Relevant bibliographies by topics / Reactor Radiation Division

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Academic literature on the topic 'Reactor Radiation Division'

Author: Grafiati
Published: 4 June 2021
Last updated: 29 July 2025

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Journal articles on the topic "Reactor Radiation Division"

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Fradin, Frank. "Up Close: Materials Science at Argonne National Laboratory." MRS Bulletin 11, no. 5 (1986): 34–35. http://dx.doi.org/10.1557/s0883769400054488.

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Basic and applied materials research at Argonne National Laboratory (ANL) is conducted by the Materials Science Division (MSD) and the Materials and Components Technology Division (MCT). Of the $30 million annual budget, $23 million comes from the U.S. Department of Energy (DOE) that funds Basic Energy Sciences (BES)-Materials Sciences, Reactor Development, Fusion Energy, Fossil Energy, and Conservation Technology. Another $5 million of the $30 million budget comes from the Nuclear Regulatory Commission and the remaining $2 million is from the Department of Defense.Representative projects in f
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Hardiyanto, Moh. "Approximation in Quantum Quadrupole at Juergen Model for Nuclear Reactor Control Rod Blade Based on \ce {Th_xDUO2} Nano Materials." Omega: Jurnal Fisika dan Pendidikan Fisika 4, no. 1 (2018): 7. http://dx.doi.org/10.31758/omegajphysphyseduc.v4i1.7.

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The functional of a multi purpose research nuclear reactor control rod blade nuclear reactor is stabilized and controlling devices for nuclear chain reactions, the existing of Cerenkov's radiation impact and thermal neutron flux in reactor chamber. This research was conducted in Large Hadron Collider (LHC) - Muon Hadron Division at CERN, Lyon - France under International Research between Canadian Deuterium Uranium (CANDU) - Nuclear Reactor and Betha Group Section for sub-particles for nanomaterial. Using Juergen Model with quantum states approaching and testing by Muon-Hadron Stirrer equipment
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Akashi, Makoto. "Role of radiation emergency medicine: historical view—a perspective on the past, present, and future." Journal of Radiation Research 65, Supplement_1 (2024): i24—i31. https://doi.org/10.1093/jrr/rrae037.

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Abstract The more science progresses, the more life and society change. Medicine also changes with the times and the culture. This is also true for radiation emergency medicine, which includes dose-assessment leading to diagnosis, treatment, medical follow-up and prognosis of persons who have developed acute injury or illness due to radioactive contamination or radiation exposure. Before the report of X-rays by Roentgen, there was evidence that X-rays had been emitted from the electrically excited Crookes tube and that skin injury had been caused by the X-rays. Thus, the history of radiation a
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Williams, Dennis K., and Trevor G. Seipp. "Considerations in the Design and Analysis of an ASME Section VIII, Div. 2 Reactor Support Skirt." Journal of Pressure Vessel Technology 129, no. 2 (2007): 316–22. http://dx.doi.org/10.1115/1.2722301.

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This paper describes the considerations employed in the finite element analysis of a relatively “short” support skirt on a hydrocarbon reactor vessel. The analysis is accomplished in accordance with ASME B&PV Code, Section VIII, Division 2 alternate rules in conjunction with the guidelines outlined in WRC Bulletin 429. This provides a sound basis for the classification of the calculated stress intensities. The support skirt is capable of sustaining the deadweight load in addition to resisting the effects of thermal displacements, wind loadings, overturning moments from external piping load
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Azarov, S., V. Sydorenko, and O. Zadunaj. "EVALUATION OF EXPLOSIVE RISK IN THE PROCESS STORAGE OF WELDED NUCLEAR FUEL." Bulletin of Lviv State University of Life Safety, no. 18 (December 31, 2018): 81–87. http://dx.doi.org/10.32447/20784643.18.2018.08.

