Authors

Click to increase image sizeClick to decrease image size Additional informationNotes on contributorsCharles W. BagnalCharles W. Bagnal Jr. (BS, nuclear engineering, Georgia Institute of Technology, 1980) is a consulting engineer at GRP Consulting, Inc., currently engaged in reactor physics methods development and nuclear engineering support services. He has been involved in nuclear reactor design analysis and software development for six years. His experience includes advanced light water reactor (LWR) and heavy water reactor designs, including extended burnup fuel cycles using gadolinia burnable poison.Gerard P. CavanaughGerard P. Cavanaugh (BS, physics, Massachusetts Institute of Technology, 1969; MS, 1970, and PhD, 1976, nuclear engineering, University of Illinois, Urbana-Champaign) worked from 1973 to 1975 in the Neutronics Physics Division at Oak Ridge National Laboratory. He is currently supervisor of radiation physics and criticality analysis at Combustion Engineering, Inc. (C-E). His primary technical interests are in the areas of radiation transport, stochastic sampling methodologies, and computer applications ranging from mainframes to personal computers.Robert P. HarrisRobert P. Harris (BS, 1974, and MS, 1975, nuclear engineering, and MS, 1984, metallurgy, Rensselaer Polytechnic Institute) has worked in the core design, safety analysis, and licensing of C-E pressurized water reactors since 1973. He is currently involved in the neutronic design of advanced burnable poisons and fuel assemblies. He consults in the areas of core fuel management, safety analysis, and startup physics testing.Regis A. MatzieRegis A. Matzie (BS, physics, U.S. Naval Academy, 1965; MS, 1971, and PhD, 1976, nuclear engineering, Stanford University) is currently the manager of analog plants in the nuclear engineering department at C-E. His current technical interests include advanced LWR designs, methods of improving fuel utilization and fuel cycle costs in current design LWRs, and alternate fuel cycles for advanced converter reactors.Laszlo B. TarkoLaszlo B. Tarko (BS, physics, University of Connecticut, 1980) is currently the lead engineer in the radiation physics group at C-E. His current technical interests include radiation transport, ex-core radiation physics, dose rates, energy deposition, and associated computer techniques.Howard OckenHoward Ocken (D. Eng., metallurgy, Yale University, 1966) is a project manager in the Nuclear Power Division of the Electric Power Research Institute. He has managed projects that addressed materials performance in nuclear core components. His current interests include materials aspects associated with reducing radiation fields, especially replacing cobalt sources and decontamination and preconditioning technology.Per Hedemann JensenPer Hedemann Jensen (BSc, electronic engineering, Technical University, Aarhus, Denmark, 1970) is a senior health physicist at Ris0 National Laboratory, where he is head of the Section for Applied Health Physics. He has been involved in studies of radiological consequences from hypothetical core-melt accidents at nuclear power plants. His current technical interest is experimental work on internal dosimetry problems.Ian J. HastingsIan J. Hastings (PhD, metallurgical science, University of Queensland, 1968) is head of the Fuel Properties and Behaviour Group in the Fuel Materials Branch at the Chalk River Nuclear Laboratories (CRNL) of Atomic Energy of Canada Limited. His current interests are in oxide fuel behavior under irradiation, particularly release of short-lived fission products under normal and accident conditions, and in fusion ceramics.Elio MizzanElio Mizzan (BA Sc, chemical engineering, University of Toronto, 1949) is a supervisor at the Fuel Materials Branch Hot Cell Facility at CRNL. His interests have been in the areas of postirradiation examination of reactor fuels and materials, particularly postdefect handling of spent U02 fuel.Alan M. RossAlan M. Ross (BSc, general, University of London, 1953) is a supervisor at the Recycle Fuel Fabrication Laboratories of the Fuel Materials Branch of CRNL. His interests include the fabrication, nondestructive assay, properties, irradiation behavior, and neutron radiography of current and advanced thermal reactor fuels.John R. KelmJohn