Relevant bibliographies by topics / Reactor physic

Academic literature on the topic 'Reactor physic'

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Published: 14 March 2023

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Journal articles on the topic "Reactor physic"

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Delpech, S., E. Merle-Lucotte, D. Heuer, M. Allibert, V. Ghetta, C. Le-Brun, X. Doligez, and G. Picard. "Reactor physic and reprocessing scheme for innovative molten salt reactor system." Journal of Fluorine Chemistry 130, no. 1 (January 2009): 11–17. http://dx.doi.org/10.1016/j.jfluchem.2008.07.009.

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Younan, Simon, and David R. Novog. "Development and Testing of TRACE/PARCS ECI Capability for Modelling CANDU Reactors with Reactor Regulating System Response." Science and Technology of Nuclear Installations 2022 (March 27, 2022): 1–31. http://dx.doi.org/10.1155/2022/7500629.

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The use of the USNRC codes TRACE and PARCS has been considered for the coupled safety analysis of CANDU reactors. A key element of CANDU simulations is the interactions between thermal-hydraulic and physic phenomena with the CANDU reactor regulating system (RRS). To date, no or limited development has taken place in TRACE-PARCS in this area. In this work, the system thermal-hydraulic code TRACE_Mac1.0 is natively coupled with the core physic code PARCS_Mac1.0, and RRS control is implemented via the exterior communications interface (ECI) in TRACE. ECI is used for coupling the external codes to TRACE, including additional physical models and control system models. In this work, a Python interface to the TRACE ECI library is developed, along with an RRS model written in Python. This coupling was tested using a CANDU-6 IAEA code coupling benchmark and a 900 MW CANDU model for various transients. For the CANDU-6 benchmark, the transients did not include RRS response, however, the TRACE_Mac1.0/PARCS_Mac1.0 coupling and ECI script functionality was compared to the previous benchmark simulations, which utilized external coupling. For the 900 MW CANDU simulations, all aspects of the ECI module and RRS were included. The results from the CANDU-6 benchmark when using the built-in coupling are comparable to those previously achieved using external coupling between the two codes with coupled simulations taking 2x to 3x less execution time. The 900 MW CANDU simulations successfully demonstrate the RRS functionality for the loss of flow events, and the coupled solutions demonstrate adequate performance for figure-of-eight flow instability modeling.
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Nguyen, Nhi Dien, Ba Vien Luong, Vinh Vinh Le, Van Dong Duong, Xuan Hai Nguyen, Ngoc Son Pham, and Dong Vu Cao. "Results of Operation and Utilization of the Dalat Nuclear Research Reactor." Nuclear Science and Technology 4, no. 1 (March 30, 2014): 1–9. http://dx.doi.org/10.53747/jnst.v4i1.208.

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The Dalat Nuclear Research Reactor (DNRR) with the nominal power of 500 kW was reconstructed and upgraded from the USA 250-kW TRIGA Mark-II reactor built in early 1960s. The renovated reactor was put into operation on 20th March 1984. It was designed for the purposes of radioisotope production (RI), neutron activation analysis (NAA), basic and applied researches, and nuclear education and training. During the last 30 years of operation, the DNRR was efficiently utilized for producing many kinds of radioisotopes and radiopharmaceuticals used in nuclear medicine centers and other users in industry, agriculture, hydrology and scientific research; developing a combination of nuclear analysis techniques (INAA, RNAA, PGNAA) and physic-chemical methods for quantitative analysis of about 70 elements and constituents in various samples; carrying out experiments on the reactor horizontal beam tubes for nuclear data measurement, neutron radiography and nuclear structure study; and establishing nuclear training and education programs for human resource development. This paper presents the results of operation and utilization of the DNRR. In addition, some main reactor renovation projects carried out during the last 10 years are also mentioned in the paper.
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Pascal, V., Y. Gorsse, N. Alpy, K. Ammar, M. Anderhuber, AM Baudron, G. Campioni, et al. "MULTIPHYSICS MODELISATION OF AN UNPROTECTED LOSS OF FLOW TRANSIENT IN A SODIUM COOLED FAST REACTORS USING A NEUTRONIC-THERMAL-HYDRAULIC COUPLING SCHEME." EPJ Web of Conferences 247 (2021): 07001. http://dx.doi.org/10.1051/epjconf/202124707001.

