Relevant bibliographies by topics / Fission Reactor Physic

Academic literature on the topic 'Fission Reactor Physic'

Author: Grafiati
Published: 14 March 2023

Create a spot-on reference in APA, MLA, Chicago, Harvard, and other styles

Select a source type:

Contents

Consult the lists of relevant articles, books, theses, conference reports, and other scholarly sources on the topic 'Fission Reactor Physic.'

Next to every source in the list of references, there is an 'Add to bibliography' button. Press on it, and we will generate automatically the bibliographic reference to the chosen work in the citation style you need: APA, MLA, Harvard, Chicago, Vancouver, etc.

You can also download the full text of the academic publication as pdf and read online its abstract whenever available in the metadata.

Journal articles on the topic "Fission Reactor Physic"

1

Ripani, M. "Energy from nuclear fission." EPJ Web of Conferences 268 (2022): 00010. http://dx.doi.org/10.1051/epjconf/202226800010.

Full text
Abstract:
The physics of nuclear fission will be briefly illustrated, from the basic mechanism behind this phenomenon to the relevant physical quantities like nuclear cross sections, neutron flux and reaction products, together with the accompanying phenomenon of neutron capture and its role in determining how the fuel transforms in a nuclear reactor. The basic concepts underlying the operation of different types of nuclear reactors will be illustrated, along with the concept of fuel cycle. The aspects of radioactive waste, fuel resources and safety will also be briefly illustrated.
APA, Harvard, Vancouver, ISO, and other styles
2

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

Full text
Abstract:
The physics of nuclear fission will be briefly illustrated, from the basic mechanism behind this phenomenon to the relevant physical quantities like nuclear cross sections, neutron flux and reaction products, together with the accompanying phenomenon of neutron capture and its role in determining how the fuel transforms in a nuclear reactor. The basic concepts underlying the operation of different types of nuclear reactors will be illustrated, along with the concept of fuel cycle. After touching on the aspect of safety, the current situation of nuclear power in the world, with its costs, its role in reducing carbon emissions, the available resources and finally the issues of waste management and accidents will be briefly illustrated.
APA, Harvard, Vancouver, ISO, and other styles
3

Verbeke, Jérôme M., Odile Petit, Abdelhazize Chebboubi, and Olivier Litaize. "Correlated Production and Analog Transport of Fission Neutrons and Photons using Fission Models FREYA, FIFRELIN and the Monte Carlo Code TRIPOLI-4® ." EPJ Web of Conferences 170 (2018): 01019. http://dx.doi.org/10.1051/epjconf/201817001019.

Full text
Abstract:
Fission modeling in general-purpose Monte Carlo transport codes often relies on average nuclear data provided by international evaluation libraries. As such, only average fission multiplicities are available and correlations between fission neutrons and photons are missing. Whereas uncorrelated fission physics is usually sufficient for standard reactor core and radiation shielding calculations, correlated fission secondaries are required for specialized nuclear instrumentation and detector modeling. For coincidence counting detector optimization for instance, precise simulation of fission neutrons and photons that remain correlated in time from birth to detection is essential. New developments were recently integrated into the Monte Carlo transport code TRIPOLI-4 to model fission physics more precisely, the purpose being to access event-by-event fission events from two different fission models: FREYA and FIFRELIN. TRIPOLI-4 simulations can now be performed, either by connecting via an API to the LLNL fission library including FREYA, or by reading external fission event data files produced by FIFRELIN beforehand. These new capabilities enable us to easily compare results from Monte Carlo transport calculations using the two fission models in a nuclear instrumentation application. In the first part of this paper, broad underlying principles of the two fission models are recalled. We then present experimental measurements of neutron angular correlations for 252Cf(sf) and 240Pu(sf). The correlations were measured for several neutron kinetic energy thresholds. In the latter part of the paper, simulation results are compared to experimental data. Spontaneous fissions in 252Cf and 240Pu are modeled by FREYA or FIFRELIN. Emitted neutrons and photons are subsequently transported to an array of scintillators by TRIPOLI-4 in analog mode to preserve their correlations. Angular correlations between fission neutrons obtained independently from these TRIPOLI-4 simulations, using either FREYA or FIFRELIN, are compared to experimental results. For 240Pu(sf), the measured correlations were used to tune the model parameters.
APA, Harvard, Vancouver, ISO, and other styles
4

Burgio, N., M. Carta, V. Fabrizio, L. Falconi, A. Gandini, R. Gatto, V. Peluso, E. Santoro, and M. B. Sciarretta. "SUBCRITICALITY MONITORING IN FUSION-FISSION HYBRID REACTORS." Problems of Atomic Science and Technology, Ser. Thermonuclear Fusion 44, no. 2 (2021): 27–41. http://dx.doi.org/10.21517/0202-3822-2021-44-2-27-41.

