Relevant bibliographies by topics / Photon and neutron fluences

Contents

  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Photon and neutron fluences'

Author: Grafiati
Published: 4 June 2021
Last updated: 1 February 2022

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Journal articles on the topic "Photon and neutron fluences"

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Mesbahi, Asghar, and Rezvan Khaldari. "Neutron and photon scattering properties of high density concretes used in radiation therapy facilities: A Monte Carlo study." Polish Journal of Medical Physics and Engineering 23, no. 3 (2017): 61–65. http://dx.doi.org/10.1515/pjmpe-2017-0011.

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Abstract In the current study the neutron and photon scattering properties of some newly developed high density concretes (HDCs) were calculated by using MCNPX Monte Carlo code. Five high-density concretes including Steel-Magnetite, Barite, Datolite-Galena, Ilmenite-ilmenite, Magnetite-Lead with the densities ranging from 5.11 g/cm3 and ordinary concrete with density of 2.3 g/cm3 were studied in our simulations. The photon beam spectra of 4 and 18 MV from Varian linac and neutron spectra of clinical 18 MeV photon beam was used for calculations. The fluence of scattered photon and neutron from all studied concretes was calculated in different angles. Overall, the ordinary concrete showed higher scattered photons and Datolite-Galena concrete (4.42 g/cm3) had the lowest scattered photons among all studied concretes. For neutron scattering, fluence at the angle of 180 was higher relative to other angles while for photons scattering fluence was maximum at 90 degree. The scattering fluence for photons and neutrons was dependent on the angle and composition of concrete. The results showed that the fluence of scattered photons and neutrons changes with the composition of high density concrete. Also, for high density concretes, the variation of scattered fluence with angle was very pronounced for neutrons but it changed slightly for photons. The results can be used for design of radiation therapy bunkers.
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Luszik-Bhadra, M., M. Reginatto, and V. Lacoste. "Measurement of energy and direction distribution of neutron and photon fluences in workplace fields." Radiation Protection Dosimetry 110, no. 1-4 (2004): 237–41. http://dx.doi.org/10.1093/rpd/nch179.

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Lei JiaRong, Yuan Yong Gang, Zhao Lin, Zhao Min Zhi та Cui Gao Xian. "Investigations of the photon fluences in various n+γ\=mixed fields in the fast neutron reactor". Acta Physica Sinica 52, № 1 (2003): 53. http://dx.doi.org/10.7498/aps.52.53.

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Haddad, Kh, O. Anjak, and B. Yousef. "Neutron and high energy photon fluence estimation in CLINAC using gold activation foils." Reports of Practical Oncology & Radiotherapy 24, no. 1 (2019): 41–46. http://dx.doi.org/10.1016/j.rpor.2018.08.009.

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Shekhtman, L., F. Ignatov, and V. Tayursky. "Simulation of physics background in Super c-tau factory detector." EPJ Web of Conferences 212 (2019): 01009. http://dx.doi.org/10.1051/epjconf/201921201009.

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Simulation of background particle fluxes generated by colliding beams is performed with FLUKA package for the Super C-Tau factory Detector (SCTD). Two processes are considered as main sources of luminosity generated background: two-photon production of electron-positron pairs and Bha-Bha scattering with bremsstrahlung photon emission (radiative Bha-Bha). The SCTD geometry is described corresponding to the last version of the Conceptual Design Report. The magnetic field based on the calculation in ANSYS is introduced in the model. Main results of the simulation for beam energy of 3 GeV, luminosity of 1035 cm−2s−1 and 1.5 T magnetic field are the following: charged particle fluence in the region of the Inner Tracker (radius 5cm -20 cm, Z between -30cm and 30 cm) is between 105 particles/(cm2s) and ∼103 particles/(cm2s); 1-MeV neutron equivalent fluence for Si in the regions corresponding to electronics of the Inner Tracker and the Drift Chamber is below 1011 n/(cm2y) and absorbed dose is below 100 Gy/y in the hottest regions of the detector.
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Calvi, M., P. Carniti, C. Gotti, C. Matteuzzi, and G. Pessina. "Single photon detection with SiPMs irradiated up to 1014 cm−2 1-MeV-equivalent neutron fluence." Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 922 (April 2019): 243–49. http://dx.doi.org/10.1016/j.nima.2019.01.013.