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Sodium cooled fast neutron reactors (SFR) are one of the selected reactor concepts in the framework of the Generation IV International Forum. In this concept, unprotected loss of cooling flow transients (ULOF), for which the non-triggering of backup systems is postulated, are regarded as potential initiators of core melting accidents. During an ULOF transient, spatial distributions of fuel, structure and sodium temperatures are affected by the core cooling flow decrease, which will modify the spatial and energy distribution of neutron in the core due to the spatial competition of neutron feedback effects. As no backup systems are triggered, sodium may reach its boiling temperature at some point, leading to local sodium density variations and making the transient fluctuate in a two-phase flow physics where thermal-hydraulics and neutronics may interact with each other. The transient phenomenology involves several physic disciplines at different time and spatial scales, such as core neutronics, coolant thermal-hydraulics and fuel thermo-mechanics. This paper presents the results of thermal-hydraulic/neutronic coupled simulations of an ULOF transient on the SFR project ASTRID. These coupled calculations are based on the supervisor platform SALOME to link the neutron code APOLLO3® to the system thermal-hydraulic code CATHARE3. The physical approach used by the coupling to describe the neutron kinetic is a quasi-static adiabatic one, updating the normalized spatial power distribution periodically by performing static neutron calculations, while a point kinetic model associated to a neutron feedback model calculates the power amplitude variations.
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Nowak, Agata, Robert Mazur, Ewa Panek, and Joanna Chmist. "Model Studies on the Effectiveness of MBBR Reactors for the Restoration of Small Water Reservoirs." E3S Web of Conferences 30 (2018): 02004. http://dx.doi.org/10.1051/e3sconf/20183002004.

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The authors present the Moving Bed Biofilm Reactor (MBBR) model with a quasi-continuous flow for small water reservoir restoration, characterized by high concentrations of organic pollutants. To determine the efficiency of wastewater treatment the laboratory analysis of physic-chemical parameters were conducted for the model on a semi-technical scale of 1:3. Wastewater treatment process was carried out in 24 h for 1 m3 for raw sewage. The startup period was 2 weeks for all biofilters (biological beds). Approximately 50% reduction in COD and BOD5 was obtained on average for the studied bioreactors. Significant improvements were achieved in theclarity of the treated wastewater, with the reduction of suspension by 60%. The oxygen profile has improved significantly in 7 to 9 hours of the process, and a diametric reduction in the oxidative reduction potential was recorded. A preliminary model of biological treatment effectiveness was determined based on the conducted studies. In final stages, the operation mode was set in real conditions of polluted water reservoirs.
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Maria F, Lencina, Robinson Ada J, Rearte Samanta M, and Albarracín Patricia M. "Production of unicelular protein and reduction of contaminating amount of vinasse." Journal of Applied Biotechnology & Bioengineering 9, no. 6 (December 26, 2022): 229–31. http://dx.doi.org/10.15406/jabb.2022.09.00315.

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The vinasse from ethanol distillery, which is a highly contaminating industrial waste, is produced in large quantities. Through biotechnology, it can be used for the production of protein while reducing contamination. The Candida utilis strain was isolated and adapted under different concentrations of aqueous formulas of vinasse, from 10 to 50%. The experimental trials were carried out in a lab using a “batch” reactor with vinasse. The growth of the microorganism was monitored using a carbon dioxide sensor (CO2). The parameters measured were: total nitrogen, COD (chemical demand of oxygen), pH and conductivity, at the beginning and end of each trial. Every two hours, the DO (optics density in a liquid environment) was measured with the objective of knowing its cellular concentration. For each physic- chemical variable analyzed, an ANOVA was realized to evaluate the factors of repetition, treatment and reactor, and it was chosen a significance level of 1%. The parameters measured reported: in total nitrogen there was an enrichment of 136% in the environment composed of 50% of vinasse in aqueous formulas; the average removal of the chemical demand of oxygen was 43%; the variation of pH, which was compared at the end of the trials, was 4% less than at the beginning; and the conductivity lessened to 9%. The monitoring of yeast growth by measuring the carbon dioxide concentrations throughout the time and the environment’s OD, allowed for the creation of a growth curve of the microorganism, with a fermentation period of 21 hours. It was proved that the Candida utilis strain can develop in a batch reactor with vinasse, in aqueous solutions of 50%, and producing a proteic enrichment of it as well as the removal of COD. The proposed process reduces the contamination of the main industrial effluent of Tucumán
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Ahmad Latiffi, Nur Atikah, Radin Maya Saphira Radin Mohamed, Najeeha Mohd Apandi, and Amir Hashim Mohd Kassim. "Application of Phycoremediation Using Microalgae Scenedesmus sp. as Wastewater Treatment in Removal of Heavy Metals from Food Stall Wastewater." Applied Mechanics and Materials 773-774 (July 2015): 1168–72. http://dx.doi.org/10.4028/www.scientific.net/amm.773-774.1168.