Full text
APA, Harvard, Vancouver, ISO, and other styles
5

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

Full text
Abstract:
The anti-neutrino source properties of a fission reactor are governed by the production and beta decay of the radionuclides present and the summation of their individual anti-neutrino spectra. The fission product radionuclide production changes during reactor operation and different fissioning species give rise to different product distributions. It is thus possible to determine some details of reactor operation, such as power, from the anti-neutrino emission to confirm safeguards records. Also according to some published calculations, it may be feasible to observe different anti-neutrino spectra depending on the fissile contents of the reactor fuel and thus determine the reactor's fissile material inventory during operation which could considerable improve safeguards. In mid-2014 the University of Liverpool deployed a prototype anti-neutrino detector at the Wylfa R1 station in Anglesey, United Kingdom based upon plastic scintillator technology developed for the T2K project. The deployment was used to develop the detector electronics and software until the reactor was finally shutdown in December 2015. To support the development of this detector technology for reactor monitoring and to understand its capabilities, the National Nuclear Laboratory modelled this graphite moderated and natural uranium fuelled reactor with existing codes used to support Magnox reactor operations and waste management. The 3D multi-physics code PANTHER was used to determine the individual powers of each fuel element (8×6152) during the year and a half period of monitoring based upon reactor records. The WIMS/TRAIL/FISPIN code route was then used to determine the radionuclide inventory of each nuclide on a daily basis in each element. These nuclide inventories were then used with the BTSPEC code to determine the anti-neutrino spectra and source strength using JEFF-3.1.1 data. Finally the anti-neutrino source from the reactor for each day during the year and a half of monitored reactor operation was calculated. The results of the preliminary calculations are shown and limitations in the methods and data discussed.
APA, Harvard, Vancouver, ISO, and other styles
6

Anastasiou, Maria. "6Li(n,t)α reaction event-identification for the 235U(n,f)/6Li(n,t) cross section ratio measurement in the NIFFTE fissionTPC." HNPS Advances in Nuclear Physics 28 (October 17, 2022): 30–35. http://dx.doi.org/10.12681/hnps.3567.

Full text
Abstract:
While nuclear data play an important role in nuclear physics applications, it has become important to have a better understanding of the data and try to minimize the uncertainties. In particular, there is a need for precision neutron-induced fission cross section measurements on fissile nuclei. Neutron-induced fission cross sections are typically measured as ratios, with a well-known standard in the denominator. While the 235U(n,f) reaction is a well measured standard, some light particle reactions are also well-known and their use as reference can provide information to remove shared systematic uncertainties that are present in an actinide-only ratio. A recent measurement of the 235U(n,f) reaction using as a reference the standard 6Li(n,t) reaction, was conducted at the Los Alamos Neutron Science Center using the NIFFTE collaboration’s fission time projection chamber (fissionTPC). The fissionTPC is a 2×2π charged particle tracker designed for measuring neutron-induced fission. Detailed 3D track reconstruction of the reaction products enables evaluation of systematic effects and corresponding uncertainties which are less directly accessible by other measurement techniques. This work focuses on the analysis for the event identification of the 6Li(n,t)α reaction in the fissionTPC.
APA, Harvard, Vancouver, ISO, and other styles
7

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

Full text
Abstract:
Fission product yields (FPYs) are an important source of information that are used for basic and applied physics. They are essential observables to address questions relevant to nucleosynthesis in the cosmos that created the elements from iron to uranium, for example, in energy generating processes from fission recycling in binary neutron star mergers; resolving the reactor neutrino anomaly; decay heat release in nuclear reactors; and many national security applications. While new applications will require accurate energy-dependent FPY data over a broad set of incident neutron energies, the current evaluated FPY data files contain only three energy points: thermal, fast, and 14-MeV incident energies. Recent measurements using mono-energetic and pulsed neutron beams at the Triangle Universities Nuclear Laboratory (TUNL) tandem accelerator and employing a dual fission ionization chambers setup have produced self-consistent, high-precision data critical for testing fission models for the neutron-induced fission of the major actinide nuclei. This paper will present new campaign just beginning utilizing a RApid Belt-driven Irradiated Target Transfer System (RABITTS) to measure shorter-lived fission products and the time dependence of fission yields, expanding the measurements from cumulative towards independent fission yields.
APA, Harvard, Vancouver, ISO, and other styles
8

Davies, Sebastian, Dzianis Litskevich, Bruno Merk, Andrew Levers, Paul Bryce, and Anna Detkina. "DYN3D and CTF Coupling within a Multiscale and Multiphysics Software Development (Part II)." Energies 15, no. 13 (July 1, 2022): 4843. http://dx.doi.org/10.3390/en15134843.

Full text
Abstract:
Traditionally, the complex coupled physical phenomena in nuclear reactors has resulted in them being treated separately or, at most, simplistically coupled in between within nuclear codes. Currently, coupling software environments are allowing different types of coupling, modularizing the nuclear codes or multi-physics. Several multiscale and multi-physics software developments for LWR are incorporating these to deliver improved or full coupled reactor physics at the fuel pin level. An alternative multiscale and multi-physics nuclear software development between NURESIM and CASL is being created for the UK. The coupling between DYN3D nodal code and CTF subchannel code can be used to deliver improved coupled reactor physics at the fuel pin level. In the current journal article, the second part of the DYN3D and CTF coupling was carried out to analyse a parallel two-way coupling between these codes and, hence, the outer iterations necessary for convergence to deliver verified improved coupled reactor physics at the fuel pin level. This final verification shows that the DYN3D and CTF coupling delivers improved effective multiplication factors, fission, and feedback distributions due to the presence of crossflow and turbulent mixing.
APA, Harvard, Vancouver, ISO, and other styles
9

Winterberg, F. "Mini Fission-Fusion-Fission Explosions (Mini-Nukes). A Third Way Towards the Controlled Release of Nuclear Energy by Fission and Fusion." Zeitschrift für Naturforschung A 59, no. 6 (June 1, 2004): 325–36. http://dx.doi.org/10.1515/zna-2004-0603.