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Vysakh, R., M. M. Musthafa, C. V. Midhun, et al. "Experimental determination of thermal neutron fluence around Elekta Versa HD linear accelerator for various photon energies." Biomedical Physics & Engineering Express 6, no. 5 (2020): 055018. http://dx.doi.org/10.1088/2057-1976/abac90.

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Abdullaiev, A., S. Soldatov, V. Hann, and S. Chernitskyi. "Calculation of Neutron Fluence and Energy Release in WWER-1000 Structural Components Using Monte Carlo Method." Nuclear and Radiation Safety, no. 1(77) (February 19, 2018): 11–17. http://dx.doi.org/10.32918/nrs.2018.1(77).02.

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The paper describes the methodology for the calculation of neutron fluence and energy release in WWER-1000 reactor cavity and baffle using the Monte Carlo MCNPX code. It formulates an approach to the simulation of a 3-D neutron source and conditions for the transport of neutrons and photons in the core. The research presents preliminary results of neutron fluence and energy release calculation in WWER-1000 reactor cavity and baffle.
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Kowalik, Anna, Weronika Jackowiak, Julian Malicki, et al. "Measurements of doses from photon beam irradiation and scattered neutrons in an anthropomorphic phantom model of prostate cancer: a comparison between 3DCRT, IMRT and tomotherapy." Nukleonika 62, no. 1 (2017): 29–35. http://dx.doi.org/10.1515/nuka-2017-0005.

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Abstract Introduction. The rapid development of new radiotherapy technologies, such as intensity modulated radiotherapy (IMRT) or tomotherapy, has resulted in the capacity to deliver a more homogenous dose in the target. However, the higher doses associated with these techniques are a reason for concern because they may increase the dose outside the target. In the present study, we compared 3DCRT, IMRT and tomotherapy to assess the doses to organs at risk (OARs) resulting from photon beam irradiation and scattered neutrons. Material and methods. The doses to OARs outside the target were measured in an anthropomorphic Alderson phantom using thermoluminescence detectors (TLD 100) 6Li (7.5%) and 7Li (92.5%). The neutron fluence rate [cm−2·s−1] at chosen points inside the phantom was measured with gold foils (0.5 cm diameter, mean surface density of 0.108 g/cm3). Results. The doses [Gy] delivered to the OARs for 3DCRT, IMRT and tomotherapy respectively, were as follows: thyroid gland (0.62 ± 0.001 vs. 2.88 ± 0.004 vs. 0.58 ± 0.003); lung (0.99 ± 0.003 vs. 4.78 ± 0.006 vs. 0.67 ± 0.003); bladder (80.61 ± 0.054 vs. 53.75 ± 0.070 vs. 34.71 ± 0.059); and testes (4.38 ± 0.017 vs. 6.48 ± 0.013 vs. 4.39 ± 0.020). The neutron dose from 20 MV X-ray beam accounted for 0.5% of the therapeutic dose prescribed in the PTV. The further from the field edge the higher the contribution of this secondary radiation dose (from 8% to ~45%). Conclusion. For tomotherapy, all OARs outside the therapeutic field are well-spared. In contrast, IMRT achieved better sparing than 3DCRT only in the bladder. The photoneutron dose from the use of high-energy X-ray beam constituted a notable portion (0.5%) of the therapeutic dose prescribed to the PTV.
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Sajo-Bohus, Laszlo, H. R. Vega-Carrillo, and Hardev Singh Virk. "SSNTD Technique in Photo-Neutron Applications." Solid State Phenomena 239 (August 2015): 180–214. http://dx.doi.org/10.4028/www.scientific.net/ssp.239.180.