R. Kelm is a research technician in the Fuel Materials Branch at CRNL. His research responsibility is the operation of a special project hot cell. His current interest is U02 oxidation and stress corrosion cracking.Real J. ChenierReal J. Chenier is a research technician in the Fuel Materials Branch at CRNL. His current research responsibility is operation of the postirradiation metallographic facilities.D. H. RoseD. H. Rose is a research technologist in the Fuel Properties and Behaviour Group of the Fuel Materials Branch at CRNL. His current responsibility is fabrication and operation of instrumented in-reactor experiments.J. NovakJ. Novak (BASc, engineering science, University of Toronto, 1974) is employed in Central Nuclear Services, Nuclear Generation Division of Ontario Hydro. Since 1976 he has been engaged in the areas of nuclear fuel production and development. His current technical interests include behavior of irradiated fuel in air, U02 powder characteristics, and fuel performance improvement.Claudio RonchiClaudio Ronchi (Dr. rer. nat. phys., State University, Milan, Italy, 1965) is a research officer at the Joint Research Centre (JRC) of the Commission of European Communities. After having worked in the research and development of advanced fuels for fast breeders, he is now engaged in reactor safety studies.Jacques van de LaarJacques van de Laar (Ingenieur Fysische Techniek, H.T.S., Heerlen, The Netherlands, 1974) works in thec mathematical modeling department of JRC-Karlsruhe. He is currently involved in the development and execution of computer programs for reactor fuel performance and safety analysis.Hubert BlankHubert Blank (PhD, metal physics, Technical University of Stuttgart, 1957), head of the Physics Division of the European Institute for Transuranium Elements, Karlsruhe, has directed the “Swelling of Advanced Fuels” project at this institute since 1973.Tetsuo FukasawaTetsuo Fukasawa (BS, 1976; MS, 1978; and Dr. Eng., 1981, nuclear engineering, Tohoku University) is a researcher in the Energy Research Laboratory (ERL), Hitachi, Ltd. He has specialized in the radiochemistry of actinide elements and is currently working in the field of low-level radioactive waste treatment and spent fuel reprocessing.Koichi ChinoKoichi Chino (BS, 1972, and MS, 1974, mechanical engineering, Tokyo Institute of Technology) is a researcher at ERL. His primary areas of interest are transport phenomena and radioactive waste management.Osamu KuriyamaOsamu Kuriyama (BS, 1973, and MS, 1975, Tohoku University) is a researcher at ERL. His current interests include the radioactive waste management and chemistry of nuclear waste.Fumio KawamuraFumio Kawamura (BS, chemical engineering, Gunma University,1970; MS, 1972, and Dr. Eng., 1976, Tohoku University) is a researcher at ERL where he is involved in radioactive waste management and reactor water chemistry.Hideo YusaHideo Yusa (BS, physics, Tohoku University, 1959; Dr. Eng., Osaka University, 1969) is a chief researcher at ERL. He is responsible for the research and development of radioactive waste management systems.Bernard L. CohenBernard L. Cohen (BS, Case Institute of Technology, 1944; MS, University of Pittsburgh, 1948; DSc, Carnegie Institute of Technology, 1950) did basic research on nuclear structure using accelerators at Oak Ridge National Laboratory from 1950 to 1958 and at the University of Pittsburgh until the mid-1970s. He then turned his research efforts to the environmental impacts of energy generation, including studies of radioactive waste, health effects of radiation, risk and risk aversion, radon problems, and reactor safety. He is a professor of physics at the University of Pittsburgh and a former director (1965 to 1978) of its Scaife Nuclear Laboratories.K. TasakaK. Tasaka (PhD, nuclear engineering, University of Tokyo, 1976) first worked in breeder reactor safety and fission product characteristics research for ten years and in light water reactor (LWR) safety research for nine years at the Japan Atomic Energy Research Institute (JAERI). He is the project leader of the Rig of Safety Assessment (ROSA) program, and his current interests include analysis of thermal-hydraulic behavior during a loss-of-coolant accident (LOCA) and an anticipated transient without scram in LWRs.M. SuzukiM. Suzuki (MS, mechanical engineering, Kyoto University, 1971) has worked for the ROSA program since 1974. His current interests include safety evaluation of an LWR.Y. AnodaY. Anoda (PhD, mechanical engineering, University of Tokyo, 1979) is a research engineer for the ROSA program. His current interests include two-phase flow during a LOCA.Y. KoizumiY. Koizumi (PhD, mechanical engineering, University of Tokyo, 1977) is a research engineer for the ROSA program. His current interests include analysis of thermal-hydraulic behavior during a LOCA with emphasis on two-phase flow characteristics and heat transfer.T. YonomotoT. Yonomoto (MS, nuclear engineering, University of Osaka, 1982) is a research engineer for the ROSA program. His current interests include analysis of thermal-hydraulic behavior during a LOCA.H. KumamaruH. Kumamaru (PhD, nuclear engineering, University of Tokyo, 1980) is a research engineer for the ROSA program. His current interests include core heat transfer under LOCA conditions.H. NakamuraH. Nakamura (MS, crystalline material engineering, Nagoya University, 1981) is a research engineer for the ROSA program. His current interests include analysis of thermal-hydraulic behavior during a LOCA.M. ShibaM. Shiba (MS, mechanical engineering, Waseda University, 1959) is the general manager of Reactor Safety Laboratory 1 at JAERI. He has worked for 22 years at JAERI in the field of reactor engineering and safety and is currently responsible for simulated LOCA experiments.Genichi MatsumotoGenichi Matsumoto (BS, physics, Tokyo University, 1946) has been an associate professor of nuclear engineering at Nagoya University from 1963 to the present, where he is responsible for research and education in nuclear reactor engineering. He worked as a member of the Scientific Research Institute of Tokyo following his graduation from Tokyo University, and from 1950 to 1963, he served on the technical staff of the Research Reactor Operation Division of the Japan Atomic Energy Research Institute. His current research field includes nuclear safety, neutron radiography (especially neutron television technology), and heat pipe technology.Soichi DoiSoichi Doi (BS, 1976, and MS, 1978, nuclear engineering, Nagoya University) has been employed by the Mitsubishi Atomic Power Industry Co. since 1978, where he is responsible for the nuclear fuel engineering of light water reactors.Kohei OhkuboKohei Ohkubo (BS, mechanical engineering, Aichi Institute of Technology, 1975) is a staff member of Nagoya University.Yasushi IkedaYasushi Ikeda (BS, physics, 1963, and PhD, nuclear engineering, 1982, Nagoya University) has been an assistant staff member of Nagoya University from 1964 to the present. He has investigated thermodynamics of nuclear materials using mass spectrometric technology; neutron radiography technology is also included in his research interests.Günther HesselGünther Hessel [BS, physics, Technical University Dresden, German Democratic Republic (GDR), 1970] is a research scientist at the Central Institute of Nuclear Research (CIN), Rossendorf. He is involved in experimental investigations and developments for technical diagnosis, especially at nuclear power plants.Hans-Erich KöppenHans-Erich Köppen (BS, computer science, Technical University Dresden, 1973) is a research scientist at the CIN. His area of expertise is microprocessor hard- and software and the construction of autonomously working monitors.Peter LiewersPeter Liewers (BS, physics, University of Halle, GDR, 1957; PhD, physics, University of Leipzig, GDR, 1962) is the scientific leader of the group for reactor diagnostics at the CIN. His interests and activities have shifted from reactor physics to technical diagnostics.Peter SchumannPeter Schumann (BS, nuclear engineering, Technical University Dresden, 1963; PhD, physics, Bergakademie Freiberg, GDR, 1970) is a staff scientist at the CIN where he is concerned with digital signal processing and computer software. Formerly he worked in the field of in-core measuring techniques and neutron spectrometryFrank-Peter WeiβFrank-Peter Weiβ (BS, physics, Technical University Dresden, 1973) is a research scientist in the group for technical diagnostics at the CIN. His current interest is the application of statistical pattern recognition to technical diagnostics.