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At present, at the Chornobyl NPP, the main building of the general-purpose storage system for spent nuclear fuel is the "wet type" storage of spent nuclear fuel number 1 (SNF-1), designed for receiving and storing spent nuclear fuel. In the light of the post-Fukushima events, the task of increasing the explosion and fire safety is a priority direction of the Chornobyl NPP operation. SNF-1 should meet the current requirements of safety regulatory documents, both under normal operating conditions and during emergency situations. Among the emergencies that are likely to occur in the SNF-1 reposit
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Jo, Seungjae, Sanghwan Kim, and Jaehyun Cho. "A Fast Variance Reduction Technique for Efficient Radiation Shielding Calculations in Nuclear Reactors." Energies 17, no. 22 (2024): 5695. http://dx.doi.org/10.3390/en17225695.

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The increasing demand for cleaner and more sustainable energy sources has sparked significant interest in small modular reactors (SMRs). Due to their compact and modular design, SMRs pose unique challenges in radiation shielding, requiring a more refined approach. This study focuses on developing a new variance reduction technique (VRT) for radiation shielding analysis, specifically tailored for SMRs, to address the limitations of traditional methods such as surface source write/surface source read (SSW/SSR). The proposed VRT supports multi-threading and enhances computational efficiency by re
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Soumyakanti, Adhikari, Joshi Ravi, and Mukherjee Tulsi. "Radiation chemistry in microemulsion." Journal of Indian Chemical Society Vol. 78, October-December 2001 (2001): 573–77. https://doi.org/10.5281/zenodo.5883800.

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Radiation Chemistry &amp; Chemical Dynamics Division, Bhabha Atomic Research Centre, Mumbai-400 085, India <em>Eemail</em>: mukherji@magnum.barc.ernet.in&nbsp; <em>Fax</em> : 91-22-5505151 <em>Manuscript received 5 December 2000</em> Radiation chemistry can be used to study reactions of free radicals not only in homogeneous medium but also in micro-heterogeneous medium, microemulsion being typical example of this type of medium. This article intends to summarize some radiation chemical studies in microemulsion using pulse radiolysis as a tool. Attempt has been made to show that the reaction an
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Soumyakanti, Adhikari, Joshi Ravi, and Mukherjee Tulsi. "Radiation chemistry in microemulsion." Journal of Indian Chemical Society Vol. 78, Oct-Dec 2001 (2001): 573–77. https://doi.org/10.5281/zenodo.5910191.

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Radiation Chemistry &amp; Chemical Dynamics Division, Bhabha Atomic Research Centre, Mumbai-400 085, India <em>E mail</em>: mukherji@magnum.barc.ernet.in&nbsp; &nbsp; &nbsp; &nbsp;<em>Fax</em> : 91-22-5505151 <em>Manuscript received 5 December 2000</em> Radiation chemistry can be used to study reactions of free radicals not only in homogeneous medium but also in micro-heterogeneous medium, microemulsion being typical example of this type of medium. This article intends to summarize some radiation chemical studies in miuoemulsion using pulse radiolysis as a tool. Attempt has been made to show t
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Dipak, Kumar Palit. "Studies of ultrafast reaction dynamics in the excited states of molecules in solutionΨ". Journal of Indian Chemical Society Vol. 79, Jan 2002 (2002): 1–13. https://doi.org/10.5281/zenodo.5840027.

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Radiation Chemistry &amp; Chemical Dynamics Division, Bhabha Atomic Research Centre, Mumbai-400 085, India <em>E-mail </em>dkpalit@apsara.barc.ernet.in&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp;&nbsp; <em>Fax : </em>91-22-5505151 In the course of a photochemical reaction, reactants are converted into products with the possibility of various transition states and transient intermediates on the reaction pathway. The properties of these transient intermediate species are central to the reaction and determine its ra
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Jovanovic, Goran, Nikola Buric, and Milos Tijanic. "Stimulation of mucoperiostal slice epithelization by small power laser after the primary plastic of oroantral communication." Medical review 63, no. 3-4 (2010): 188–93. http://dx.doi.org/10.2298/mpns1004188j.