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Passive Solid State Nuclear Track Detectors (SSNTDs) are a versatile tool for neutron studies as has been shown long ago and several good quality materials are commercially available. They are useful for charged particle detection in the linear energy transfer (LET) range above the threshold value of ~10 keV μm-1. Linacs, operating above 6 MeV up to the energy region where radiotherapy is applied usually up to ~25MeV, induce unwanted photo-neutron field; their spectra shows two components due to reaction dynamics based on evaporation and knock-on mechanisms. Neutrons produced by Linacs are often neglected in health application; however, today it has become necessary to assess the effect on patient, staff and radiation workers. Radiation studies using SSNTDs play a major role in this case. Other fields also take advantage of the passive detectors properties; in fact they are employed with success to measure neutron signals relevant for plasma diagnostics as it was demonstrated at the RFX facility as part of the ITER project. The PADC-NTD techniques provide information on external neutron field values around the RFX-installation during pulsed operation. In any case, converter materials, as charged particles from (n, p) and (n, α) reactions, are required to produce neutron fingerprints through latent tracks. These once etched provide information on neutron fluence spatial values. Track histograms are then employed to determine photo-neutron induced damage in materials as well as radiation dose to both patient and professionally exposed workers. The estimated neutron fluence that can be determined by NTM covers a large range of values, the largest being above 1010(± 12%) neutrons/cm2.
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Dissertations / Theses on the topic "Photon and neutron fluences"

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Naumann, Bärbel. "Berechnung des Strahlungsuntergrundes in der Umgebung der Strahlfänger an der Strahlungsquelle ELBE." Forschungszentrum Dresden, 2010. http://nbn-resolving.de/urn:nbn:de:bsz:d120-qucosa-29511.

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Beam dumps are installed at the experimental areas of the ELBE facility. Their purpose is to absorb the primary electron beam and the secondary radiation. The beam dump consists of a purified graphite core inside a water cooled stainless steel vessel. The radiation shield surrounding the beam dump will be designed individually for each experimental area. In this context, dose rate calculations were carried out to estimate the dose rate source term around the stainless steel vessel of the beam dump. Detailed Monte Carlo simulations were carried out using the code FLUKA. The energy dependent photon and neutron fluences and the equivalent dose rates were obtained near the surface of the cylindrical steel vessel for a beam current of 1 mA and energies of 20 MeV and 50 MeV.
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Naumann, Bärbel. "Berechnung des Strahlungsuntergrundes in der Umgebung der Strahlfänger an der Strahlungsquelle ELBE." Forschungszentrum Rossendorf, 2002. https://hzdr.qucosa.de/id/qucosa%3A21778.

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Beam dumps are installed at the experimental areas of the ELBE facility. Their purpose is to absorb the primary electron beam and the secondary radiation. The beam dump consists of a purified graphite core inside a water cooled stainless steel vessel. The radiation shield surrounding the beam dump will be designed individually for each experimental area. In this context, dose rate calculations were carried out to estimate the dose rate source term around the stainless steel vessel of the beam dump. Detailed Monte Carlo simulations were carried out using the code FLUKA. The energy dependent photon and neutron fluences and the equivalent dose rates were obtained near the surface of the cylindrical steel vessel for a beam current of 1 mA and energies of 20 MeV and 50 MeV.
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Wooten, Hasani Omar. "Time-Dependent Neutron and Photon Dose-Field Analysis." Diss., Georgia Institute of Technology, 2005. http://hdl.handle.net/1853/7153.

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A unique tool is developed that allows the user to model physical representations of complicated glovebox facilities in two dimensions and determine neutral-particle flux and ambient dose-equivalent fields throughout that geometry. The code Pandemonium, originally designed to determine flux and dose rates only, has been improved to include realistic glovebox geometries, time-dependent source and detector positions, time-dependent shielding thickness calculations, time-integrated doses, a representative criticality accident scenario based on time-dependent reactor kinetics, and more rigorous photon treatment. The photon model has been significantly enhanced by expanding the energy range to 10 MeV to include fission photons, and by including a set of new buildup factors, the result of an extensive study into the previously unknown "purely-angular effect" on photon buildup. Purely-angular photon buildup factors are determined using discrete ordinates and coupled electron-photon cross sections to account for coherent and incoherent scattering and secondary photon effects of bremsstrahlung and florescence. Improvements to Pandemonium result in significant modeling capabilities for processing facilities using intense neutron and photon sources, and the code obtains comparable results to Monte Carlo calculations but within a fraction of the time required to run such codes as MCNPX.
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Schramm, Georg Alexander. "Analysis and simulation of photon scattering and neutron capture gamma spectra." Helmholtz-Zentrum Dresden-Rossendorf, 2014. http://nbn-resolving.de/urn:nbn:de:bsz:d120-qucosa-146889.

