucleares. Usando un modelo sencillo de cascada de fisión a dos componentes, se ilustra la dependencia del número de antineutrinos detectados a una distancia L del reactor según la composición nuclear del combustible. Se explica el principio de detección de neutrinos de reactores en base al decaimiento beta inverso y se describe como los detectores de neutrinos pueden emplearse para el monitoreo de la producción de materiales fisibles en el reactor. Se comenta como generalizar este análisis al

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2

Sandoval Lagos, Jaime, and Edgar Mauricio López. "Desarrollo de capacidades para la operación del reactor nuclear IAN-R1." Revista Investigaciones y Aplicaciones Nucleares, no. 2 (December 17, 2018): 15–30. http://dx.doi.org/10.32685/2590-7468/invapnuclear.2.2018.52.

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Este documento presenta una descripción histórica del reactor nuclear de investigación IAN-R1. Se hace una contextualización sobre el origen del reactor en el marco del programa Átomos para la Paz, y se incluyen las características técnicas y la configuración inicial del núcleo, cuyo combustible nuclear de tecnología MTR (90%) fue sustituido por uno de tipo TRIGA (20%) (acrónimos de material testing reactor y training, research, isotopes general atomics, respectivamente). De igual manera, se presentan las características de las dos modernizaciones que se han realizado a la instrumentación y el

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3

Rockwell, Theodore. "Facts & Fission." Mechanical Engineering 131, no. 12 (2009): 32–37. http://dx.doi.org/10.1115/1.2009-dec-3.

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This article discusses the real-world practicality of nuclear power. Neither reactors nor casks of spent fuel have the capability of going “prompt critical” like a bomb. The laws of nature prohibit it and engineers must make clear that facts of nature are not matters of opinion. The Chernobyl reactor, which failed so spectacularly in Ukraine in 1986, became for many a symbol of the dangers represented by nuclear reactors. But that is not warranted; such an accident is simply impossible for the kind of commercial reactors now being planned or built. From a public safety standpoint, the most imp

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4

Kondylakis, J. S. "Theoretically and under very special applied conditions a nuclear fission reactor may explode as nuclear bomb." HNPS Proceedings 18 (November 23, 2019): 121. http://dx.doi.org/10.12681/hnps.2558.

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This article/presentation describes a theoretical and applied research in nuclear fission reactor systems. It concerns with theoretical approaches and in very special applied cases consideration where a common nuclear fission reactor system may be considered to explode as nuclear bomb. This research gives critical impacts to the design, operation, management and philosophy of nuclear fission reactors systems. It also includes a sensitivity analysis of a particular applied problem concerning the core melting of a nuclear reactor and its deposit to the bottom of reactor vessel. Specifically, in

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5

Naumov, Vadim, Sergey Gusak, and Andrey Naumov. "Small nuclear power plants for power supply in arctic regions: assessment of spent nuclear fuel radioactivity." Nuclear Energy and Technology 4, no. 2 (2018): 119–25. http://dx.doi.org/10.3897/nucet.4.30677.

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The purpose of the present study is the investigation of mass composition of long-lived radionuclides accumulated in the fuel cycle of small nuclear power plants (SNPP) as well as long-lived radioactivity of spent fuel of such reactors. Analysis was performed of the published data on the projects of SNPP with pressurized water-cooled reactors (LWR) and reactors cooled with Pb-Bi eutectics (SVBR). Information was obtained on the parameters of fuel cycle, design and materials of reactor cores, thermodynamic characteristics of coolants of the primary cooling circuit for reactor facilities of diff

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6

Ripani, M. "Energy from nuclear fission." EPJ Web of Conferences 246 (2020): 00010. http://dx.doi.org/10.1051/epjconf/202024600010.

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The physics of nuclear fission will be briefly illustrated, from the basic mechanism behind this phenomenon to the relevant physical quantities like nuclear cross sections, neutron flux and reaction products, together with the accompanying phenomenon of neutron capture and its role in determining how the fuel transforms in a nuclear reactor. The basic concepts underlying the operation of different types of nuclear reactors will be illustrated, along with the concept of fuel cycle. After touching on the aspect of safety, the current situation of nuclear power in the world, with its costs, its r

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7

Ruskov, Ivan, Andrei Goverdovski, Walter Furman, et al. "Neutron induced fission of 237Np – status, challenges and opportunities." EPJ Web of Conferences 169 (2018): 00021. http://dx.doi.org/10.1051/epjconf/201816900021.