Full text
Abstract:
Chemically ignited nuclear microexplosions with a fissile core, a DT reflector and U238 (Th232) pusher, offer a promising alternative to magnetic and inertial confinement fusion, not only burning DT, but in addition U238 (or Th232), and not depending on a large expensive laser of electric pulse power supply. The prize to be paid is a gram size amount of fissile material for each microexplosion, but which can be recovered by breeding in U238.In such a “mini-nuke” the chemical high explosive implodes a spherical metallic shell onto a smaller shell, with the smaller shell upon impact becoming the source of intense black body radiation which vaporizes the ablator of a spherical U238 (Th232) pusher, with the pusher accelerated to a velocity of ∼200 km/s, sufficient to ignite the DT gas placed in between the pusher and fissile core, resulting in a fast fusion neutron supported fission reaction in the core and pusher. Estimates indicate that a few kg of high explosives are sufficient to ignite such a “mini-nuke”, with a gain of ∼103, releasing an energy equivalent to a few tons of TNT, still manageable for the microexplosion to be confined in a reactor vessel.A further reduction in the critical mass is possible by replacing the high explosive with fast moving solid projectiles. For light gas gun driven projectiles with a velocity of ∼ 10 km/s, the critical mass is estimated to be 0.25 g, and for magnetically accelerated 25 km/s projectiles it is as small as ∼ 0.05 g.With the much larger implosion velocities, reached by laser- or particle beam bombardment of the outer shell, the critical mass can still be much smaller with the fissile core serving as a fast ignitor.Increasing the implosion velocity decreases the overall radius of the fission-fusion assembly in inverse proportion to this velocity, for the 10 km/s light gas gun driven projectiles from 10 cm to 5 cm, for the 25 km/s magnetically projectiles down to 2 cm, and still more for higher implosion velocities.
APA, Harvard, Vancouver, ISO, and other styles
10

Li, Jia, and Shanliang Zheng. "Feasibility Study to Byproduce Medical Radioisotopes in a Fusion Reactor." Molecules 28, no. 5 (February 22, 2023): 2040. http://dx.doi.org/10.3390/molecules28052040.

Full text
Abstract:
Currently, international nuclear fission reactors producing medical isotopes face the problem of shutdown and maintenance, decommissioning, or dismantling, while the production capacity of domestic research reactors for medical radioisotopes is inadequate, and the supply capacity for medical radioisotopes faces major challenges in the future. Fusion reactors are characterized by high neutron energy, high flux density, and the absence of highly radioactive fission fragments. Additionally, compared to fission reactors, the reactivity of the fusion reactor core is not significantly affected by the target material. By building a preliminary model of the China Fusion Engineering Test Reactor (CFETR), a Monte Carlo simulation was performed for particle transport between different target materials at a fusion power of 2 GW. The yields (specific activity) of six medical radioisotopes (14C, 89Sr, 32P, 64Cu, 67Cu, and 99Mo) with various irradiation positions, different target materials, and different irradiation times were studied, and compared with those of other high-flux engineering test reactors (HFETR) and the China Experimental Fast Reactor (CEFR). The results show that this approach not only provides competitive medical isotope yield, but also contributes to the performance of the fusion reactor itself, e.g., tritium self-sustainability and shielding performance.
APA, Harvard, Vancouver, ISO, and other styles
More sources

Dissertations / Theses on the topic "Fission Reactor Physic"

1

ABRATE, NICOLO'. "Methods for safety and stability analysis of nuclear systems." Doctoral thesis, Politecnico di Torino, 2022. http://hdl.handle.net/11583/2971611.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Kennedy, William B. (William Blake) 1979. "Analysis of the MIT research reactor fission product and actinide radioactivity inventories." Thesis, Massachusetts Institute of Technology, 2004. http://hdl.handle.net/1721.1/32723.