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Within this thesis two twin experiments consisting of neutron capture and photon scattering on the neighbour isotopes 77Se / 78Se and 195Pt / 196Pt have been analysed to gain qualitative and quantitative information about the photon strength function and level density in the respective compound nuclei. For the analysis and simulation of both experimental types a new Monte Carlo simulation using a fast and efficient, extreme statistical treatment of radiative nuclear deexcitations, was developed. Furthermore the influence of fluctuations of transition widths on photon scattering were investigated and quantified. It could be shown that those lead to an enhancement of elastic scattering processes. The data analysis of both twin experiments reveals non-Lorentzian extra E1 photon strength below the neutron separation energy.
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Sun, Chengwei. "First measurement of the reaction helium-3(photon,proton -proton)neutron." W&M ScholarWorks, 1990. https://scholarworks.wm.edu/etd/1539623791.

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Differential cross sections for the {dollar}\sp3{dollar}He({dollar}\gamma{dollar},pp)n reaction were measured with a bremsstrahlung beam for kinematics selected in the quasi-free two-nucleon region with neutron recoil q{dollar}\sb{lcub}\rm n{rcub}\approx{dollar} 0. Five photon energy points were taken between 200 and 440 MeV. The two proton detectors were positioned in such a way that the angle of one proton, in the CM of the pp pair, relative to the photon direction is 75{dollar}\sp\circ{dollar}. The data confirm the predicted quenching of the cross section. In the photon energy region from 310 to 440 MeV the data are in agreement with a theoretical prediction based on a diagrammatic description of the process. at lower energies (200 to 310 MeV) the data are about 40% to 70% higher than the predictions. However the shape of the proton momentum spectrum is reproduced when three body mechanisms are included.
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Steer, Steven John. "Isomer decay spectroscopy of N<126 neutron-rich nuclei." Thesis, University of Surrey, 2008. http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.493243.

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Kolomeitsev, E. E., Burkhard Kämpfer, and D. N. Voskresensky. "Contribution of the massive photon decay channel to the neutrino cooling of neutron stars." Forschungszentrum Dresden, 2010. http://nbn-resolving.de/urn:nbn:de:bsz:d120-qucosa-31717.

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The role of the massive photon decay via intermediate states of electron-electron-holes and proton-proton-holes into neutrino-anti-neutrino pairs in the course of neutron star cooling is investigated. These reactions may ba operative in hot neutron stars in the region of proton pairing. The corresponding contribution to the neutrino emissivity is calculated. It varies with the temperature as T3/2e−mγ/T for T < m γ, where mγ is an effective photon mass in superconducting matter. Estimates show that this process appears as strong cooling channel of neutron stars at temperatures T ≈ ( 10^9 - 10^10) K.
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Kolomeitsev, E. E., Burkhard Kämpfer, and D. N. Voskresensky. "Contribution of the massive photon decay channel to the neutrino cooling of neutron stars." Forschungszentrum Rossendorf, 1995. https://hzdr.qucosa.de/id/qucosa%3A21997.

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The role of the massive photon decay via intermediate states of electron-electron-holes and proton-proton-holes into neutrino-anti-neutrino pairs in the course of neutron star cooling is investigated. These reactions may ba operative in hot neutron stars in the region of proton pairing. The corresponding contribution to the neutrino emissivity is calculated. It varies with the temperature as T3/2e−mγ/T for T < m γ, where mγ is an effective photon mass in superconducting matter. Estimates show that this process appears as strong cooling channel of neutron stars at temperatures T ≈ ( 10^9 - 10^10) K.
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Maeda, Yosuke. "Search for the Decay KL→π0νν with a Neutron-Insensitive GeV-Energy Photon Detector". 京都大学 (Kyoto University), 2016. http://hdl.handle.net/2433/215315.

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要旨ファイルを2017-04-17に差替え<br>Kyoto University (京都大学)<br>0048<br>新制・課程博士<br>博士(理学)<br>甲第19502号<br>理博第4162号<br>新制||理||1598(附属図書館)<br>32538<br>京都大学大学院理学研究科物理学・宇宙物理学専攻<br>(主査)教授 中家 剛, 教授 谷森 達, 准教授 成木 恵<br>学位規則第4条第1項該当
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Assatel, Omran. "Characterisation of photon and neutron spectra in medical linear accelerators using theoretical and experimental techniques." Thesis, University of Surrey, 1996. http://epubs.surrey.ac.uk/804743/.