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Nowadays, there is an increased interest in a complete study of the neutron-induced fission of 237Np. This is due to the need of accurate and reliable nuclear data for nuclear science and technology. 237Np is generated (and accumulated) in the nuclear reactor core during reactor operation. As one of the most abundant long-lived isotopes in spent fuel (“waste”), the incineration of 237Np becomes an important issue. One scenario for burning of 237Np and other radio-toxic minor actinides suggests they are to be mixed into the fuel of future fast-neutron reactors, employing the so-called transmuta

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8

Chavez-Estrada, Marisol, and Alexis A. Aguilar-Arevalo. "Antineutrino Flux from the Laguna Verde Nuclear Power Plant." Advances in High Energy Physics 2015 (2015): 1–9. http://dx.doi.org/10.1155/2015/109738.

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We present a calculation of the antineutrino flux produced by the reactors at the Laguna Verde Nuclear Power Plant in México, based on the antineutrino spectra produced in the decay chains of the fission fragments of the main isotopes in the reactor core, and their fission rates, which have been calculated using the DRAGON simulation code. We also present an estimate of the number of expected events in a detector made of plastic scintillator with a mass of 1 ton, at 100 m from the reactor cores.

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9

Till, Charles E. "Nuclear fission reactors." Reviews of Modern Physics 71, no. 2 (1999): S451—S455. http://dx.doi.org/10.1103/revmodphys.71.s451.

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10

Hidaka, Hiroshi. "A Review of In Situ Isotopic Studies of the Oklo and Bangombé Natural Fission Reactors Using Microbeam Analytical Techniques." Minerals 10, no. 12 (2020): 1060. http://dx.doi.org/10.3390/min10121060.

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Isotopic analyses of elements in the natural reactor materials have often been performed to understand the distribution behaviors of the fission products and to evaluate the function of nuclear reactions since the first discovery of a natural reactor in 1972. Several types of unique microminerals, including significant amounts of fission products, have been found in and around the Oklo and the Bangombé natural reactors. In the past two decades, microbeam techniques using ion and laser probe facilities have been effectively applied for the in situ isotopic analyses of individual microminerals t

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11

Taylor, Zack, Benjamin Collins, and Ivan Maldonado. "MATRIX EXPONENTIAL METHODS FOR PARALLEL COMPUTING OF ISOTOPIC DEPLETION AND SPECIES TRANSPORT FOR MOLTEN SALT REACTOR ANALYSIS." EPJ Web of Conferences 247 (2021): 06047. http://dx.doi.org/10.1051/epjconf/202124706047.

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Matrix exponential methods have long been utilized for isotopic depletion in nuclear fuel calculations. In this paper we discuss the development of such methods in addition to species transport for liquid fueled molten salt reactors (MSRs). Conventional nuclear reactors work with fixed fuel assemblies in which fission products and fissile material do not transport throughout the core. Liquid fueled molten salt reactors work in a much different way, allowing for material to transport throughout the primary reactor loop. Because of this, fission product transport must be taken into account. The

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12

Lambert, Timothy, and Xuan Hieu Nghiem. "Review of the Deployment of and Research into Generation III & IV Nuclear Fission Reactors for Power Generation." PAM Review Energy Science & Technology 1 (August 3, 2015): 90–108. http://dx.doi.org/10.5130/pamr.v1i0.1387.

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Nuclear fission is one of the more popular and efficient sources of energy that has been used in the last few decades. In the setting of the ongoing worldwide debate of the energy problem, this paper will review the different types and generations of nuclear reactors, and do comparisons with other notable energy sources (biofuel and fusion). The current generations III, III+, IV of reactor (mostly pressurized water reactors), their thermal efficiency, technical (structure and configuration), lifetime, energy output and how the systems contrast are discussed. The paper was written by gathering

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13

Petti, D., D. Crawford, and N. Chauvin. "Fuels for Advanced Nuclear Energy Systems." MRS Bulletin 34, no. 1 (2009): 40–45. http://dx.doi.org/10.1557/mrs2009.11.

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AbstractFuels for advanced nuclear reactors differ from conventional light water reactor fuels and also vary widely because of the specific architectures and intended missions of the reactor systems proposed to deploy them. Functional requirements of all fuel designs for advanced nuclear energy systems include (1) retention of fission products and fuel nuclides, (2) dimensional stability, and (3) maintenance of a geometry that can be cooled. In all cases, anticipated fuel performance is the limiting factor in reactor system design, and cumulative effects of increased utilization and increased

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14

Petrovski, A. M., T. N. Korbut, E. A. Rudak, and M. O. Kravchenko. "Accounting of the vver-1200 overload influence for fission products activities calculating." Proceedings of the National Academy of Sciences of Belarus, Physical-Technical Series 64, no. 4 (2020): 491–96. http://dx.doi.org/10.29235/1561-8358-2019-64-4-491-496.