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This paper represents the results of using phycoremediation technology in treating the wastewater produced from food stall activity by using microalgae of Scenedesmus sp. in removal of heavy metals. Phycoremediation has advantages over physic-chemical approaches as it is can completely degrade organic pollutants without destroy the surrounding flora and fauna. Aim of this study is to determine the effectiveness of microalgae Scenedesmussp to assimilate the pollutant load based on the optimum time and concentration. Characteristics of food stall wastewater need to be identified and analyse before phycoremediation process taken place. The wastewater sampling was collected at food stall during peak time i.e. at 8 a.m. and 4 p.m. Microalgae Scenedesmus sp. to be injected to the batch reactor based on five (5) different concentration cells. The results shows that the optimum removal of heavy metals are dominant by concentration no. 1 (C1) compare to other concentration in the treatment i.e. removal of Ferum by 88.22% and 69.63%, Copper by 60% and 53.85% at both sampling time while removal of zinc is dominant by concentration no.4 (C4) by 75.61% and 76.63% respectively.
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Foffi, Rachele, Elisa Savuto, Matteo Stante, Roberta Mancini, and Katia Gallucci. "Study of Energy Valorization of Disposable Masks via Thermochemical Processes: Devolatilization Tests and Simulation Approach." Energies 15, no. 6 (March 13, 2022): 2103. http://dx.doi.org/10.3390/en15062103.

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The COVID-19 pandemic exacerbated the use of medical protective equipment, including face masks, to protect the individual from the virus. This work studies the feasibility of using these materials as fuel for thermochemical processes for the production of syngas. A preliminary physic-chemical characterization was made by means of moisture and ash determination, thermogravimetric analysis, X-ray fluorescence. Afterward, pyrolysis and gasification tests were executed in a laboratory-scale fluidized bed reactor with chirurgical and FFP2 masks investigating four temperature levels and three different operating conditions (fluidizing agents and dry/wet sample). A qualitative and quantitative analysis of condensable aromatic hydrocarbons in the produced gas, collected during the test campaign, was performed employing a gas chromatograph-mass spectrometer. The experimental data from the tests were used to propose a hybrid approach to simulate the gasification process, based on experimental laws for the devolatilization step and a thermodynamic equilibrium approach for char gasification. The resulting data were compared with a thermodynamic equilibrium model, showing that the new approach captures non-equilibrium effects always present in real gasifiers operation.
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Смолин and V. Smolin. "Mathematical Simulation of Biotechnical Scanner to Determine Hydration Degrees a Biological Tissue in Norme and at Different Pathologies." Journal of New Medical Technologies 22, no. 1 (February 11, 2015): 11–16. http://dx.doi.org/10.12737/9068.

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The organs and tissues of the living body depending on the structure and functional states can contain from 50 to 90% of water. Water in a living organism can be in two forms: free water and structured water. Structured water forms strong links with organic molecules. Free water is movable, its quantity can vary considerably depending on the functional state of the body and determines a hydration degree of a tissues. In clinical practice, the existing technical possibilities of determining hydration degree of biological objects are li-mited and hardly used. Any conclusions about the cause of death due to swelling are not sufficiently and quantified justified. This paper is devoted to the development of a mathematical model of biotechnical scanner to determine the degree of hydration of biological tissues, based on the physic-chemical effect caused by additive volume of the system in the interaction of the sample of biological tissue with ethanol. The mathematical model demonstrated that the violations of additivity volume are observed even with the addition of small water volume to large alcohol volume. A probabilistic model was developed and shown that the effects of the exothermic reaction, mixing water and ethanol, have a strong effect on the dates of the process. But this fixing process of a biological object is extended during times, the studied system by the end of fixation will go down in the stationary regime, which will determine the degree of hydration. Registration changes of the system volume during the interaction of a biological object with ethanol allows to studying the dynamics of physical and chemical processes in the reactor of biotechnical scanner.
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Katsioulas, I., I. Savvidis, and C. Eleftheriadis. "Nuclear Reactor Neutrino Detection with the Spherical Proportional Counter." HNPS Proceedings 21 (March 8, 2019): 92. http://dx.doi.org/10.12681/hnps.2010.