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Books on the topic "Photon and neutron fluences"

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Balcar, Ewald. Theory of magnetic neutron and photon scattering. Clarendon Press, 1989.

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László, Koblinger, ed. Monte Carlo particle transport methods: Neutron and photon calculations. CRC Press, 1991.

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Foton Fakutorī Kenkyūkai (2001 KEK). Heisei 13-nendo PF Kenkyūkai "X-sen chūseishi hansharitsuhō ni yoru hakumaku tasōmaku no kōzō kaiseki": X-ray and neutron reflectivity studies on thin films and multilayers : KEK, Tsukuba, Japan, December 21-22, 2001. High Energy Accelerator Research Organization, 2002.

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Bilanovic, Z. Neutron-photon energy deposition in CANDU reactor fuel channels: A comparison of modelling techniques using ANISN and MCNP computer codes. System Chemistry and Corrosion Branch, Chalk River Laboratories, 1994.

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Lux, Iván, and László Koblinger. Monte Carlo Particle Transport Methods: Neutron and Photon Calculations. CRC Press, 2018. http://dx.doi.org/10.1201/9781351074834.

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International Commission on Radiation Units and Measurements., ed. Photon, electron, proton, and neutron interaction data for body tissues. International Commission on Radiation Units and Measurements, 1992.

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Photon, Electron, Proton & Neutron Interaction Data for Body Tissues (Icru Report 46D). Intl Commission on Radiation, 1992.

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Assatel, Omran Zaid. Characterisation of photon and neutron spectra in medical linear accelerators using theoretical and experimentaltechniques. 1996.

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Monte Carlo Particle Transport Methods. Taylor & Francis Group, 2017.

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Thun, Johan. Studies of the Nuclear Processes of Proton Capture Photon Production and Spallation Neutron Emission With Advanced Experimental Techniques. Uppsala Universitet, 1999.

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Book chapters on the topic "Photon and neutron fluences"

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Lone, M. A. "Photon Strength Functions." In Neutron Induced Reactions. Springer Netherlands, 1986. http://dx.doi.org/10.1007/978-94-009-4636-1_26.

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Wallace, S. A., B. J. Allen, and J. N. Mathur. "Monte Carlo Neutron Photon Treatment Planning Calculations." In Cancer Neutron Capture Therapy. Springer US, 1996. http://dx.doi.org/10.1007/978-1-4757-9567-7_43.

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Tokuuye, Koichi, Yasuyuki Akine, Tooru Kobayashi, and Keiji Kanda. "Assessment of Photon Contributions in Gadolinium Neutron Capture Reactions-A Preliminary Study." In Cancer Neutron Capture Therapy. Springer US, 1996. http://dx.doi.org/10.1007/978-1-4757-9567-7_121.

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Rivard, Mark J., Mark Yudelev, and Jacek G. Wierzbicki. "157Gd Photon Dose Enhancement from a Neutron Emitting 252Cf Point Source." In Frontiers in Neutron Capture Therapy. Springer US, 2001. http://dx.doi.org/10.1007/978-1-4615-1285-1_184.

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Nicola, C. Di, and E. Pedretti. "Uncollided Neutron Fluences in a Mirror-Like Machine (MFTF-B) with Polarized DT Plasmas." In Muon-Catalyzed Fusion and Fusion with Polarized Nuclei. Springer US, 1987. http://dx.doi.org/10.1007/978-1-4757-5930-3_16.

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Nimal, J. C., and T. Vergnaud. "TRIPOLI-3: A Neutron/Photon Monte Carlo Transport Code." In Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications. Springer Berlin Heidelberg, 2001. http://dx.doi.org/10.1007/978-3-642-18211-2_104.

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Hoogenboom, J. E. "Continuous Energy Adjoint Monte Carlo for Coupled Neutron-Photon Transport." In Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications. Springer Berlin Heidelberg, 2001. http://dx.doi.org/10.1007/978-3-642-18211-2_98.