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Click to increase image sizeClick to decrease image size Additional informationNotes on contributorsY. OhsawaY. Ohsawa (PhD, Rikkyo University) is a member of the reactor control and instrumentation division staff of Hitachi Atomic Energy Research Laboratory. His interests include plant dynamics, and control and reactor diagnosis.K. KatoK. Kato (center) (ME, nuclear engineering, Tokyo University, 1969) is a member of the reactor control and instrumentation division staff of Hitachi Atomic Energy Research Laboratory, engaged in development of a reactor anomaly system.R. OyamadaR. Oyamada (BE, Ibaraki University, 1959) of the Project Engineering Section staff of Japan Materials Testing Reactor has, in recent years, been engaged in nuclear calculation to choose the core (fuel element and capsules) configuration of the JMTR.E. D. ClaytonE. D. Clayton (PhD, physics, University of Oregon, 1952) is Manager of Criticality Research at the Battelle-Pacific Northwest Laboratories, and research associate professor in the University of Washington’s Department of Nuclear Engineering. Past chairman of the Nuclear Criticality Safety Division of the American Nuclear Society, a pioneer in criticality studies with plutonium, and since its inception in 1961, director of the Plutonium Critical Mass Laboratory of PNL, Clayton is currently chairman of work groups 10 and 12 within Subcommittee ANS-8. His current technical interests include most aspects of criticality measurements and studies.Karl HornyikKarl Hornyik (PhD, nuclear engineering, University of Illinois, 1965) is assistant professor of nuclear engineering at Oregon State University. He has been working with Portland General Electric on various problems concerning nuclear power plant siting and plant safety.John E. GrundJohn E. Grund (MS, nuclear engineering, North Carolina State University, 1957) is chief nuclear engineer for Portland General Electric Company. His areas of interest are nuclear safety and licensing. He has previously worked at the NRTS in Idaho on the SPERT project in the area of reactor kinetics.D. GuarinoD. Guarino (“Perito Tecnico Industriale,” Industrial Technical Institute of Naples, 1959) joined CNEN in 1960 and has worked primarily in the field of uranium compounds chemical analysis. He is presently engaged in the development of LWR fuel elements thermal hydraulics.V. MarinelliV. Marinelli (center) (PhD, nuclear engineering, Politecnico di Torino, 1967), at CNEN since 1969, is leader of thermal hydraulic studies at Gruppo Progettazione e Sperimentazione of CNEN Plutonium Program. His main areas of interest are the development of LWR computer codes as well as the planning and analysis of experimental tests.L. PastoriL. Pastori (“Perito Tecnico Industriale,” Industrial Technical Institute for Nuclear Energy Enrico Fermi, Rome, 1962), at CNEN since 1962, is expert in computer software problems and is presently engaged in studies of core simulator computer codes.M. W. MahoneyM. W. Mahoney (BS, physical metallurgy, University of California, Berkeley) is currently enrolled in an MS program at UCLA. He is a member of the ASME Subcommittee on Elevated Temperature Fatigue and Fracture. He has previously worked in nuclear reactor materials development and is currently investigating fracture, creep, and stress corrosion at elevated temperatures in a variety of materials. The current research interests ofN. E. PatonN. E. Paton (MS, metallurgical engineering, University of Aukland, New Zealand; PhD, Massachusetts Institute of Technology) include stress corrosion, fracture, and mechanical properties of various materials.J. C. WoodJ. C. Wood (MSc, University of Bristol, 1967) has been a member of the Fuels and Materials Division at Atomic Energy of Canada Limited, Chalk River Nuclear Laboratories, since leaving the Central Electricity Generating Board in 1969. His present interests include fuel engineering and stress corrosion cracking.L. D. PhilippL. D. Philipp (center) (BSEE, University of Colorado, 1963; MSEE, University of Washington, 1967; PhD, electrical engineering, University of New Mexico, 1971) has seven years experience in reactor instrumentation at Hanford where he has technical leadership responsibility for programs involving neutron flux instrumentation and insulator research and development.L. D. MuhlesteinL. D. Muhlestein (PhD, physics, Iowa State University, 1966; associate professor of physics, University of Missouri-Columbia, 1966-1973) is presently manager of the refueling and plant programs at Hanford Engineering Development Laboratory.M. R. WoodM. R. Wood (BSEE, University of Washington, 1947), presently a system engineer in the Westinghouse Hanford FFTF project, has worked in the nuclear reactor instrument field for 22 years.D. P. BrownDonald P. Brown (MSEE, University of Washington, 1965), an advanced engineer with Westinghouse Hanford Company, has 16 years of experience in nuclear instrumentation. His recent efforts have been aimed at the development of thermal- and fast-neutron detectors for in-core application.W. G. SpearWard G. Spear (MSEE, University of Idaho, 1960), presently Manager of Reactor Instrument Development at Westinghouse Hanford Company, has been working in the nuclear field for 22 years, with emphasis on reactor instrumentation development for the past 14 years.