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Nuclear Power Reactors are the most powerful neutrino sources as they emit large numbers of antineu- trinos, at energies up to 10 MeV. The reactor neutrino detection is very important for fundamental physics goals, as well as for applications, among them being the possibility to determine the isotopic composition of the reactor’s core. This could lead to application of neutrino spectroscopy for reactor monitoring, either for improving the reliability of operation of power reactors or as a method to accomplish certain safeguard and non-proliferation objectives. We present here the conditions on detecting neutrinos coming from nuclear reactors with the Spherical Proportional Counter (SPC), by exploiting the coherent neutrino-nucleus elastic scattering.
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Dissertations / Theses on the topic "Reactor physic"

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Pope, Michael A. (Michael Alexander). "Reactor physics design of supercritical CO₂-cooled fast reactors." Thesis, Massachusetts Institute of Technology, 2004. http://hdl.handle.net/1721.1/33633.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2004.
Includes bibliographical references (p. 109-113).
Gas-Cooled Fast Reactors (GFRs) are among the GEN-IV designs proposed for future deployment. Driven by anticipated plant cost reduction, the use of supercritical CO₂ (S-CO₂) as a Brayton cycle working fluid in a direct cycle is evaluated. By using S- CO₂ at turbine inlet conditions of 20 MPa and 550⁰C - 700⁰C, efficiencies between 45% and 50% can be achieved with extremely compact components. Neutronic evaluation of candidate core materials was performed for potential use in block-type matrix fueled GFRs with particular concentration on lowering coolant void reactivity to less than $1. SiC cercer fuel was found to have relatively low coolant void worth (+22 cents upon complete depressurization of S-CO₂ coolant) and tolerable reactivity- limited burnup at matrix volume fractions of 60% or less in a 600 MWth core having H/D of 0.85 and titanium reflectors. Pin-type cores were also evaluated and demonstrated higher kff versus burnup, and higher coolant void reactivity than the SiC cercer cores (+$2.00 in ODS MA956-clad case having H/D of 1).
(cont.) It was shown, however, that S-CO₂ coolant void reactivity could be lowered significantly - to less than $1 - in pin cores by increasing neutron leakage (e.g. lowering the core H/D ratio to 0.625 in a pin core with ODS MA956 cladding), an effect not observed in cores using helium coolant at 8 MPa and 500⁰C. An innovative "block"-geometry tube-in-duct fuel consisting of canisters of vibrationally compacted (VIPAC) oxide fuel was introduced and some preliminary calculations were performed. A reference tube-in-duct core was shown to exhibit favorable neutron economy with a conversion ratio (CR) at beginning of life (BOL) of 1.37, but had a coolant void reactivity of +$ 1.4. The high CR should allow designers to lower coolant void worth by increasing leakage while preserving the ability of the core to reach high burnup. Titanium, vanadium and scandium were found to be excellent reflector materials from the standpoint of ... and coolant void reactivity due to their unique elastic scattering cross-section profiles: for example, the SiC cercer core having void reactivity of +$0.22 with titanium was shown to have +$0.57 with Zr₃Si₂.
(cont.) Overall, present work confirmed that the S-CO₂-cooled GFR concept has promising characteristics and a sufficiently broad opion space such that a safe and competitive design could be developed in future work with considerably less than $1 void reactivity and a controllable [delta]k due to burnup.
by Michael A. Pope.
S.M.
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Sadeghi, Mohammad Mehdi 1959. "SYMBOLIC MANIPULATION IN REACTOR PHYSICS." Thesis, The University of Arizona, 1986. http://hdl.handle.net/10150/275520.

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Bora, Pekicten Aziz. "Assembly homogenization of light water reactors by a monte carlo reactor physics method and verification by a deterministic method." Thesis, KTH, Kärnkraftsäkerhet, 2011. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-34492.

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Gottfridsson, Filip. "Simulation of Reactor Transient and Design Criteria of Sodium-cooled Fast Reactors." Thesis, Uppsala universitet, Tillämpad kärnfysik, 2010. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-148572.