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Current work is aimed at the analysis of the fission products decay influence during fuel reloading, when calculating the accumulated fission products activity for the VVER-1200 reactor fuel campaign. The Bateman problem solution based technique was used for calculations, within the framework of the two fissile nuclides approximation. The fission products producing process for the VVER-1200 reactor stationary campaign is considered, taking into account the reactor shutdown periods for refueling and without taking them into account (instant reload approximation). It was shown, that the instant

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15

Rohanda, Anis. "ANALISIS PERUBAHAN MASSA BAHAN FISIL DAN NON FISIL DALAM TERAS PWR 1000 MWe DENGAN ORIGEN-ARP 5.1." JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA 17, no. 1 (2015): 13. http://dx.doi.org/10.17146/tdm.2015.17.1.2234.

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Teras reaktor merupakan tempat terjadinya reaksi pembelahan (fisi) yang terkendali. Komponen reaktor seperti bahan bakar, kelongsong (cladding) dan air pendingin memiliki peranan penting dalam keberlangsungan reaksi fisi. Reaksi fisi mengakibatkan terbentuknya sejumlah nuklida hasil fisi dan hasil aktivasi. Hasil fisi berasal dari reaksi tangkapan neutron termal dengan bahan fisil sedangkan hasil aktivasi berasal dari interaksi bahan non fisil seperti material kelongsong dan pendingin oleh neutron dan gamma. Pada setiap pengoperasian suatu reaktor, informasi perubahan massa bahan fisil dan non

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16

Estienne, M., M. Fallot, L. Giot, et al. "Summation Calculations for Reactor Antineutrino Spectra, Decay Heat and Delayed Neutron Fractions Involving New TAGS Data and Evaluated Databases." EPJ Web of Conferences 211 (2019): 01001. http://dx.doi.org/10.1051/epjconf/201921101001.

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Three observables of interest for present and future reactors depend on the β decay properties of the fission products: antineutrinos from reactors, the reactor decay heat and delayed neutron emission. In these proceedings, we present new results from summation calculations of the first two quantities quoted above, performed with evolved independent yields coupled with fission product decay data, from various nuclear data bases or models. New TAGS results from the latest experiment of the TAGS collaboration at the JYFL facility of Jyväskylä will be displayed as well as their impact on the anti

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17

Solbrig, Charles W. "Converting Maturing Nuclear Sites to Integrated Power Production Islands." Science and Technology of Nuclear Installations 2011 (2011): 1–10. http://dx.doi.org/10.1155/2011/519538.

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Nuclear islands, which are integrated power production sites, could effectively sequester and safeguard the US stockpile of plutonium. A nuclear island, an evolution of the integral fast reactor, utilizes all the Transuranics (Pu plus minor actinides) produced in power production, and it eliminates all spent fuel shipments to and from the site. This latter attribute requires that fuel reprocessing occur on each site and that fast reactors be built on-site to utilize the TRU. All commercial spent fuel shipments could be eliminated by converting all LWR nuclear power sites to nuclear islands. Ex

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18

Salahuddin, Asif, and Masood Iqbal. "Comparison of actinides and fission products recycling scheme with the normal plutonium recycling scheme in fast reactors." Nuclear Technology and Radiation Protection 28, no. 1 (2013): 1–17. http://dx.doi.org/10.2298/ntrp1301001s.

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Multiple recycling of actinides and non-volatile fission products in fast reactors through the dry re-fabrication/reprocessing atomics international reduction oxidation process has been studied as a possible way to reduce the long-term potential hazard of nuclear waste compared to that resulting from reprocessing in a wet PUREX process. Calculations have been made to compare the actinides and fission products recycling scheme with the normal plutonium recycling scheme in a fast reactor. For this purpose, the Karlsruhe version of isotope generation and depletion code, KORIGEN, has been modified

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19

Ripani, M. "Energy from nuclear fission." EPJ Web of Conferences 189 (2018): 00013. http://dx.doi.org/10.1051/epjconf/201818900013.

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The main features of nuclear fission as a physical phenomenon will be revisited, emphasizing its peculiarities with respect to other nuclear reactions. Some basic concepts underlying the operation of nuclear reactors and the main types of reactors will be illustrated, including fast reactors, showing the most important differences among them. The nuclear cycle and radioactive nuclear waste production will be also discussed, along with the perspectives offered by next-generation nuclear assemblies being proposed. The current situation of nuclear power in the world, its role in reducing carbon e

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20

Bonal, Jean-Pierre, Akira Kohyama, Jaap van der Laan, and Lance L. Snead. "Graphite, Ceramics, and Ceramic Composites for High-Temperature Nuclear Power Systems." MRS Bulletin 34, no. 1 (2009): 28–34. http://dx.doi.org/10.1557/mrs2009.9.