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Mehner, H. C. "Effect of Axial Flux Density Variations on the Determination of Neutron Fluences for LWR-PV Dosimetry." In Proceedings of the Seventh ASTM-Euratom Symposium on Reactor Dosimetry. Springer Netherlands, 1992. http://dx.doi.org/10.1007/978-94-011-2781-3_9.

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Bikondoa, Oier. "X-Ray Photon Correlation Spectroscopy for the Characterization of Soft and Hard Condensed Matter." In X-ray and Neutron Techniques for Nanomaterials Characterization. Springer Berlin Heidelberg, 2016. http://dx.doi.org/10.1007/978-3-662-48606-1_3.

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Kanschat, G. "Parallel Computation of Multi-Dimensional Neutron and Photon Transport in Inhomogeneous Media." In Lecture Notes in Computational Science and Engineering. Springer Berlin Heidelberg, 1999. http://dx.doi.org/10.1007/978-3-642-60155-2_36.

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Conference papers on the topic "Photon and neutron fluences"

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Zheng, Zheng, Hui Li, and Mengqi Wang. "Application of a 3D Discrete Ordinates-Monte Carlo Coupling Method on CAP1400 Cavity Streaming Calculation." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66401.

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Neutrons and photons produced from reactor core during operation pass through the pressure vessel, reach the reactor cavity, and form the reactor cavity streaming. Reactor cavity streaming dose rates calculation during normal operation is important for the evaluation and control of the equipment dose rates in the nuclear power plant. Because reactor is great in dimension and complex in geometry, neutrons and photons fluence rates declined by several orders from reactor core to outside. Cavity streaming calculation is a deep penetration calculation with heavy computation load which is difficult to converge. Three dimensional Discrete Ordinates and Monte Carlo (SN-MC) coupling method combines the advantage of the SN method with high efficiency and the MC method with fine geometrical modeling. The SN-MC coupling method decreases the tally errors and increases the efficiency of the MC method effectively by using MC surface source generated by the SN fluence rates. In this paper, the theoretical model of the 3D SN-MC coupling method is presented. In order to fulfill the coupling calculation, a 3D Discrete Ordinates code is modified to output angular fluence rates, a link code DO2MC is developed to calculate cummulative distribution functions of source particle variables on surface source, and a source subroutine is written for a 3D Monte Carlo code. The 3D SN-MC coupling method is applied on the calculation of the CAP1400 cavity streaming neutron and photon dose rates. Numerical results show that the 3D SN-MC coupling codes are correct, the relative errors of the results are less than 20% compared with those of the MC bootstrapping method, and the efficiency is greatly enhanced.
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Zhou, Yan, Zheng Zheng, and Qiliang Mei. "The Preliminary Shielding Analysis of CAP1400 Based on JMCT-S Code." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66429.

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JMCT-S[1] 3-D high resolution Monte Carlo neutron and photon transport code is proposed for shielding design due to its significant advantages such as complex geometry modeling, accurate calculation method, high efficient parallel computing and visible mass data analysis. To demonstrate its feasibility and benefits in engineering, this paper presents the verification of JMCT-S code based on primary shielding analysis for CAP1400 nuclear power station. Firstly, by employing JMCT-S code this paper completes the modeling and simulations of CAP1400 nuclear power station with full-core pin-by-pin and reactor pressure vessel internals inside of primary shield wall[2]. Secondly, neutron fluence rates are calculated based on the equilibrium cycle information. Particularly, the full-core neutron source is calculated from 3-D power distribution, fissionable nuclide fractions, fission spectrum, particle numbers and energy released per fission. Finally, JMCT-S code is verified by comparing results with those of the MCNP[3] code. According to the calculation results, JMCT-S code has similar accuracy to the MCNP code. The relative error of neutron fluence rate in active core is within ±1.5%, and deviation of neutron fluence rate for fast neutron fluence rate on inner surface of reactor pressure vessel is less than ±10%. Consequently, JMCT-S code is reliable in shielding design of reactor plant which lays the foundation for usage of JMCT-S code.
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Heilbronn, Lawrence, Ashwin Srikrishna, and Daniel Peffley. "Neutron fluences in lunar habitats." In 2015 IEEE Aerospace Conference. IEEE, 2015. http://dx.doi.org/10.1109/aero.2015.7119252.