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The need for energy is growing in the world and the market of nuclear power is now once more expanding. Some issues of the current light-water reactors can be solved by the next generation of nuclear power, Generation IV, where sodium-cooled reactors are one of the candidates. Phénix was a French prototype sodium-cooled reactor, which is seen as a success. Although it did encounter an earlier unexperienced phenomenon, A.U.R.N., in which a negative reactivity transient followed by an oscillating behavior forced an automatic emergency shutdown of the reactor. This phenomenon lead to a lot of downtime of the reactor and is still unsolved. However, the most probable cause of the transients is radial movements of the core, referred to as core-flowering. This study has investigated the available documentation of the A.U.R.N. events. A simplified model of core-flowering was also created in order to simulate how radial expansion affects the reactivity of a sodium-cooled core. Serpent, which is a Monte-Carlo based simulation code, was chosen as calculation tool. Furthermore, a model of the Phénix core was successfully created and partly validated. The model of the core has a k_eff = 1.00298 and a neutron flux of (8.43+-0.02)!10^15 neutrons/cm^2 at normal state. The result obtained from the simulations shows that an expansion of the core radius decreases the reactivity. A linear approximation of the result gave the relation: change in k_eff/core extension = - 60 pcm/mm. This value corresponds remarkably well to the around - 60 pcm/mm that was obtained from the dedicated core-flowering experiments in Phénix made by the CEA. Core-flowering can recreate similar signals to those registered during the A.U.R.N. events, though the absence of trace of core movements in Phénix speaks against this. However, if core-flowering is the sought answer, it can be avoided by design. The equipment that registered the A.U.R.N. events have proved to be insensitive to noise. Though, the high amplitude of the transients and their rapidness have made some researcher believe that the events are a combination of interference in the equipment of Phénix and a mechanical phenomenon. Regardless, the origin of A.U.R.N. seems to be bound to some specific parameter of Phénix due to the fact that the transients only have occurred in this reactor. A safety analysis made by an expert committee, appointed by CEA, showed that the A.U.R.N. events are not a threat to the safety of Phénix. However, the origin of these negative transients has to be found before any construction of a commercial size sodium-cooled fast reactor can begin. Thus, further research is needed.
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Gonzalez, Vargas Jose Angel [Verfasser], and R. [Akademischer Betreuer] Stieglitz. "Advanced Reactor Physics Methods for Transient Analysis of Boiling Water Reactors / Jose Angel Gonzalez Vargas ; Betreuer: R. Stieglitz." Karlsruhe : KIT-Bibliothek, 2017. http://d-nb.info/1148551336/34.

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Brinkmann, Torsten. "Use of catalytic membrane reactors for in situ reaction and separation." Thesis, University of Bath, 1999. https://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.301546.

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Emmett, John Carter Alfred. "A standard neutron spectrum source of application to fast reactor physics." Thesis, Imperial College London, 2000. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.312126.

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Christensen, Eric Kurt. "Applications of Neutrino Physics." Diss., Virginia Tech, 2014. http://hdl.handle.net/10919/64864.

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Neutrino physics has entered a precision era in which understanding backgrounds and systematic uncertainties is particularly important. With a precise understanding of neutrino physics, we can better understand neutrino sources. In this work, we demonstrate dependency of single detector oscillation experiments on reactor neutrino flux model. We fit the largest reactor neutrino flux model error, weak magnetism, using data from experiments. We use reactor burn-up simulations in combination with a reactor neutrino flux model to demonstrate the capability of a neutrino detector to measure the power, burn-up, and plutonium content of a nuclear reactor. In particular, North Korean reactors are examined prior to the 1994 nuclear crisis and waste removal detection is examined at the Iranian reactor. The strength of a neutrino detector is that it can acquire data without the need to shut the reactor down. We also simulate tau neutrino interactions to determine backgrounds to muon neutrino and electron neutrino measurements in neutrino factory experiments.
Ph. D.
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MAEDA, REINALDO de M. "Determinação experimental de parâmetros de física de reatores utilizando refletor de água pesada no reator IPEN/MB-01." reponame:Repositório Institucional do IPEN, 2012. http://repositorio.ipen.br:8080/xmlui/handle/123456789/10128.

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Dissertação (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Tuttelberg, Kaur. "STORM in Monte Carlo reactor physics calculations." Thesis, KTH, Fysik, 2014. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-146284.

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Books on the topic "Reactor physic"

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Nuclear reactor physics. 2nd ed. Weinheim: Wiley-VCH, 2007.

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Stacey, Weston M. Nuclear Reactor Physics 3e. Weinheim, Germany: Wiley-VCH Verlag GmbH & Co. KGaA, 2018. http://dx.doi.org/10.1002/9783527812318.

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Masterson, Robert E. Introduction to Nuclear Reactor Physics. Boca Raton : Taylor & Francis, a CRC title, part of the Taylor & Francis imprint, a member of the Taylor & Francis Group, the academic division of T&F Informa, plc, [2017]: CRC Press, 2017. http://dx.doi.org/10.1201/9781315118055.

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Lewis, E. E. Fundamentals of nuclear reactor physics. Amsterdam: Academic Press, 2008.

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Lewis, E. E. Fundamentals of nuclear reactor physics. Amsterdam: Academic Press, 2008.

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Lewis, E. E. Fundamentals of nuclear reactor physics. Amsterdam: Academic Press, 2008.

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Glasstone, Samuel. Nuclear Reactor Engineering: Reactor Systems Engineering. Boston, MA: Springer US, 1994.

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Herman, M., and Nello Paver. Nuclear reaction data and nuclear reactors: [Workshop on Nuclear Reaction Data and Nuclear Reactors: Physics, Design and Safety, 25 February - 28 March 2002]. Trieste: Abdus Salam International Centre for Theoretical Physics, 2005.