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AbstractThe age of nuclear power originated with the gas-cooled, graphite-moderated reactor in the 1940s. Although this reactor design had intrinsic safety features and enjoyed initial widespread use, gas-cooled reactor technology was supplanted by higher power density water-cooled systems in the 1960s. However, the next-generation reactors seek enhanced power conversion efficiency and the ability to produce hydrogen, best accomplished with high-temperature gas-cooled systems. Thus, international interest in gas-cooled reactor systems is reemerging. Although the materials systems of these reac

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21

Mesquita, Amir Zacarias, Daniel Artur Pinheiro Palma, Hugo Cesar Rezende, et al. "Power Measurement Methodologies for Pool Nuclear Research Reactors." Latin American Journal of Development 3, no. 2 (2021): 882–92. http://dx.doi.org/10.46814/lajdv3n2-032.

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Redundancy and diversity are two important criteria for power measurement in nuclear reactors. Other criteria such as accuracy, reliability and response speed are also of major concern. Power monitoring of nuclear reactors is normally done by means of neutronic instruments, i.e. by the measurement of neutron flux. The greater the number of channels for power measuring the greater is the reliability and safety of reactor operations. The aim of this research is to develop new methodologies for on-line monitoring of nuclear reactor power using other reliable processes. One method uses the tempera

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22

Langston, Lee S. "PBMR-A Future Failsafe Gas Turbine Nuclear Power Plant?" Mechanical Engineering 133, no. 08 (2011): 54–59. http://dx.doi.org/10.1115/1.2011-aug-5.

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This article presents an overview of a pebble bed modular reactor (PBMR) power plant. A PBMR power plant is a gas turbine nuclear power plant that completely eliminates the possibility of a devastating loss-of-coolant accident. In a PBMR power plant, uranium dioxide nuclear fuel, coated with mass diffusion and radioactive fission product containment layers of pyrolytic carbon and silicon carbide, is formed into nuclear poppy seed-sized fuel particles. Some 15,000 of these are embedded in a tennis ball-sized graphite sphere, which is encased in a thin carbon shell, sintered, annealed and machin

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23

Tikhomirov, G. V., and A. S. Gerasimov. "THE MAIN PROBLEMS OF THE MANAGEMENT OF RADIOACTIVE WASTE FROM NPP SPENT FUEL USING NUCLEAR TRANSMUTATION." Professor’s Journal. Series: Technical science 3 (September 1, 2019): 41–56. http://dx.doi.org/10.18572/2686-8598-2019-3-3-41-56.

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the main problems associated with research on transmutation, and whichshould be paid attention to by today's young researchers, are formulated. The processes of formation of hazardous nuclides during transmutation in reactor facilities are considered. The goals of transmutation and the choice of nuclides to be transmuted are discussed. The concept of radiotoxicity is explained as a measure of the radiological hazard of radio-active nuclides, based on the maximum permissible concentration of nuclides according to the IAEA standards. The problem of the formation of secondary radioactive nuclides

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24

Luks, Aleksandra, Krzysztof Pytel, Mikołaj Tarchalski, Nikołaj Uzunow, and Tomasz Krok. "Modelling of thermal hydraulics in a KAROLINA calorimeter for its calibration methodology validation." Nukleonika 61, no. 4 (2016): 453–60. http://dx.doi.org/10.1515/nuka-2016-0074.

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Abstract Results of numerical calculations of heat exchange in a nuclear heating detector for nuclear reactors are presented in this paper. The gamma radiation is generated in nuclear reactor during fission and radiative capture reactions as well as radioactive decay of its products. A single-cell calorimeter has been designed for application in the MARIA research reactor in the National Centre for Nuclear Research (NCBJ) in Świerk near Warsaw, Poland, and can also be used in the Jules Horowitz Reactor (JHR), which is under construction in the research centre in Cadarache, France. It consists

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Jiang, Yifeng, Benoit Geslot, Vincent Lamirand, and Pierre Leconte. "Review of kinetic modulation experiments in low power nuclear reactors." EPJ Nuclear Sciences & Technologies 6 (2020): 55. http://dx.doi.org/10.1051/epjn/2020017.

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The safety improvement of nuclear reactors requires continuous efforts in understanding the fundamental physical quantities related to the fission process. In neutronic models, the reactor dynamics is covered by the kinetic parameters to characterize the temporal behavior of the neutron population subject to perturbations. The reactor transfer function is a frequency domain analogy of this temporal description. It can be measured experimentally through transfer function analysis via noise analysis or kinetic modulation, for the study of reactor stability and kinetic parameters. This paper summ

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26

Ambrožič, Klemen, Damien Fourmentel, Hubert Carcreff, Vladimir Radulović, and Luka Snoj. "Computational support on the development of nuclear heating calorimeter detector design." EPJ Web of Conferences 225 (2020): 04033. http://dx.doi.org/10.1051/epjconf/202022504033.