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Heilbronn, Lawrence, Lawrence Townsend, Chelsea Burnham, et al. "Neutron fluences and doses behind shielded environments in space." In 2014 IEEE Aerospace Conference. IEEE, 2014. http://dx.doi.org/10.1109/aero.2014.6836309.

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Prokopec, R., K. Humer, H. Fillunger, et al. "MECHANICAL BEHAVIOUR OF CYANATE ESTER∕EPOXY BLENDS AFTER REACTOR IRRADIATION TO HIGH NEUTRON FLUENCES." In ADVANCES IN CRYOGENIC ENGINEERING MATERIALS: Transactions of the International Cryogenic Materials Conference - ICMC, Vol. 54. AIP, 2008. http://dx.doi.org/10.1063/1.2900343.

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Dohi, Kenji, Kenji Nishida, Akiyoshi Nomoto, Naoki Soneda, Hiroshi Matsuzawa, and Minoru Tomimatsu. "Effect of Additional Irradiation at Different Fluxes on RPV Embrittlement." In ASME 2009 Pressure Vessels and Piping Conference. ASMEDC, 2009. http://dx.doi.org/10.1115/pvp2009-77658.

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The effect of the neutron flux at high fluence on the microstructural and hardness changes of a reactor pressure vessel (RPV) steel was investigated. An accelerated test reactor irradiation of a RPV material, previously irradiated in commercial reactors, was carried out at the lowest possible neutron fluxes in order to obtain neutron fluences up to approximately 1×1020 n/cm2 (E&amp;gt;1MeV). State-of-the-art experimental techniques such as three-dimensional atom probe were applied to carry out advanced quantitative characterization of defect features in the materials. Results for the same material irradiated in both high and low flux conditions are compared. For neutron fluences above 6×1019 n/cm2 (E&amp;gt;1MeV) the difference in the neutron fluence dependence of the increase in hardness is not seen for any neutron flux condition. The volume fraction of solute atom clusters increases linearly with neutron fluence, and the influence of neutron flux is not significant. The component elements and the chemical composition of the solute atom clusters formed by the irradiation do not change regardless of the neutron fluence and flux. The square root of the volume fraction of the solute atom clusters is a good correlation with the increase in hardness.
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Tomimatsu, Minoru, Hiroyuki Sakamoto, Kenji Dohi, Toshiyuki Watanabe, and Hiroshi Matsuzawa. "Microstrucutural Characterization of RPV Steels Irradiated to High Fluences." In ASME 2009 Pressure Vessels and Piping Conference. ASMEDC, 2009. http://dx.doi.org/10.1115/pvp2009-78103.

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Neutron radiation embrittlement of reactor pressure vessel (RPV) steels is one of critical issues for the structural integrity assessment of the RPVs. Especially, the embrittlement at high fluences is of great interest for the long term operation of light water reactors because information on the mechanical property changes as well as embrittlement mechanisms is limited at high fluences. In this study, microstructural analyses were conducted on the RPV steels irradiated to high fluences in order to confirm the applicability of the trend curve at high fluence region. Steels investigated are five base metals and a weld metal with their copper content ranging from 0.02 to 0.25 wt. %. These steels were irradiated in the material test reactors to fluence up to 1.3 × 1020 n/cm2, E &amp;gt; 1MeV, at temperature of about 290 °C. After irradiation, transmission electron microscope (TEM) observations were performed to characterize the nano-meter scale microstructural changes due to irradiation. Formation of dislocation loops was observed. Number density and diameter of dislocation loop was investigated. Effects of chemical composition of steel and fluence on dislocation loop formation are discussed.
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Sandu, V., S. Popa, E. Sandu, D. Di Gioacchino та P. Tripodi. "Development of Space Instabilities of Defect Distribution at High Fluences in Neutron Irradiated YBa2Cu3O7−δ Ceramics". У SIXTH INTERNATIONAL CONFERENCE OF THE BALKAN PHYSICAL UNION. AIP, 2007. http://dx.doi.org/10.1063/1.2733388.

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Dohi, Kenji, Kenji Nishida, Akiyoshi Nomoto, Naoki Soneda, Hiroshi Matsuzawa, and Minoru Tomimatsu. "Effect of Neutron Flux at High Fluence on Microstructural and Hardness Changes of RPV Steels." In ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/pvp2010-25514.