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Centre, Bhabha Atomic Research, ed. Operational reactor physics analysis codes (ORPAC). Mumbai: Bhabha Atomic Research Centre, 2007.

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Marguet, Serge. The Physics of Nuclear Reactors. Cham: Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-59560-3.

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Book chapters on the topic "Reactor physic"

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Bignan, Gilles, Philippe Fougeras, Patrick Blaise, Jean-Pascal Hudelot, and Frédéric Mellier. "Reactor Physics Experiments on Zero Power Reactors." In Handbook of Nuclear Engineering, 2053–184. Boston, MA: Springer US, 2010. http://dx.doi.org/10.1007/978-0-387-98149-9_18.

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Natelson, Michael. "Fission Reactor Physics fission reactor physics." In Encyclopedia of Sustainability Science and Technology, 3787–820. New York, NY: Springer New York, 2012. http://dx.doi.org/10.1007/978-1-4419-0851-3_18.

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Lakey, J. R. A., and R. E. Alexander. "Developments in Health Physics Dosimetry." In Reactor Dosimetry, 951–58. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-010-9726-0_44.

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Lakey, J. R. A., and R. E. Alexander. "Developments in Health Physics Dosimetry." In Reactor Dosimetry, 951–58. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-009-5378-9_96.

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Mikityuk, K. "Fast Reactor Physics." In Thorium Energy for the World, 215–21. Cham: Springer International Publishing, 2016. http://dx.doi.org/10.1007/978-3-319-26542-1_33.

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Wakabayashi, Genichiro, Takahiro Yamada, Tomohiro Endo, and Cheol Ho Pyeon. "Reactor Physics Experiments." In Introduction to Nuclear Reactor Experiments, 47–85. Singapore: Springer Nature Singapore, 2022. http://dx.doi.org/10.1007/978-981-19-6589-0_2.

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Natelson, Michael. "Fission Reactor Physics." In Nuclear Energy, 5–40. New York, NY: Springer New York, 2018. http://dx.doi.org/10.1007/978-1-4939-6618-9_18.

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Natelson, Michael. "Fission Reactor Physics." In Nuclear Energy, 7–57. New York, NY: Springer New York, 2012. http://dx.doi.org/10.1007/978-1-4614-5716-9_2.

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Natelson, Michael. "Fission Reactor Physics." In Encyclopedia of Sustainability Science and Technology, 1–38. New York, NY: Springer New York, 2016. http://dx.doi.org/10.1007/978-1-4939-2493-6_18-3.

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Fabry, A., and A. Lowe. "Workshop “LWR-PV Physics, Dosimetry, Damage Correlation and Materials Problems”." In Reactor Dosimetry, 999. Dordrecht: Springer Netherlands, 1985. http://dx.doi.org/10.1007/978-94-010-9726-0_49.

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Conference papers on the topic "Reactor physic"

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Cerba, Š., V. Necas, and J. Lüley. "Determination of the Dosimetry Situation in Reactor Physic Laboratory of SUT in Bratislava." In 2020 ANS Virtual Winter Meeting. AMNS, 2020. http://dx.doi.org/10.13182/t123-33337.

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Atong, Duangduen, and Viboon Sricharoenchaikul. "Thermal Conversion of Mixed Wastes From Biodiesel Manufacturing for Production of Fuel Gas." In ASME 2009 3rd International Conference on Energy Sustainability collocated with the Heat Transfer and InterPACK09 Conferences. ASMEDC, 2009. http://dx.doi.org/10.1115/es2009-90200.

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Thermochemical conversion process has become a viable technology for managing excess waste from various industries while producing value added fuel products. In the work reported here, distribution of products (solid, liquid, and gas) by thermal conversion of wastes from biodiesel production process which are extracted physic nut and palm shell mixed with glycerol waste was carried out using a medium scale tubular reactor with feeding rate of 5 g/min. Several important operating parameters were studied including the proportion of each waste (100:0 – 70:30), reaction temperature (700 – 900°C) and air to fuel ratio (AF) 0.0 – 0.6. It was found that when the temperature increased, the quantity of solid and liquid product decreased while gas product increased. For conversion to CO2, CO, CxHy and H2, when the temperature increased, CO2 decreased while yields of CO, CH4 and H2 increased. Greater conversion to CO2, CO, H2 with AF increased from 0.0 to 0.3. Higher AF from 0.3 to 0.6 resulted in lesser CO and H2 while conversion to CO2 increased. On the other hand, CxHy decreased when AF changed from 0.0 to 0.6. The maximum heating values of gas product in this study are 3.48 MJ/m3 and 2.27 MJ/m3 for glycerol waste mixed with physic nut waste and palm shell waste, respectively (both at 30% glycerol wastes and reaction temperature of 900°C). The maximum of mole ratio of H2 to CO obtained is 0.59 for physic nut and 0.37 for palm shell mixed wastes. Relatively high CxHy, low product gas heating value and H2 to CO ratio indicated the need for further product upgrading before using as raw material for other advanced fuel production processes such as Fisher-Tropsch, DME, or methanol syntheses beside direct heat and power utilization.
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Deng, Jiaolong, Xiang Chai, Tengfei Zhang, and Xiaojing Liu. "Conceptual Multi-Physic Coupling Simulation on Transient Operations Of a He-Xe Cooled Mobile Nuclear Power Plant." In 2022 29th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/icone29-92247.