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Heating due to energy deposition of intense ionizing radiation in samples and structural materials of nuclear reactors poses severe limitations in terms of cooling requirements for safe reactor operation, especially in high neutron and gamma flux environments of material testing fission reactors (MTRs) and novel fusion devices. A bilateral CEA-JSI research project was launched in 2018 with the objective to measure the gamma heating rates in standard reactor-related materials (graphite, aluminium, stainless steel and tungsten) as well as fusionrelevant materials (low-activation steel Eurofer-97

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Mesquita, A. Z., H. C. Rezende, A. A. C. Santos, and V. V. A. Silva. "DEVELOPMENT OF METHODS FOR MONITORING AND CONTROLLING POWER IN NUCLEAR REACTORS." Revista de Engenharia Térmica 13, no. 1 (2014): 24. http://dx.doi.org/10.5380/reterm.v13i1.62064.

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Power monitoring of nuclear reactors is normally done by means of neutronic instruments, i.e. by the measurement of neutron flux. The greater the number of channels for power measuring the greater is the reliability and safety of reactor operations. The aim of this research is to develop new methodologies for on-line monitoring of nuclear reactor power using other reliable processes. One method uses the temperature difference between an instrumented fuel element and the pool water below the reactor core. Another method consists of the steady-state energy balance of the primary and secondary re

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28

Burgio, N., M. Carta, V. Fabrizio, et al. "SUBCRITICALITY MONITORING IN FUSION-FISSION HYBRID REACTORS." Problems of Atomic Science and Technology, Ser. Thermonuclear Fusion 44, no. 2 (2021): 27–41. http://dx.doi.org/10.21517/0202-3822-2021-44-2-27-41.

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29

Stoneham, A. M. "Nuclear fission: the interplay of science and technology." Philosophical Transactions of the Royal Society A: Mathematical, Physical and Engineering Sciences 368, no. 1923 (2010): 3295–313. http://dx.doi.org/10.1098/rsta.2010.0061.

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When the UK’s Calder Hall nuclear power station was connected to the grid in 1956, the programmes that made this possible involved a powerful combination of basic and applied research. Both the science and the engineering were novel, addressing new and challenging problems. That the last Calder Hall reactor was shut down only in 2003 attests to the success of the work. The strengths of bringing basic science to bear on applications continued to be recognized until the 1980s, when government and management fashions changed. This paper identifies a few of the technology challenges, and shows how

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30

Khorasanov, Georgiy, Dmitriy Samokhin, Aleksandr Zevyakin, Yevgeniy Zemskov, and Anatoliy Blokhin. "Lead reactor of small power with metallic fuel." Nuclear Energy and Technology 4, no. 2 (2018): 99–102. http://dx.doi.org/10.3897/nucet.4.30527.

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The possibility for obtaining a hard neutron spectrum in small reactor cores has been considered. A harder spectrum than spectra in known fast sodium cooled and molten salt reactors has been obtained thanks to the selection of relatively small core dimensions and the use of metallic fuel and natural lead (natPb) coolant. The calculations for these compositions achieve an increased average neutron energy and a large fraction of hard neutrons in the spectrum (with energies greater than 0.8 MeV) caused by a minor inelastic interaction of neutrons with the fuel with no light chemical elements and

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31

Zeinalov, Shakir, Olga Sidorova, Pavel Sedyshev, Valery Shvetsov, Youngseok Lee, and Uk-Won Nam. "Thermal neutron intensity measurement with fission chamber in current, pulse and Campbell modes." EPJ Web of Conferences 231 (2020): 05009. http://dx.doi.org/10.1051/epjconf/202023105009.

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In thermal nuclear reactors, most of the power is generated by thermal neutron induced fission. Therefore, fission chambers with targets that respond directly to slow neutrons are of great interest for thermal neutron flux measurements due to relatively low sensitivity to gamma radiation. However, the extreme conditions associated with experiments at very low cross section demand highly possible thermal neutron flux, leading often to substantial design changes. In this paper we report design of a fission chamber for wide range (from 10 to 1012 n/cm2 sec) measurement of thermal neutron flux. Te

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Mills, Robert W., David J. Mountford, Jonathon P. Coleman, Carl Metelko, Matthew Murdoch, and Yan-Jie Schnellbach. "Modelling of the anti-neutrino production and spectra from a Magnox reactor." EPJ Web of Conferences 170 (2018): 07008. http://dx.doi.org/10.1051/epjconf/201817007008.