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Introduction The oroantral communication is a pathologic communication between the oral cavity and maxillary sinus. It originates with extraction of the upper lateral teeth. Primary plastics communication, which is more extensive than 5 mm has been unsuccessful in 16%. Small power lasers have positive reaction on wounds healing. The aim of this work was to determine the lasers effects on slice epithelization after the plastics more extensive than 5 mm. Material and methods The experimental research was done on dogs with extraction of the upper second premolars on both sides, and formed oroantr
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Books on the topic "Reactor Radiation Division"

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Freeman, Richard R., James A. King, and Gregory P. Lafyatis. Electromagnetic Radiation. Oxford University Press, 2019. http://dx.doi.org/10.1093/oso/9780198726500.001.0001.

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Electromagnetic Radiation is a graduate level book on classical electrodynamics with a strong emphasis on radiation. This book is meant to quickly and efficiently introduce students to the electromagnetic radiation science essential to a practicing physicist. While a major focus is on light and its interactions, topics in radio frequency radiation, x-rays, and beyond are also treated. Special emphasis is placed on applications, with many exercises and homework problems. The format of the book is designed to convey the basic concepts of a topic in the main central text in the book in a mathemat
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Conference papers on the topic "Reactor Radiation Division"

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Scott, Peter, Aniket Patankar, Ziyao Wu, Henrik Haussmann, and Ahmed Ghoniem. "High-Fidelity Thermomechanical Modeling of a Novel Indirectly Irradiated Reactor for Solar Thermochemical Fuel Production." In ASME 2024 18th International Conference on Energy Sustainability collocated with the ASME 2024 Heat Transfer Summer Conference and the ASME 2024 Fluids Engineering Division Summer Meeting. American Society of Mechanical Engineers, 2024. http://dx.doi.org/10.1115/es2024-130505.

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Abstract We have previously proposed the Reactor Train System (RTS) for efficient solar thermochemical hydrogen (STCH) production, which utilizes a counter-flow radiative heat exchange system with moving reactors. RTS reactors are heated with indirect infrared radiation, which is markedly different from current experimentally demonstrated solar receiver-reactors. In this work we present a design study of a prototype reactor, including a high-fidelity heat transfer model with component dimensions informed by mechanical stress modeling. This model was used to subject different variants of the re
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Dupont, Mathieu. "Health Physics Research Reactor Criticality Accident Alarm System Benchmark Overview [Slides]." In 14th International Conference on Radiation Shielding and 21st Topical Meeting of the Radiation Protection and Shielding Division (ICRS 14/RPSD 2022), Seattle, WA (United States), 25-29 Sep 2022. US DOE, 2022. http://dx.doi.org/10.2172/1924056.

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Bullard, Tim, Miles Greiner, Matt Dennis, Samuel Bays, and Ruth Weiner. "Thermal Analysis of a Proposed Transport Cask for Three Advanced Burner Reactor Used Fuel Assemblies." In ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/pvp2010-26138.

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Preliminary studies of used fuel generated in the US Department of Energy’s Advanced Fuel Cycle Initiative have indicated that current used fuel transport casks may be insufficient for the transportation of said fuel. This work considers transport of three 5-year-cooled oxide Advanced Burner Reactor used fuel assemblies with a burn-up of 160 MWD/kg. A transport cask designed to carry these assemblies is proposed. This design employs a 7-cm-thick lead gamma shield and a 20-cm-thick NS-4-FR composite neutron shield. The temperature profile within the cask, from its center to its exterior surface
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Dickson, Terry, Eric Focht, and Mark Kirk. "Review of Proposed Methodology for Risk-Informed Relaxation to ASME Section XI: Appendix G." In ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/pvp2010-25010.

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The current regulations, as set forth by the United States Nuclear Regulatory Commission (NRC), to insure that light-water nuclear reactor pressure vessels (RPVs) maintain their structural integrity when subjected to planned normal reactor startup (heat-up) and shut-down (cool-down) transients are specified in Appendix G to 10 CFR Part 50, which incorporates by reference Appendix G to Section XI of the American Society of Mechanical Engineers (ASME) Code. The technical basis for these regulations are now recognized by the technical community as being conservative and some plants are finding it
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Chang, Shih-Jung. "A Fracture Probability Integral for Pressure Vessel Life Estimate and Accident Analysis." In ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/pvp2010-25968.