Full text
Abstract:
Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Physics, 2004.
MIT Institute Archives copy: leaves 92-111 bound in reverse order.
Includes bibliographical references (leaf 57).
The current analysis of the MITR core radioactivity inventory eliminates unnecessary assumptions made in previous estimates of the inventory, and revises the list of contributory isotopes to include all actinide and fission product isotopes necessary for a proper accident source term calculation. The result is a power-history-dependent inventory that increases with bum-up, and comprises 41 actinide isotopes and 596 fission product isotopes. The analysis uses the ORIGEN2 depletion code to calculate the activity of actinide and fission product isotopes for eight MITR input models at 32 intervals over a period of 5376MWD. The input models simulate a MITR core loaded with high- enrichment, U-Alx cermet fuel or low-enrichment, monolithic U-Mo fuel, and operated at 6MW with a continuous-burn-up or cyclic-burn-up-and-decay power history. Reorganization of the ORIGEN2 output file, and application of an element reduction criterion creates the condensed matrix file for each MITR input model. This file lists the contribution of each isotope to the core radioactivity inventory at each output interval, and is the basis for all inventory analysis. The inventory analysis yields three important conclusions. First, the assumption of an equilibrium inventory of isotopes in the fuel is accurate to within 3% for all time after 10% fuel bum-up, and conservative over the entire fuel cycle. The equilibrium fuel assumption is invalid for the actinides due to a slow rate of inventory growth. Second, the cyclic-bum-up-and-decay power history yields a lower core inventory than the continuous-burn-up power history for both fuel enrichments. The difference is minimized by increasing the ratio of irradiation time to decay time.
(cont.) Finally, the analysis indicates that conversion to a U-Mo fuel will produce an actinide inventory 18 times greater than that of the current U-Alx fuel, with no significant change in the fission product inventory. However, the actinide inventory is a small fraction of the fission product inventory. The worst-case core inventory available for release is 2.91 E+7Ci for the high-enrichment fuel, and 2.94E+7Ci for the low-enrichment fuel, with a core loading of 24 elements in each case. The best-estimate core inventory available for release is 2.83E+7Ci, and 2.82E+7Ci respectively, and accounts for typical cyclic operation of the MITR.
by William B. Kennedy.
S.B.
APA, Harvard, Vancouver, ISO, and other styles
3

Lapinski, Felicia. "Experimental studies at CERN-nTOF of the 230Th(n,f) reaction." Thesis, Uppsala universitet, Tillämpad kärnfysik, 2020. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-417867.

Full text
Abstract:
This work investigates the feasibility to perform an experiment at CERN n_TOF to study the fission cross section and fission fragment angular distribution (FFAD) of the 230Th(n,f) reaction. An analysis of fission fragment energy losses in the experimental target resulted in a choice of target thickness of 0.1 µm (100 µg/cm2 ), which yields good transmission out of the target at up to 45° emission angles from the target normal. A detection setup using ten PPAC detectors with nine thorium targets interleaved in between them was investigated, where the detectors and targets were tilted 45° with respect to the neutron beam. This makes it possible to measure all emission angles needed with respect to the neutron beam in order to determine the FFAD. For the experimental area EAR2 at n_TOF, a prediction of the count rate in the experiment resulted in low statistical uncertainties after a few weeks of beam time, which indicates that an experiment like this is feasible.
Detta projekt undersöker genomförbarheten av ett experiment vid CERN n_TOF för att mäta tvärsnittet och fördelningen av emissionsvinklar av fissionsfragment (FFAD) från 230Th(n,f)-reaktionen. En analys av energiförlusterna av fissionsfragment inuti torium-provet resulterade i en optimal provtjocklek på 0.1 µm (100 µg/cm2 ), vilket medför att fissionsfragment som emitteras i vinklar upp till 45° från provets normal har hög sannolikhet att transmitteras ut ur provet. En detektionsuppställning med tio PPAC-detektorer med nio toriumprov mellan dem undersöktes, där detektorerna och proven antogs vara snedställda med 45° från neutronstrålens riktning. Detta möjliggör detektion av fissionsfragment i alla vinklar som är nödvändiga för att kunna mäta hela FFAD. För experimentanläggningen EAR2 vid n_TOF, resulterade en uppskattning av antalet detekterade fissionsevent per sekund i låga mätosäkerheter efter ett par veckor av mättid, vilket antyder att experimentet är görbart.
APA, Harvard, Vancouver, ISO, and other styles
4

Kern, Kilian [Verfasser]. "Advanced Treatment of Fission Yield Effects and Method Development for Improved Reactor Depletion Calculations / Kilian Kern." Karlsruhe : KIT Scientific Publishing, 2019. http://www.ksp.kit.edu.

Full text
APA, Harvard, Vancouver, ISO, and other styles
5

Kern, Kilian [Verfasser], and R. [Akademischer Betreuer] Stieglitz. "Advanced Treatment of Fission Yield Effects and Method Development for Improved Reactor Depletion Calculations / Kilian Kern ; Betreuer: R. Stieglitz." Karlsruhe : KIT-Bibliothek, 2018. http://d-nb.info/1174252227/34.

Full text
APA, Harvard, Vancouver, ISO, and other styles
6

Todd, Jamie R. D. (James Robert Drysdale). "Angular distributions and kinetic energies of fission products from the 238U(12C,f) reaction." Thesis, McGill University, 1991. http://digitool.Library.McGill.CA:80/R/?func=dbin-jump-full&object_id=59911.