This white paper provides an overview and status report of the thermal-hydraulic nuclear research and development, both experimental and computational, conducted predominantly at Argonne National Laboratory. Argonne from the early 1970s through the early 1990s was the Department of Energy's (DOE's) lead lab for thermal-hydraulic development of Liquid Metal Reactors (LMRs). During the 1970s and into the mid-1980s, Argonne conducted thermal-hydraulic studies and experiments on individual reactor components supporting the Experimental Breeder Reactor-II (EBR-II), Fast Flux Test Facility (FFTF), and the Clinch River Breeder Reactor (CRBR). From the mid-1980s and into the early 1990s, Argonne conducted studies on phenomena related to forced- and natural-convection thermal buoyancy in complete in-vessel models of the General Electric (GE) Prototype Reactor Inherently Safe Module (PRISM) and Rockwell International (RI) Sodium Advanced Fast Reactor (SAFR). These two reactor initiatives involved Argonne working closely with U.S. industry and DOE. This paper describes the very important impact of thermal hydraulics dominated by thermal buoyancy forces on reactor global operation and on the behavior/performance of individual components during postulated off-normal accident events with low flow. Utilizing Argonne's LMR expertise and design knowledge is vital to the further development of safe, reliable, and high-performance LMRs. Argonne believes there remains an important need for continued research and development on thermal-hydraulic design in support of DOE's and the international community's renewed thrust for developing and demonstrating the Global Nuclear Energy Partnership (GNEP) reactor(s) and the associated Argonne Liquid Metal-Advanced Burner Reactor (LM-ABR). This white paper highlights that further understanding is needed regarding reactor design under coolant low-flow events. These safety-related events are associated with the transition from normal high-flow operation to natural circulation. Low-flow coolant events are the most difficult to design for because they involve the most complex thermal-hydraulic behavior induced by the dominance of thermal-buoyancy forces acting on the coolants. Such behavior can cause multiple-component flow interaction phenomena, which are not adequately understood or appreciated by reactor designers as to their impact on reactor performance and safety. Since the early 1990s, when DOE canceled the U.S. Liquid Metal Fast Breeder Reactor (LMFBR) program, little has been done experimentally to further understand the importance of the complex thermal-buoyancy phenomena and their impact on reactor design or to improve the ability of three-dimensional (3-D) transient computational fluid dynamics (CFD) and structures codes to model the phenomena. An improved experimental data base and the associated improved validated codes would provide needed design tools to the reactor community. The improved codes would also facilitate scale-up from small-scale testing to prototype size and would facilitate comparing performance of one reactor/component design with another. The codes would also have relevance to the design and safety of water-cooled reactors. To accomplish the preceding, it is proposed to establish a national GNEP-LMR research and development center at Argonne having as its foundation state-of-art science-based infrastructure consisting of: (a) thermal-hydraulic experimental capabilities for conducting both water and sodium testing of individual reactor components and complete reactor in-vessel models and (b) a computational modeling development and validation capability that is strongly interfaced with the experimental facilities. The proposed center would greatly advance capabilities for reactor development by establishing the validity of high-fidelity (i.e., close to first principles) models and tools. Such tools could be used directly for reactor design or for qualifying/tuning of lower-fidelity models, which now require costly experimental qualification for each different type of design application. Capabilities required to establish and operate this center are found primarily in Argonne's Nuclear Engineering and Mathematics and Computer Science Divisions. Funding for the center would be sought from DOE-NE (GNEP/Advanced Burner Reactor and Generation IV programs), DOE-SC/ASCR, and the commercial nuclear industry. Having the above experimental and modeling capabilities at Argonne would constitute a national/international center of excellence for conducting the research and engineering and design tool development needed to support the DOE GNEP/ LM-ABR initiative in developing safe, high-performance reactors.