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A multiple integral representation has been developed to analytically model the probability of failure of reactor vessel. The probability of fracture is a basic methodology for projecting for the life of a new vessel as well as to estimate the remaining life of an existing vessel. The integral representation for the probability of fracture calculation is based on the number count of critical cracks across the whole section of a vessel, based on a given calibrated crack distribution function, obtained by experimental examination of the vessel cross section. Multiple integral is implemented beca
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Yuan, Haomin, Dezhi Dai, and Yu-Hsiang Lan. "Coupled Flow and Thermal Radiation Simulation for Molten Salt Flow in Random Pebble Bed." In ASME 2024 Heat Transfer Summer Conference collocated with the ASME 2024 Fluids Engineering Division Summer Meeting and the ASME 2024 18th International Conference on Energy Sustainability. American Society of Mechanical Engineers, 2024. http://dx.doi.org/10.1115/ht2024-121105.

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Abstract The design of a pebble bed core cooled by molten salt represents one of the Gen IV nuclear reactor concepts. This design lays the foundation for the Fluoride High-temperature Reactor (FHR), which harnesses the advantages of both pebble bed and molten salt cooling systems. While thermal radiation plays a negligible role in heat transfer under forced convection, it becomes a significant factor under mixed convection and natural convection conditions, profoundly altering the temperature profile. In our earlier investigation of pebble bed behavior, the influence of thermal radiation was n
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Moran, Traci L., Pradeep Ramuhalli, Allan F. Pardini, Steven R. Doctor, and Michael T. Anderson. "Evaluating the Use of Ultrasonic Testing in Lieu of Radiography for Inspecting Welds in Nuclear Power Plants." In ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/pvp2010-25353.

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The nuclear power industry has recently proposed using ultrasonic testing (UT) in lieu of radiographic testing (RT) on new construction welds and on the repairs of operating reactor component welds. Advantages of UT include a reduction in inspection time, costs, and plant personnel exposure to radiation fields. The replacement of one nondestructive testing method with another, however, requires a detailed analysis of the capabilities of the replacement method as compared to the existing method. Capabilities of interest in this context include detection reliability, false call rates, flaw chara
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Killian, Douglas E. "Design of a Weld Overlay for a Large Bore Pipe Nozzle to Optimize Residual Stress." In ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/pvp2010-26100.

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Full Structural Weld Overlays (FSWOL) have been used successfully in the nuclear power industry for a number of years to mitigate and repair small (4″) to medium (10″) bore welded piping components susceptible to primary water stress corrosion cracking (PWSCC). Mitigation is provided by the creation of compressive residual stress on the inside surface of the pipe as layers of weld overlay are deposited over the outside surface of the pipe. ASME Code Case N-740-2 requires that these overlay designs provide adequate structural integrity considering the growth of postulated 75% through-wall insid
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Lidbury, David, Elisabeth Keim, Bernard Marini, Lorenzo Malerba, and Asmahana Zeghadi. "Overview of RPV Sub-Project of PERFORM 60." In ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/pvp2010-25980.

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PERFORM 60 (prediction of the effects of radiation for reactor pressure vessel and in-core materials using multi-scale modelling - 60 years foreseen plant lifetime) is a 48-month project of the 7th Framework of the European Atomic Energy Community (EURATOM) being carried out under the auspices of the Directorate General Research, Technology and Development (DG.RTD) of the European Commission. Launched in March 2009, and building on the achievements of PERFECT, a EURATOM 6th Framework project, PERFORM 60 has as its main objective the development of multi-scale modelling tools integrated onto a
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Chalasani, N. R., and Miles Greiner. "Benchmark of Computational Fluid Dynamics Simulations Using Temperatures Measured Within Enclosed Vertical and Horizontal Array of Heater Rods." In ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/pvp2010-25803.

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Experiments and computational fluid dynamics/radiation heat transfer simulations of an 8×8 array of heated rods within an aluminum enclosure are performed with nitrogen and helium as backfill gases in both horizontal and vertical orientations. This configuration represents a region inside the channel of a boiling water reactor fuel assembly between two consecutive spacer plates. The rods can be oriented horizontally or vertically to represent transport or storage conditions. The measured and simulated rod temperatures are compared for three different rod heat generation rates to assess the acc
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