Full text
Abstract:
The angular anisotropy, $ omega$, of individual fission products produced from the $ sp{238} rm U( sp{12}$C, f) 119.9 MeV incident heavy-ion induced fission reaction, was modelled in terms of the angular momentum, l, conferred upon the intermediate nucleus. Evidence of incomplete momentum transfer led to a model treating fission products as being the result of two fission inducing processes: complete fusion resulting in compound nucleus formation, and an $ alpha$-transfer incomplete fusion process. The average angular anisotropies for each of the two processes were calculated to be, $ omega sb{ rm CF}$ = 2.57, and $ omega sb alpha$ = 1.71, respectively, which fit well to the experimental data. A new method was developed to estimate the total kinetic energy release of heavy-ion fission events leading to individual fission products from the above reaction. The average total $ langle$E$ sb{ rm k}{ rangle} approx 195$ MeV calculated using the new method is consistent with other experimental data, and with theories regarding heavy-ion induced fission.
APA, Harvard, Vancouver, ISO, and other styles
7

Birgersson, Evert. "Determination of binary fission-fragment yields in the reaction 251Cf(nth, f) and Verification of nuclear reaction theory predictions of fission-fragment distributions in the reaction 238U(n, f)." Doctoral thesis, Örebro : Institutionen för naturvetenskap Department of Natural Sciences, 2007. http://urn.kb.se/resolve?urn=urn:nbn:se:oru:diva-1474.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

Prokofiev, Alexander. "Nucleon-Induced Fission Cross Sections of Heavy Nuclei in the Intermediate Energy Region." Doctoral thesis, Uppsala : Acta Universitatis Upsaliensis : Univ.-bibl. [distributör], 2001. http://publications.uu.se/theses/91-554-5009-1/.

Full text
APA, Harvard, Vancouver, ISO, and other styles
9

Dufek, Jan. "Development of New Monte Carlo Methods in Reactor Physics : Criticality, Non-Linear Steady-State and Burnup Problems." Doctoral thesis, Stockholm : Skolan för teknikvetenskap, Kungliga Tekniska högskolan, 2009. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-10602.

Full text
APA, Harvard, Vancouver, ISO, and other styles
10

Skwarcan-Bidakowski, Alexander. "Nuclear reactor core model for the advancednuclear fuel cycle simulator FANCSEE. Advanceduse of Monte Carlo methods in nuclear reactorcalculations." Thesis, Institutionen för Reaktorfysik, 2017. http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-324260.

Full text
Abstract:
A detailed reactor core modeling of the LOVIISA-2 PWR and FORSMARK-3BWR was performed in the Serpent 2 Continuous Energy Monte-Carlocode.Both models of the reactors were completed but the approximations ofthe atomic densities of nuclides present in the core differedsignificantly.In the LOVIISA-2 PWR, the predicted atomic density for the nuclidesapproximated by Chebyshev Rational Approximation method (CRAM)coincided with the corrected atomic density simulated by the Serpent2 program. In the case of FORSMARK-3 BWR, the atomic density fromCRAM poorly approximated the data returned by the simulation inSerpent 2. Due to boiling of the moderator in the core of FORSMARK-3,the model seemed to encounter problems of fission density, whichyielded unusable results.The results based on the models of the reactor cores are significantto the FANCSEE Nuclear fuel cycle simulator, which will be used as adataset for the nuclear fuel cycle burnup in the reactors.
FANCSEE
APA, Harvard, Vancouver, ISO, and other styles
More sources

Books on the topic "Fission Reactor Physic"

1

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

Find full text
APA, Harvard, Vancouver, ISO, and other styles
2

G, McHugh, Merrick A. R, and Royal Society (Great Britain), eds. The Fast-neutron-breeder fission reactor. London: Royal Society, 1990.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
3

Slugeň, Vladimír. Safety of VVER-440 reactors: Barriers against fission products release. London: Springer, 2011.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
4

Meeting, Royal Society (Great Britain) Discussion. The fast-neutron breeder fission reactor: Proceedings of a Royal Society dicussion meeting held on 24 and 25 May 1989. London: Royal Society, 1990.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
5

Napoli, Museo nazionale di. Complete Unified Theory, Nirmalendu Das: Key words: mass of a photon & a graviton, unification of physics, value of Pi at excited state, unknown weight of radioactive elements, fission reaction of uranium, gamma ray burst, black hole properties through complete unified theory. Edited by De Petra Giulio and Italy Ministero dell'educazione nazionale. Bani Prokash (P) Limited, Panbazar, Guwahati -781001, Assam, India: G.P.Dev Choudhury, Bani Prokash (P) Limited, Panbazar, Guwahati - 781001, Assam, India in G.P.Dev Choudhury, Bani Prokash (P) Limited, Panbazar, Guwahati - 781001, Assam, India ., 1998.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
6

Stacey, Weston M. Nuclear Reactor Physics. Wiley & Sons, Limited, John, 2018.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
7

Nuclear Reactor Physics. Wiley-Interscience, 2001.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
8

Stacey, Weston M. Nuclear Reactor Physics. Wiley & Sons, Incorporated, John, 2018.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
9

Stacey, Weston M. Nuclear Reactor Physics. Wiley & Sons, Incorporated, John, 2018.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
10

Stacey, Weston M. Nuclear Reactor Physics. Wiley & Sons, Incorporated, John, 2018.

Find full text
APA, Harvard, Vancouver, ISO, and other styles
More sources

Book chapters on the topic "Fission Reactor Physic"

1

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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
3

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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
4

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.