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The anti-neutrino source properties of a fission reactor are governed by the production and beta decay of the radionuclides present and the summation of their individual anti-neutrino spectra. The fission product radionuclide production changes during reactor operation and different fissioning species give rise to different product distributions. It is thus possible to determine some details of reactor operation, such as power, from the anti-neutrino emission to confirm safeguards records. Also according to some published calculations, it may be feasible to observe different anti-neutrino spec

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Tonchev, Anton P., Jack A. Silano, Chris Hagmann, et al. "Toward short-lived and energy-dependent fission product yields from neutron-induced fission." EPJ Web of Conferences 239 (2020): 03001. http://dx.doi.org/10.1051/epjconf/202023903001.

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Fission product yields (FPYs) are an important source of information that are used for basic and applied physics. They are essential observables to address questions relevant to nucleosynthesis in the cosmos that created the elements from iron to uranium, for example, in energy generating processes from fission recycling in binary neutron star mergers; resolving the reactor neutrino anomaly; decay heat release in nuclear reactors; and many national security applications. While new applications will require accurate energy-dependent FPY data over a broad set of incident neutron energies, the cu

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Estienne, Magali, Muriel Fallot, Lydie Giot, Loïc Le Meur, and Amanda Porta. "Recent advances in beta decay measurements." EPJ Nuclear Sciences & Technologies 4 (2018): 24. http://dx.doi.org/10.1051/epjn/2018034.

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Three observables of interest for present and future reactors depend on the β decay data of the fission products: the reactor decay heat, antineutrinos from reactors and delayed neutron emission. Concerning the decay heat, significant discrepancies still exist between summation calculations in − their two main ingredients: the decay data and the fission yields − performed using the most recent evaluated databases available. It has been recently shown that the associated uncertainties are dominated by the ones on the decay data. But the results subtantially differ taking into account or not the

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Shi, Xue-Ming, and Xian-Jue Peng. "Neutron transport-burnup code MCORGS and its application in fusion fission hybrid blanket conceptual research." International Journal of Modern Physics: Conference Series 44 (January 2016): 1660236. http://dx.doi.org/10.1142/s2010194516602362.

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Fusion science and technology has made progress in the last decades. However, commercialization of fusion reactors still faces challenges relating to higher fusion energy gain, irradiation-resistant material, and tritium self-sufficiency. Fusion Fission Hybrid Reactors (FFHR) can be introduced to accelerate the early application of fusion energy. Traditionally, FFHRs have been classified as either breeders or transmuters. Both need partition of plutonium from spent fuel, which will pose nuclear proliferation risks. A conceptual design of a Fusion Fission Hybrid Reactor for Energy (FFHR–E), whi

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Kinoshita, Motoyasu. "Restructuring of Nuclear Oxide Fuel under High Burnup Irradiation." Advances in Science and Technology 45 (October 2006): 1952–60. http://dx.doi.org/10.4028/www.scientific.net/ast.45.1952.

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The ceramics fuel of UO2, irradiated in power reactors, has restructuring at high burnup, around 70MWd/kgU, which is near in the scope of future fuel utilization with improving economy. The original grains are divided into sub-grains of 100 nm scale and segregation of fission gas (Xe, Kr) grows bubbles resulting in volumetric swelling of the fuel. This restructuring was investigated in the field of nuclear engineering of power reactor fuel industry. This presentation briefly provides observations of this restructuring and some of engineering consequences. In a mechanism study a new approach, c

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Reid, Jack, Greg Bailey, Edmund Cracknell, Mark Gilbert, and Lee Packer. "COMPARISON OF WASTE DUE TO IRRADIATED STEELS IN THE ESFR AND DEMO." EPJ Web of Conferences 247 (2021): 18002. http://dx.doi.org/10.1051/epjconf/202124718002.

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For either nuclear fusion or generation IV fission reactors to be viable as a commercial energy source the decommissioning and waste disposal solutions must be considered during the design. A multi-step simulation process combining Monte Carlo Neutron Transport simulations with inventory simulations have been performed to estimate the activation of steels in key reactor components of the European Sodium-cooled fast Reactor (ESFR). Waste classifications based on UK waste disposal regulations have been applied to the key components to estimate the expected masses of low level and intermediate le

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Shatat, Shaleh Raed, Ade Riusma Ariyana, and Devina Arifani. "STATE'S READINESS MOBILITY IN APPLYING NUCLEAR TECHNOLOGY AS ENERY DEVELOPMENT IN LEGAL PERSPECTIVE." Jurnal Pembaharuan Hukum 8, no. 2 (2021): 290. http://dx.doi.org/10.26532/jph.v8i2.16478.