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Abstract Mobile nuclear power plants (MNPP) with low-enriched fuel loading, compact structures, and flexible configurations significantly apply emergency power supply for remote locations. Due to good compressibility and heat-transfer performance, the He-Xe mixture is used as the working medium of the closed Brayton cycle (CBC) and the coolant of the graphite-based solid-state reactor (SSR). In the present work, multi-physics transient simulations are conducted based on the open-source software OpenFOAM. CFD methods solve the heat transfer between the solid matrix and the He-Xe channels, and the three-dimensional temperature distributions can be determined. Because of the large amounts of channels in the core, we employ a porous media model to decrease the mesh resolution near the channel-to-cladding interface. For simplification, the power transient is controlled by point kinetic equations. Doppler broadening effect is considered as the feedback between the neutronics and thermal-hydraulics. The rest components of the CBC, such as the pre-cooler, the compressor, the recuperator and the turbine, are represented as a one-dimensional model to update the boundary condition of the reactor core. The simulation results reveal dynamic features of the CBC system under several transient operations. The numerical analysis of this work could provide references to the further analysis of the MNPP.
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Lin, Bo, Sui-zheng Qiu, Guang-hui Su, Wen-xi Tian, and Ya-pei Zhang. "Simulation of Molten Corium Concrete Interaction With the MOCO Code." In 2014 22nd International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/icone22-30345.

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In the event of a severe accident in a pressurized water reactor, the core of a reactor melts and forms corium, a mixture that includes molten UO2 and ZrO2. If the reactor pressure vessel fails, corium can be relocated in the containment cavity and interact with concrete forming a melt pool. The melt pool can be flooded with water at the top for quenching it. However, the question is what extent the water can ingress in the corium melt pool to cool and quench it. To reveal that, a numerical study has been carried out using a new computer code MOCO. The code considers the heat transfer behavior in axial and radial directions from the molten pool to the overlaying water, crust generation and growth, and incorporates phenomenology that is deemed to be important for analyzing debris cooling behavior. The interaction between thermalhydraulics and physic-chemistry is modeled in MOCO. The main purpose of this paper is to present the modeling used in MOCO and some validation calculations using the data of experiments available in the literature.
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Obložinský, P., and A. Gandini. "Nuclear Reaction Data and Nuclear Reactors – Physics, Design and Safety." In Workshop on Nuclear Reaction Data and Nuclear Reactors. WORLD SCIENTIFIC, 1999. http://dx.doi.org/10.1142/9789814527392.

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Kemah, Elif, Recep Akkaya, and Seyit Rıza Tokgöz. "Comparing the new generation accelerator driven subcritical reactor system (ADS) to traditional critical reactors." In TURKISH PHYSICAL SOCIETY 32ND INTERNATIONAL PHYSICS CONGRESS (TPS32). Author(s), 2017. http://dx.doi.org/10.1063/1.4976409.

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Levine, S. H. "Basic Reactor Physics." In Proceedings of the Workshop. WORLD SCIENTIFIC, 1991. http://dx.doi.org/10.1142/9789814439398_0007.

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Joseph, Jofred, Satish Kumar, Tanmay Vasal, and N. Theivarajan. "Brayton Cycle As an Alternate Power Conversion Option for Sodium Cooled Fast Reactor." In ASME 2019 Gas Turbine India Conference. American Society of Mechanical Engineers, 2019. http://dx.doi.org/10.1115/gtindia2019-2455.