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The effect of the neutron flux at high fluence on the microstructural and hardness changes of reactor pressure vessel (RPV) steels was investigated in succession to the previous study [1]. An accelerated test reactor irradiation of copper containing RPV materials, previously irradiated in commercial reactors, was carried out at the lowest possible neutron fluxes in order to obtain neutron fluences up to approximately 1×1020 n/cm2 (E&amp;gt;1MeV). State-of-the-art experimental techniques such as three-dimensional atom probe were applied to carry out advanced quantitative characterization of defect features in the materials. Results for the same materials irradiated in both high and low flux conditions are compared. For neutron fluences above 6×1019 n/cm2 (E&amp;gt;1MeV) the difference in the neutron fluence dependence of the increase in hardness is not seen for any neutron flux condition. The number densities and the diameters of solute atom clusters for the low flux irradiation materials tend to be lower and larger, respectively, than that for the high flux irradiation materials, while the volume fraction of solute atom clusters increases linearly with increasing neutron fluence, and the effect of neutron flux is not significant. The component elements and the chemical composition of the solute atom clusters formed by irradiation for the same material do not change regardless of the neutron fluence and flux. The square root of the volume fraction of the solute atom clusters provides a good correlation with the increase in hardness.
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Reifarth, Rene, Michael Heil, Ralf Plag, Franz Käppeler, Franitsek Becvár, and M. Krticka. "Photon strength function and neutron/proton capture." In Workshop on Photon Strength Functions and Related Topics. Sissa Medialab, 2008. http://dx.doi.org/10.22323/1.044.0012.

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Reports on the topic "Photon and neutron fluences"

1

Rhoades, W. A., R. A. Lillie, and M. B. Emmett. Transmission factors for the penetration of neutron and photon fluence into wood-frame dwellings, 1990 (TF90). Office of Scientific and Technical Information (OSTI), 1992. http://dx.doi.org/10.2172/10150499.

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Rhoades, W. A., R. A. Lillie, and M. B. Emmett. Transmission factors for the penetration of neutron and photon fluence into wood-frame dwellings, 1990 (TF90). Office of Scientific and Technical Information (OSTI), 1992. http://dx.doi.org/10.2172/5147507.

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Grimm, K. N. Neutron Fluences for EBR-II Reflector Assemblies U9902, U9003, U9005, U9006 and U9027. Office of Scientific and Technical Information (OSTI), 2014. http://dx.doi.org/10.2172/1495197.

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Wooten, Hasani Omar. Time-Dependent Neutron and Photon Dose-Field Analysis. Office of Scientific and Technical Information (OSTI), 2005. http://dx.doi.org/10.2172/883461.

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Hermann, O. W., and C. W. Alexander. Review of spent-fuel photon and neutron source spectra. Office of Scientific and Technical Information (OSTI), 1986. http://dx.doi.org/10.2172/6234717.

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Alsmiller, Jr., R. G., J. M. Barnes, and J. D. Drischler. Neutron-photon multigroup cross sections for neutron energies less than or equal to400 MeV. Revision 1. Office of Scientific and Technical Information (OSTI), 1986. http://dx.doi.org/10.2172/6375717.

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Liew, S. L., L. P. Ku, and J. G. Kolibal. Three-dimensional Monte Carlo calculations of the neutron and. gamma. -ray fluences in the TFTR diagnostic basement and comparisons with measurements. Office of Scientific and Technical Information (OSTI), 1985. http://dx.doi.org/10.2172/5002857.

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Eigenbrodt, Julia, and Howard Olsen Menlove. Spent fuel measurements. passive neutron albedo reactivity (PNAR) and photon signatures. Office of Scientific and Technical Information (OSTI), 2016. http://dx.doi.org/10.2172/1244333.

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Nelson, Walter R. Measurements of Accelerator-Produced Leakage Neutron and Photon Transmission through Concrete. Office of Scientific and Technical Information (OSTI), 2002. http://dx.doi.org/10.2172/799944.

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Mao, S. Photon and neutron responses of optical absorption dosimeters used at SLAC. Office of Scientific and Technical Information (OSTI), 2000. http://dx.doi.org/10.2172/753283.

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