This is the Final report for the DOE Match Grant (DE-FG02-99NE38163) awarded to the Nuclear and Radiological Engineering (NRE) Department, University of Florida, for the period of September 1999 to January 2002. This grant has been instrumental for maintaining high-quality graduate and undergraduate education at the NRE department. The grant has been used for supporting student entry and retention and for upgrading nuclear educational facilities, nuclear instrumentation, computer facilities, and computer codes to better enable the incorporation of experimental experiences and computer simulations related to advanced light water fission reactor engineering and other advanced reactor concepts into the nuclear engineering course curricula.

Although there are 430 govemment and private universities in Japan, only a limited number of them have departments associated with nuclear science education. Moreover, mainly because of financial pressures, this association is often limited to government universities. Nuclear engineering departments are incorporated with only seven of the larger universities, and there are three institutes with nuclear reactors. In these facilities, education in reactor physics, radiation measurements, electromagnetic and material sciences, are conducted. In terms of radiation safety and radiological health physics, tem radioisotope centers and seven radiochemistry laboratories in universities play an important role. Virtually all of the financial support for nuclear education comes from the Japanese Govemment via the Ministry of Education, Science, and Culture. These are supplemented via private and corporate grants to various university faculty members. In addition to these universities, and private/corporate research institutes, The Japan Atomic Energy Research Institute teaches a short lecture course in nuclear science on a regular basis.

X-Ray SpectrometryVolume 28, Issue 4 p. 207-208 Guest EditorialFree Access Guest Editorial Jorge E. Fernández, Jorge E. Fernández INFM, Department of Energetic, Nuclear and environmental control Engineering, University of BolognaSearch for more papers by this author Jorge E. Fernández, Jorge E. Fernández INFM, Department of Energetic, Nuclear and environmental control Engineering, University of BolognaSearch for more papers by this author First published: 27 September 1999 https://doi.org/10.1002/(SICI)1097-4539(199907/08)28:4<207::AID-XRS372>3.0.CO;2-8AboutPDF ToolsRequest permissionExport citationAdd to favoritesTrack citation ShareShare Give accessShare full text accessShare full-text accessPlease review our Terms and Conditions of Use and check box below to share full-text version of article.I have read and accept the Wiley Online Library Terms and Conditions of UseShareable LinkUse the link below to share a full-text version of this article with your friends and colleagues. Learn more.Copy URL Share a linkShare onFacebookTwitterLinked InRedditWechat No abstract is available for this article. Volume28, Issue4Special Issue: Papers from the European Conference on EDXRS, Bologna, Italy, 7–12 June 1998July/August 1999Pages 207-208 RelatedInformation

The Lawrence Livermore National Laboratory (LLNL) Nuclear Forensics Summer Program is designed to give both undergraduate and graduate students an opportunity to come to LLNL for 8–10 weeks for a hands-on research experience. Students conduct research under the supervision of a staff scientist, attend a weekly lecture series, interact with other students, and present their work in poster format at the end of the program. Students also have the opportunity to meet staff scientists one-on-one, participate in LLNL facility tours (e.g., the National Ignition Facility and Center for Accelerator Mass Spectrometry) to gain a better understanding of the multi-disciplinary, on going science at LLNL. Currently called the Nuclear Forensics Summer Program, this program began 13 years ago as the Actinide Sciences Summer Program. The program is run within the Glenn T. Seaborg Institute in the Physical and Life Sciences Directorate at LLNL. The goal of the Nuclear Forensics Summer Program is to facilitate the training of the next generation of nuclear scientists and engineers to solve critical national security problems in the field of nuclear forensics and have the student experience conducting research at the Lab. We select students who are majoring in physics, chemistry, geology, mathematics, nuclear engineering, chemical engineering and environmental sciences. Students engage in research projects in the disciplines of actinide chemistry, radiochemistry, isotopic analysis, computational analysis, radiation detection, and nuclear engineering in order to strengthen the “pipeline” for future scientific disciplines critical to DHS (DNDO), NNSA.