Full text
APA, Harvard, Vancouver, ISO, and other styles
5

Masterson, Robert E. "Nuclear Fission and Nuclear Energy Production." In Introduction to Nuclear Reactor Physics, 319–65. 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/10.1201/9781315118055-7.

Full text
APA, Harvard, Vancouver, ISO, and other styles
6

Masterson, Robert E. "Fission Products, Xenon Transients, and Reactor Accidents." In Introduction to Nuclear Reactor Physics, 877–910. 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/10.1201/9781315118055-21.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

Kessler, Günter. "Some Basic Physics of Converters and Breeder Reactors." In Sustainable and Safe Nuclear Fission Energy, 25–57. Berlin, Heidelberg: Springer Berlin Heidelberg, 2012. http://dx.doi.org/10.1007/978-3-642-11990-3_3.

Full text
APA, Harvard, Vancouver, ISO, and other styles
8

Sekine, T., and T. Aoyama. "Fission Rate Analysis of a Fast Reactor Fuel Performance Test Using MCNP." In Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications, 737–42. Berlin, Heidelberg: Springer Berlin Heidelberg, 2001. http://dx.doi.org/10.1007/978-3-642-18211-2_117.

Full text
APA, Harvard, Vancouver, ISO, and other styles
9

Pyeon, Cheol Ho. "Neutron Spectrum." In Accelerator-Driven System at Kyoto University Critical Assembly, 125–56. Singapore: Springer Singapore, 2021. http://dx.doi.org/10.1007/978-981-16-0344-0_5.

Full text
Abstract:
AbstractThe subcritical multiplication factor is considered an important index for recognizing, in the core, the number of fission neutrons induced by an external neutron source. In this study, the influences of different external neutron sources on core characteristics are carefully monitored. Here, the high-energy neutrons generated by the neutron yield at the location of the target are attained by the injection of 100 MeV protons onto these targets. In actual ADS cores, liquid Pb–Bi has been selected as a material for the target that generates spallation neutrons and for the coolant in fast neutron spectrum cores. The neutron spectrum information is acquired by the foil activation method in the 235U-fueled and Pb–Bi-zoned fuel region of the core, modeling the Pb–Bi coolant core locally around the central region. The neutron spectrum is considered an important parameter for recognizing information on neutron energy at the target. Also, the neutron spectrum evaluated by reliable methodologies could contribute to the accurate prediction of reactor physics parameters in the core through numerical simulations of desired precision. In the present chapter, experimental analyses of high-energy neutrons over 20 MeV are conducted after adequate preparation of experimental settings.
APA, Harvard, Vancouver, ISO, and other styles
10

Tzykanov, V. A., V. N. Golovanov, V. K. Shamardin, F. N. Kryukov, and A. V. Povstyanko. "Corrosion of Fast-Reactor Claddings by Physical and Chemical Interaction with Fuel and Fission Products." In NATO Science for Peace and Security Series C: Environmental Security, 281–93. Dordrecht: Springer Netherlands, 2007. http://dx.doi.org/10.1007/978-1-4020-5903-2_19.

Full text
APA, Harvard, Vancouver, ISO, and other styles

Conference papers on the topic "Fission Reactor Physic"

1

Pal, Usha, and V. Jagannathan. "Physics Principles to Achieve Comparable Fission Power From Fertile and Fissile Rods of the Conceptual ATBR/FTBR Reactors." In 16th International Conference on Nuclear Engineering. ASMEDC, 2008. http://dx.doi.org/10.1115/icone16-48381.

Full text
Abstract:
Loading of seedless fertile rods has been used as the central principle to maximize fertile to fissile conversion in the two thorium breeder reactor concepts, viz. ATBR and FTBR [1, 2]. At fresh state the seedless thoria rods will produce practically no fission power, or nearly thousand times less fission rate compared to the seed fuel rods. Hence it is conceived that the fuel assembly would be constituted by assembling the fresh seed rods with one fuel cycle irradiated fertile thoria rods. Even in this state there is a wide disparity between the fissile content of these rods. By judicious choice of the rod dimensions and their relative locations, a degree of balance in the fission rate is achieved in the fresh state of seeded rods. Remarkably as the burnup proceeds the initially seedless fertile rods have a continuous growth of fissile content up to an asymptotic value for a given spectrum and the fissile content in seeded rods monotonically decreases. If the discharge burnup is sufficiently large by design, it is seen that the power share of the initially seedless fertile rods can even exceed that of the seed fuel rods. The physics principles of achieving this characteristic are presented in this paper.
APA, Harvard, Vancouver, ISO, and other styles
2

Pahladsingh, Remond R. "Possibility of Using Gamma Radiation From HTR Reactors for Processing of Food and Medical Products." In 12th International Conference on Nuclear Engineering. ASMEDC, 2004. http://dx.doi.org/10.1115/icone12-49316.