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The states Nuclear Program is a program to build and utilize nuclear science and technology both in the non-energy sector and in the energy sector for peaceful purposes. Utilization of non-energy in Indonesia has developed quite advanced. The use of nuclear power in every countries covers various fields such as health, research and industry. Indonesia's readiness in implementing nuclear energy is carried out by ratifying international conventions, issuing laws, and issuing regulations from the Nuclear Energy Supervisory Agency, readiness in the field of infrastructure used to strengthen techno

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Hancox, R. "The Environmental Impact of Fusion Reactors." Energy & Environment 3, no. 1 (1992): 29–44. http://dx.doi.org/10.1177/0958305x9200300102.

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Fusion power, based on the nuclear fusion of light elements to yield a net gain of energy, has the potential to extend the world's resources in a way which is environmentally attractive. Nevertheless, the easiest route to fusion — the reaction between deuterium and tritium — involves hazards from the use of tritium and the neutron activation of the structural materials. These hazards have been considered on the basis of simple conceptual reactor designs, both in relation to normal operation and decommissioning and to potential accident situations. Results from several studies are reviewed and

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Groopman, Evan E., David G. Willingham, Alex P. Meshik, and Olga V. Pravdivtseva. "Discovery of fissionogenic Cs and Ba capture five years after Oklo reactor shutdown." Proceedings of the National Academy of Sciences 115, no. 35 (2018): 8676–81. http://dx.doi.org/10.1073/pnas.1807267115.

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Understanding the release and sequestration of specific radioactive signatures into the environment is of extreme importance for long-term nuclear waste storage and reactor accident mitigation. Recent accidents at the Fukushima and Chernobyl nuclear reactors released radioactive 137Cs and 134Cs into the environment, the former of which is still live today. We have studied the migration of fission products in the Oklo natural nuclear reactor using an isotope imaging capability, the NAval Ultra-Trace Isotope Laboratory’s Universal Spectrometer (NAUTILUS) at the US Naval Research Laboratory. In O

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Allen, T., H. Burlet, R. K. Nanstad, M. Samaras, and S. Ukai. "Advanced Structural Materials and Cladding." MRS Bulletin 34, no. 1 (2009): 20–27. http://dx.doi.org/10.1557/mrs2009.8.

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AbstractAdvanced nuclear energy systems, both fission- and fusion-based, aim to operate at higher temperatures and greater radiation exposure levels than experienced in current light water reactors. Additionally, they are envisioned to operate in coolants such as helium and sodium that allow for higher operating temperatures. Because of these unique environments, different requirements and challenges are presented for both structural materials and fuel cladding. For core and cladding applications in intermediate-temperature reactors (400–650°C), the primary candidates are 9–12Cr ferritic–marte

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Shen, Yaosong. "Burning high-level TRU waste in fusion fission reactors." International Journal of Modern Physics: Conference Series 44 (January 2016): 1660227. http://dx.doi.org/10.1142/s2010194516602271.

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Recently, the concept of actinide burning instead of a once-through fuel cycle for disposing spent nuclear fuel seems to get much more attention. A new method of burning high-level transuranic (TRU) waste combined with Thorium–Uranium (Th–U) fuel in the subcritical reactors driven by external fusion neutron sources is proposed in this paper. The thorium-based TRU fuel burns all of the long-lived actinides via a hard neutron spectrum while outputting power. A one-dimensional model of the reactor concept was built by means of the ONESN_BURN code with new data libraries. The numerical results inc

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Hutchinson, Harry. "Powering Down." Mechanical Engineering 125, no. 04 (2003): 46–48. http://dx.doi.org/10.1115/1.2003-apr-4.

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This article reviews that after a half century of safety testing for the nuclear industry, a key heat-transfer lab is losing its home. Columbia University’s Heat Transfer Research Facility has been the only place to go for key safety testing. Since the days of the Atoms for Peace program during the Eisenhower years, the lab has tested generations of nuclear reactor fuel assemblies. The lab’s clients over the years have included all the designers of pressurized water reactors in the United States and others from much of the world. The tests are primarily concerned with one small, but significan

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Schwenk-Ferrero, A. "German Spent Nuclear Fuel Legacy: Characteristics and High-Level Waste Management Issues." Science and Technology of Nuclear Installations 2013 (2013): 1–11. http://dx.doi.org/10.1155/2013/293792.