"Introduction to Nuclear Physics." Nuclear Science and Engineering, 29(2), pp. 312–313 Additional informationNotes on contributorsDavid L. HetrickDr. Hetrick is Professor of Nuclear Engineering at the University of Arizona. His current interests in graduate teaching and research are nuclear reactor dynamics and safety. He was a reactor physicist at Atomics International for nine years, and has taught physics at Rensselaer Polytechnic Institute and San Fernando Valley State College. He received his PhD in theoretical physics at UCLA in 1954.

Nuclear chemical engineering. (Part of the McGraw‐Hill Series in Nuclear Engineering) Manson Benedict, Professor, Nuclear Engineering, M.I.T., and Thomas H. Pigford, Associote Professor, Nuclear Engineering, M.I.T. McGraw Hill Book Company, Inc., New York (1957). 594 pages. $9.50.

After two major nuclear power plant accidents in Chernobyl (1986) and Fukushima (2011), one of the main requirements for the nuclear power engineering is the safety of the nuclear reactors in operation, as well as new nuclear power plants of the fourth generation, which are being developed now. One of such requirements is presence of the so-called “inherent safety” mechanism, which renders the uncontrolled reactor runaway impossible under any conditions, moreover, the implementation of such a mechanism should be ensured on the level of physical principles embedded in the reactor design. Another important problem of the nuclear power engineering is the need of the transition to the large-scale use of the fast-neutron breeder reactors, with which it would be possible to set up expanded reproduction of the nuclear fuel and by that means solve the problem of supplying humanity with relatively cheap energy for thousands of years. Moreover, at present an unresolved problem is the disposal of spent nuclear fuel containing radioactive nuclides with long half-lives, which presents a long-term danger to the ecology. One of the promising conceptions of the fast-neutron breeder reactor, which can, in the case of successful implementation, partially or even entirely solve the problems of the nuclear power engineering mentioned above, is the reactor that operates in the nuclear burning wave mode, which is also known as “Traveling wave reactor”, CANDLE and by some other names. This paper presents a short review of the main theoretical approaches used for description of such a physical phenomenon as slow nuclear burning (deflagration) wave in the neutron multiplication medium initially composed of the fertile material 238U or 232Th. A comparative analysis of the possibilities of different mathematical models for describing this phenomenon is performed, both for those based on the deterministic approach (i.e. solving neutron transport equations) and for models that use Monte Carlo methods. The main merits of the fast breeder reactor, working in the nuclear burning wave mode, and problems related to the practical realization of the considered concept are discussed.

The Current Trends of Deep Learning in Autonomous Vehicles: A Review by Raymond Ning Huang 1 , Jing Ren2,* , Hossam A. Gabbar 3 1 Department of Mechanical Engineering, University of Toronto, Toronto, M5S 1A4, Canada2 Department of Electrical and Computer Engineering, Ontario Tech University, Oshawa, L1H 7K4, Canada3 Department of Energy and Nuclear Engineering,