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Abstract Enhancing the safety and economic competitiveness are major objectives in the development of advanced reactor designs with emphasis on the design of systems or components of the nuclear systems. Innovative power cycle development is another potential option to achieve these objectives. Sodium cooled fast reactor (SFR) is one among the six reactor design concepts identified by the Gen IV International Forum for development to meet the technology goals for new nuclear energy system. Similar to the power cycle used in conventional fossil fuel based thermal power plants, sodium-cooled fast reactors have adopted the Rankine cycle based power conversion system. However, the possibility of sodium water reaction is a major concern and it becomes necessary to adopt means of early detection of leaks and isolation of the affected SG module for mitigating any adverse impact of sodium water reaction. The high exothermic nature of the reaction calls for introducing an intermediate sodium heat transport loop, leading to high overall plant cost hindering commercialization of sodium fast reactors. The Indian Prototype Fast Breeder Reactor (PFBR) also uses Rankine cycle in the power generation system. The superheated steam temperature has been set at 490 degree Celsius based on optimisation studies and material limitations. Additional Fast Breeder reactors are planned in near future and further work is being done to develop more advanced sodium cooled fast reactors. The closed Brayton cycle is a promising alternative to conventional Rankine cycle. By selecting an inert gas or a gas with milder reaction with sodium, the vigorous sodium water reaction can be avoided and significant cost savings in the turbine island can be achieved as gas turbine power conversion systems are of much smaller size than comparable steam turbine systems due to their higher power density. In the study, various Brayton cycle designs on different working gases have been explored. Supercritical-CO2 (s-CO2), helium and nitrogen cycle designs are analyzed and compared in terms of cycle efficiency, component performance and physical size. The thermal efficiencies at the turbine inlet temperature of Indian PFBR have been compared for Rankine cycle and Brayton cycle based on different working fluids. Also binary mixtures of different gases are investigated to develop a more safe and efficient power generation system. Helium does not interact with sodium and other structural materials even at very high temperatures but its thermal performance is low when compared to other fluids. Nitrogen being an inert gas does not react with sodium and can serve to utilise existing turbomachinery because of the similarity with atmospheric air. The supercritical CO2 based cycle has shown best thermodynamic performance and efficiency when compared to other Brayton cycles for the turbine inlet temperature of Indian PFBR. CO2 also reacts with sodium but the reaction is mild compared to sodium water reaction. The cycle efficiency of the s-CO2 cycle can be further improved by adopting multiple reheating, inter cooling and recuperation.
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Brown, N., E. Duchnowski, L. Snead, and J. Trelewicz. "Preliminary Reactor Physics Analysis of Alternative Moderators for Modular High Temperature Gas-Cooled Reactors." In Tranactions - 2019 Winter Meeting. AMNS, 2019. http://dx.doi.org/10.13182/t31307.

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Rastogi, B. P. "REACTOR PHYSICS IN INDIA." In ACIF's First Course on Nuclear Physics and Reactors. WORLD SCIENTIFIC, 1986. http://dx.doi.org/10.1142/9789814415569_0003.

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Reports on the topic "Reactor physic"

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Cleveland, J. (Safety related reactor physics calculation for HTGR type reactors). Office of Scientific and Technical Information (OSTI), October 1989. http://dx.doi.org/10.2172/5381930.

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Sanchez, Rene, Travis Grove, and William Myers. Module 10 Reactor Physics. Office of Scientific and Technical Information (OSTI), January 2021. http://dx.doi.org/10.2172/1756787.

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Brady, M. (Physics of reactors). Office of Scientific and Technical Information (OSTI), May 1990. http://dx.doi.org/10.2172/6986759.

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Petrie, L., and G. Whitesides. (Reactor physics and criticality safety). Office of Scientific and Technical Information (OSTI), June 1990. http://dx.doi.org/10.2172/6841470.

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Ilas, Germina, Joseph Burns, Briana Hiscox, and Ugur Mertyurek. SCALE 6.2.4 Validation: Reactor Physics. Office of Scientific and Technical Information (OSTI), November 2022. http://dx.doi.org/10.2172/1902818.

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Perry, R. T., and G. H. Meriwether. A WIMS-NESTLE reactor physics model for an RBMK reactor. Office of Scientific and Technical Information (OSTI), August 1996. http://dx.doi.org/10.2172/266875.

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Sims, C. S., and G. E. Ragan. Health physics research reactor reference dosimetry. Office of Scientific and Technical Information (OSTI), June 1987. http://dx.doi.org/10.2172/6440156.

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Author, Not Given. Technical specifications: Health Physics Research Reactor. Office of Scientific and Technical Information (OSTI), March 1986. http://dx.doi.org/10.2172/6249628.

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Pope, Chad L., Edward S. Lum, Ryan Stewart, Bilguun Byambadorj, and Quinton Beaulieu. EBR-II Reactor Physics Benchmark Evaluation Report. Office of Scientific and Technical Information (OSTI), December 2017. http://dx.doi.org/10.2172/1415120.

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Wachs, Daniel. Transient Test Reactor Physics Workshop - May 2016. Office of Scientific and Technical Information (OSTI), May 2016. http://dx.doi.org/10.2172/1504917.

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