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Germany is phasing-out the utilization of nuclear energy until 2022. Currently, nine light water reactors of originally nineteen are still connected to the grid. All power plants generate high-level nuclear waste like spent uranium or mixed uranium-plutonium dioxide fuel which has to be properly managed. Moreover, vitrified high-level waste containing minor actinides, fission products, and traces of plutonium reprocessing loses produced by reprocessing facilities has to be disposed of. In the paper, the assessments of German spent fuel legacy (heavy metal content) and the nuclide composition o

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Rots, P. E. A., R. F. Mudde, H. E. A. Van Den Akker, T. H. J. J. Van Der Hagen, and H. Van Dam. "Fluidized bed nuclear fission reactor." Chemical Engineering Science 51, no. 11 (1996): 2763–68. http://dx.doi.org/10.1016/0009-2509(96)00149-2.

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Wagemans, J., L. Borms, A. Kochetkov, A. Krása, C. Van Grieken, and G. Vittiglio. "Nuclear instrumentation in VENUS-F." EPJ Web of Conferences 170 (2018): 04027. http://dx.doi.org/10.1051/epjconf/201817004027.

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VENUS-F is a fast zero power reactor with 30 wt% U fuel and Pb/Bi as a coolant simulator. Depending on the experimental configuration, various neutron spectra (fast, epithermal, and thermal islands) are present. This paper gives a review of the nuclear instrumentation that is applied for reactor control and in a large variety of physics experiments. Activation foils and fission chambers are used to measure spatial neutron flux profiles, spectrum indices, reactivity effects (with positive period and compensation method or the MSM method) and kinetic parameters (with the Rossi-alpha method). Fis

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Kulikov, Gennady G., Anatoly N. Shmelev, Vladimir A. Apse, and Evgeny G. Kulikov. "On a significant slowing-down of the kinetics of fast transient processes in a fast reactor." Nuclear Energy and Technology 6, no. 4 (2020): 295–98. http://dx.doi.org/10.3897/nucet.6.60379.

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The kinetics of nuclear reactors is determined by the average neutron lifetime. When the inserted reactivity is more than the effective delayed neutron fraction, the reactor kinetics becomes very rapid. It is possible to slow down the fast reactor kinetics by increasing the neutron lifetime. The authors consider the possibility of using the lead isotope, 208Pb, as a neutron reflector with specific properties in a lead-cooled fast reactor. To analyze the emerging effects in a reactor of this type, a point kinetics model was selected, which takes into account neutrons returning from the 208Pb re

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Merk, Bruno, Anna Detkina, Dzianis Litskevich, Seddon Atkinson, and Gregory Cartland-Glover. "The Interplay between Breeding and Thermal Feedback in a Molten Chlorine Fast Reactor." Energies 13, no. 7 (2020): 1609. http://dx.doi.org/10.3390/en13071609.

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The energy trilemma and UN SDG 7 form the key drivers for the future of all kinds of energy research. In nuclear technology, molten salt reactors are an interesting option, since they can offer a game-changing approach to deliver an attractive, highly sustainable option for a zero-carbon society by providing sufficient breeding for a self-sustained long-term operation based on spent nuclear fuel from existing reactors while being able to be controlled ideally by inherent processes. To achieve these goals, several basic challenges have already been identified and worked on; demonstration of suf

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Pomysukhina, Alina Ye, Yury P. Sukharev, and German N. Vlasichev. "Evaluation of the neutronic performance of a fast traveling wave reactor in the Th-U fuel cycle." Nuclear Energy and Technology 6, no. 2 (2020): 77–82. http://dx.doi.org/10.3897/nucet.6.54629.

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The possibility for all of the uranium or thorium fuel to be used nearly in full is expected in traveling wave reactors. A traveling wave reactor core with a fast neutron spectrum in a thorium-uranium cycle has been numerically simulated. The reactor core is shaped as a rectangular prism with a seed region arranged at one of its ends for the neutron fission wave formation. High-enriched uranium metal is used as the seed region fuel. Calculated power density dependences and concentrations of the nuclides involved with the transformation chain along the core at a number of time points have been

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Arslan, Alper Buğra, İlayda Yilmaz, Gizem Bakir, and Hüseyin Yapici. "Transmutations of Long-Lived and Medium-Lived Fission Products Extracted from CANDU and PWR Spent Fuels in an Accelerator-Driven System." Science and Technology of Nuclear Installations 2019 (October 20, 2019): 1–13. http://dx.doi.org/10.1155/2019/4930274.

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This study presents the time-dependent analyses of transmutations of long-lived fission products (LLFPs) and medium-lived fission products (MLFPs) occurring in thermal reactors in a conceptual helium gas-cooled accelerator-driven system (ADS). In accordance with this purpose, the CANDU-37 and PWR 15 × 15 spent fuels are separately considered. The ADS consists of LBE-spallation neutron target, subcritical fuel zone, and graphite reflector zone. While the considered ADS is fueled with the spent nuclear fuels extracted from each thermal reactor without the use of additional fuel, fission products

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