Full text
Abstract:
During the fission process in most of the presently operating nuclear reactors nuclear energy is converted into thermal energy and transferred to common steamcycles for powergeneration. As part of the fission process also α-, β- and neutrons particles are released from the nucleus; the release of gamma-rays is also a part of the fission process. In present nuclear reactors α-, β-, neutrons particles and particularly Gamma-rays are not gainfully used as a result of the reactor design and of the containment. These plants are built as required by regulations and international standards for safety. The inherently safe HTR reactor, by its physics and design, does not need a special reinforced containment and it is worth looking into the possibilities of this design feature to use the by-products, such as Gamma-rays, from nuclear fission. In the HTR Pebble Bed Reactors the α-, and β-particles will remain in the kernels in the pebbles. This means that only the neutron particles and gamma-rays will be available outside the reactor pressure vessel. In this report a proposal is presented to use the gamma-rays of the HTR reactor for irradiation of food and agricultural produce. For neutron shielding a reflector is placed inside the reactor while outside the reactor neutron- and thermal-shielding will be accomplished with water. The high energy gamma-rays will pass through the water-shield and could be harnessed for radiation processing of food and medical products.
APA, Harvard, Vancouver, ISO, and other styles
3

Yan, Xuesong, Yaling Zhang, Yucui Gao, and Lei Yang. "Conceptual Study of Neutron Physics of Nuclear Fuel Cycle for Ceramic Fast Reactor." In 2021 28th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2021. http://dx.doi.org/10.1115/icone28-65406.

Full text
Abstract:
Abstract To make the nuclear fuel cycle more economical and convenient, as well as prevent nuclear proliferation, the conceptual study of a simple high-temperature dry reprocessing of spent nuclear fuel (SNF) for a ceramic fast reactor is proposed in this paper. This simple high-temperature dry (HT-dry) reprocessing includes the Atomics International Reduction Oxidation (AIROX) process and purification method for rare-earth elements. After removing the part of fission products from SNF by a HT-dry reprocessing without fine separation, the remaining nuclides and some uranium are fabricated into fresh fuel which can be used back to the ceramic fast reactor. Based on the ceramic coolant fast reactor, we studied neutron physics of nuclear fuel cycle which consists operation of ceramic reactor, removing part of fission products from SNF and preparation of fresh fuels for many time. The parameters of the study include effective multiplication factor (Keff), beam density, and nuclide mass for different ways to remove the fission products from SNF. With the increase in burnup time, the trend of increasing 239Pu gradually slows down, and the trend of 235U gradually decreases and become balanced. For multiple removal of part of fission products in the nuclear fuel cycle, the higher the removal, the larger the initial Keff.
APA, Harvard, Vancouver, ISO, and other styles
4

Schmidt, J. J. "NUCLEAR DATA - THEIR IMPORTANCE AND APPLICATION IN FISSION REACTOR PHYSICS CALCULATIONS." In Proceedings of the Workshop. WORLD SCIENTIFIC, 1991. http://dx.doi.org/10.1142/9789814439398_0001.

Full text
APA, Harvard, Vancouver, ISO, and other styles
5

Verfondern, Karl, and Heinz Nabielek. "Fission Product Release From HTGR Fuel Under Core Heatup Accident Conditions." In Fourth International Topical Meeting on High Temperature Reactor Technology. ASMEDC, 2008. http://dx.doi.org/10.1115/htr2008-58160.

Full text
Abstract:
Various countries engaged in the development and fabrication of modern fuel for the High Temperature Gas-Cooled Reactor (HTGR) have initiated activities of modeling the fuel and fission product release behavior with the aim of predicting the fuel performance under operating and accidental conditions of future HTGRs. Within the IAEA directed Coordinated Research Project CRP6 on “Advances in HTGR Fuel Technology Development” active since 2002, the 13 participating Member States have agreed upon benchmark studies on fuel performance during normal operation and under accident conditions. While the former has been completed in the meantime, the focus is now on the extension of the national code developments to become applicable to core heatup accident conditions. These activities are supported by the fact that core heatup simulation experiments have been resumed recently providing new, highly valuable data. Work on accident performance will be — similar to the normal operation benchmark — consisting of three essential parts comprising both code verification that establishes the correspondence of code work with the underlying physical, chemical and mathematical laws, and code validation that establishes reasonable agreement with the existing experimental data base, but including also predictive calculations for future heating tests and/or reactor concepts. The paper will describe the cases to be studied and the calculational results obtained with the German computer model FRESCO. Among the benchmark cases in consideration are tests which were most recently conducted in the new heating facility KUEFA. Therefore this study will also re-open the discussion and analysis of both the validity of diffusion models and the transport data of the principal fission product species in the HTGR fuel materials as essential input data for the codes.
APA, Harvard, Vancouver, ISO, and other styles
6

Ottewitte, E. H. "Large scale positron production for physics needs via fission reactors." In AIP Conference Proceedings Volume 156. AIP, 1987. http://dx.doi.org/10.1063/1.36457.

Full text
APA, Harvard, Vancouver, ISO, and other styles
7

Chen, Xiaoliang, Zhendong Fan, Xiaoxian Chen, and Dingsheng Hu. "Measurement of Reaction Rate Distribution and Neutron Spectrum in China Experimental Fast Reactor." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-16413.

Full text
Abstract:
China Experimental Fast Reactor (CEFR) has completed physics start-up tests in 2010 and connected the grid on 40%FP in 2011. The reaction rate distribution, neutron spectrum are some important parameters for CEFR neutron field. In order to measure these parameters some low power irradiation tests using foil activation method have been done in CEFR core. Two kinds of special irradiation test subassemblies have been developed and fabricated for irradiation in CEFR core. And a digital high purity Germanium gamma-ray spectrometer system has been established for foil activity measurement. After dozens of low power irradiation tests in CEFR core, the radial and axial distribution of 235U and 238U fission reaction rate have been measured. The distribution of 238U capture reaction rate in CEFR core was also obtained in these tests. The experimental values of reaction rate are according with the calculation values well. Neutron spectrum was measured by means of multifoil activation method. And a neutron spectrum adjusting code was also compiled to determine the neutron spectrum.
APA, Harvard, Vancouver, ISO, and other styles
8

Bakharev, N. N., F. V. Chernyshev, V. V. Dyachenko, V. K. Gusev, N. A. Khromov, E. O. Kiselev, A. N. Konovalov, et al. "Globus-M2 experiments in scope of fusion-fission reactor development." In PROCEEDINGS OF THE INTERNATIONAL CONFERENCE ON ADVANCES AND APPLICATIONS IN PLASMA PHYSICS (AAPP 2019). AIP Publishing, 2019. http://dx.doi.org/10.1063/1.5135474.

Full text
APA, Harvard, Vancouver, ISO, and other styles
9

Liu, Rong, and Wenzhong Zhou. "Fully Coupled Multiphysics Simulation of Enhanced Thermal Conductivity UO2-BeO Fuel Behavior." In ASME 2015 International Mechanical Engineering Congress and Exposition. American Society of Mechanical Engineers, 2015. http://dx.doi.org/10.1115/imece2015-52504.

Full text
Abstract:
Commercial light water reactor fuel UO2 has a low thermal conductivity that leads to the development of a large temperature gradient across the fuel pellet, limiting the reactor operational performance due to the effects that include thermal stresses causing pellet cladding interaction and the release of fission product gases. This study presents the development of a modeling and simulation for enhanced thermal conductivity UO2-BeO fuel behavior in a light water reactor, using self-defined multiple physics models fully coupled based on the framework of COMSOL Multiphysics. Almost all the related physical models are considered, including heat generation and conduction, species diffusion, thermomechanics (thermal expansion, elastic strain, densification, and fission product swelling strain), grain growth, fission gas production and release, gap heat transfer, mechanical contact, gap/plenum pressure with plenum volume, cladding thermal and irradiation creep and oxidation. All the phenomenal models and materials properties are implemented into COMSOL Multiphysics finite-element platform with a 2D axisymmetric geometry of a fuel pellet and cladding. UO2-BeO high thermal conductivity nuclear fuel would decrease fuel temperatures and facilitate a reduction in pellet cladding interaction from our simulation results through lessening thermal stresses that result in fuel cracking, relocation, and swelling, so that the safety of the reactor would be improved.
APA, Harvard, Vancouver, ISO, and other styles
10

Zhou, Jianjun, Suizheng Qiu, Zhangpeng Guo, and Guanghui Su. "The Optimization Design of Lower Plenum and Distribution Plates in MSR." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-16436.

Full text
Abstract:
Molten salt reactor was one of six Generation IV reactor types, which uses the liquid molten salt as the coolant and fuel solvent. In transmutation of actinides and long-lived fission products have marked advantages. As a liquid reactor the physical property and thermo-characteristic is different to solid fuel and water coolant reactors, which was influenced by many factors. MOSART was one of the advanced molten salt reactors concept design, which can burners TRU from LWR spent fuel. The reactor core does not contain graphite structure elements, so the flow pattern was potentially complex and may significantly affect the fuel temperature distributions. The optimizations of the salt flow may be needed, the present work designed three core models and three kinds of distribution plates to investigate the influence of lower plenum and distribution plates to thermohydraulics characteristics of the reactor core with CFD method use software FLUENT. Velocity field and maximum temperature of the core was simulated in each model at different mass flow rate.
APA, Harvard, Vancouver, ISO, and other styles

Reports on the topic "Fission Reactor Physic"

1

Kaganas, G., and J. Rest. A physical description of fission product behavior fuels for advanced power reactors. Office of Scientific and Technical Information (OSTI), October 2007. http://dx.doi.org/10.2172/919331.

Full text
APA, Harvard, Vancouver, ISO, and other styles
2

Youinou, Gilles Jean-Michel. MANTA. An Integral Reactor Physics Experiment to Infer the Neutron Capture Cross Sections of Actinides and Fission Products in Fast and Epithermal Spectra. Office of Scientific and Technical Information (OSTI), October 2015. http://dx.doi.org/10.2172/1261040.

Full text
APA, Harvard, Vancouver, ISO, and other styles
You might also be interested in the extended bibliographies on the topic 'Fission Reactor Physic' for particular source types:
Journal articles Dissertations / Theses Books
We offer discounts on all premium plans for authors whose works are included in thematic literature selections. Contact us to get a unique promo code!

To the bibliography