Relevant bibliographies by topics / Neutron dose

Academic literature on the topic 'Neutron dose'

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Published: 10 December 2022
Last updated: 28 January 2023

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Journal articles on the topic "Neutron dose"

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Hälg, Roger Antoine, and Uwe Schneider. "Neutron dose and its measurement in proton therapy—current State of Knowledge." British Journal of Radiology 93, no. 1107 (March 2020): 20190412. http://dx.doi.org/10.1259/bjr.20190412.

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Proton therapy has shown dosimetric advantages over conventional radiation therapy using photons. Although the integral dose for patients treated with proton therapy is low, concerns were raised about late effects like secondary cancer caused by dose depositions far away from the treated area. This is especially true for neutrons and therefore the stray dose contribution from neutrons in proton therapy is still being investigated. The higher biological effectiveness of neutrons compared to photons is the main cause of these concerns. The gold-standard in neutron dosimetry is measurements, but performing neutron measurements is challenging. Different approaches have been taken to overcome these difficulties, for instance with newly developed neutron detectors. Monte Carlo simulations is another common technique to assess the dose from secondary neutrons. Measurements and simulations are used to develop analytical models for fast neutron dose estimations. This article tries to summarize the developments in the different aspects of neutron dose in proton therapy since 2017. In general, low neutron doses have been reported, especially in active proton therapy. Although the published biological effectiveness of neutrons relative to photons regarding cancer induction is higher, it is unlikely that the neutron dose has a large impact on the second cancer risk of proton therapy patients.
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Fragopoulou, M., S. Stoulos, M. Manolopoulou, M. Krivopustov, and M. Zamani. "Dose Measurements around Spallation Neutron Sources." HNPS Proceedings 16 (January 1, 2020): 53. http://dx.doi.org/10.12681/hnps.2581.

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Neutron dose measurements and calculations around spallation sources are of importance for an appropriate shielding study. Two spallation sources, consisted of Pb target, have been irradiated by high-energy proton beams, delivered by the Nuclotron accelerator (JINR), Dubna. Dose measurements of the neutrons produced by the two spallation sources were performed using Solid State Nuclear Track Detectors (SSNTDs). In addition, the neutron dose after polyethylene and concrete was calculated using phenomenological model based on empirical relations applied in high energy Physics. Analytical and experimental neutron benchmark analysis has been performed using the transmission factor. A comparison of experimental results with calculations is given.
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Ivkovic, Ana, Dario Faj, Mladen Kasabasic, Marina Poje Sovilj, Ivana Krpan, Marina Grabar Branilovic, and Hrvoje Brkic. "The influence of shielding reinforcement in a vault with limited dimensions on the neutron dose equivalent in vicinity of medical electron linear accelerator." Radiology and Oncology 54, no. 2 (May 2, 2020): 247–52. http://dx.doi.org/10.2478/raon-2020-0024.

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AbstractBackgroundHigh energy electron linear accelerators (LINACs) producing photon beams with energies higher than 10 MeV are widely used in radiation therapy. In these beams, fast neutrons are generated, which results in undesired contamination of the therapeutic beam. In this study, measurements and Monte Carlo (MC) simulations were used to obtain neutron spectra and dose equivalents in vicinity of linear accelerator.Materials and methodsLINAC Siemens Oncor Expression in Osijek University Hospital is placed in vault that was previously used for 60Co machine. Then, the shielding of the vault was enhanced using lead and steel plates. Measurements of neutron dose equivalent around LINAC and the vault were done using CR-39 solid state nuclear track detectors. To compensate energy dependence of detectors, neutron energy spectra was calculated in measuring positions using MC simulations.ResultsThe vault is a source of photoneutrons, but a vast majority of neutrons originates from accelerator head. Neutron spectra obtained from MC simulations show significant changes between the measuring positions. Annual neutron dose equivalent per year was estimated to be less than 324 μSv in the measuring points outside of the vault.ConclusionsSince detectors used in this paper are very dependent on neutron energy, it is extremely important to know the neutron spectra in measuring points. Though, patient dosimetry should include neutrons, estimated annual neutron doses outside the vault were far below exposure limit of ionizing radiation for workers.
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Shagholi, Negin, Hassan Ali, Mahdi Sadeghi, Arjang Shahvar, Hoda Darestani, Banaee Nooshin, and Kheirolah Mohammadi. "Neutron dose evaluation of Elekta Linac at two energies (10 & 18 MV) by MCNP code and comparison with experimental measurements." JOURNAL OF ADVANCES IN PHYSICS 6, no. 1 (November 1, 2014): 1006–15. http://dx.doi.org/10.24297/jap.v6i1.1820.

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Medical linear accelerators, besides the clinically high energy electron and photon beams, produce other secondary particles such as neutrons which escalate the delivered dose. In this study the neutron dose at 10 and 18MV Elekta linac was obtained by using TLD600 and TLD700 as well as Monte Carlo simulation. For neutron dose assessment in 2020 cm2 field, TLDs were calibrated at first. Gamma calibration was performed with 10 and 18 MV linac and neutron calibration was done with 241Am-Be neutron source. For simulation, MCNPX code was used then calculated neutron dose equivalent was compared with measurement data. Neutron dose equivalent at 18 MV was measured by using TLDs on the phantom surface and depths of 1, 2, 3.3, 4, 5 and 6 cm. Neutron dose at depths of less than 3.3cm was zero and maximized at the depth of 4 cm (44.39 mSvGy-1), whereas calculation resulted in the maximum of 2.32 mSvGy-1 at the same depth. Neutron dose at 10 MV was measured by using TLDs on the phantom surface and depths of 1, 2, 2.5, 3.3, 4 and 5 cm. No photoneutron dose was observed at depths of less than 3.3cm and the maximum was at 4cm equal to 5.44mSvGy-1, however, the calculated data showed the maximum of 0.077mSvGy-1 at the same depth. The comparison between measured photo neutron dose and calculated data along the beam axis in different depths, shows that the measurement data were much more than the calculated data, so it seems that TLD600 and TLD700 pairs are not suitable dosimeters for neutron dosimetry in linac central axis due to high photon flux, whereas MCNPX Monte Carlo techniques still remain a valuable tool for photonuclear dose studies.
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Gutermuth, F., T. Radon, G. Fehrenbacher, and J. G. Festag. "The response of various neutron dose meters considering the application at a high energy particle accelerator." Kerntechnik 68, no. 4 (August 1, 2003): 172–79. http://dx.doi.org/10.1515/kern-2003-0072.

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Abstract The applicability of several neutron detectors for dose measurements at a neutron field typical for high energy particle accelerators is investigated. The response of four commercially available active neutron dose meters and two passive detectors to neutrons from a 241Am-Be(α,n) source and to neutrons at the CERN EU high energy reference field was determined experimentally and simulated using the Monte-Carlo code FLUKA. Fluence response functions and dose responses for the different detectors were calculated in the energy range between 1 keV and 10 GeV. The results show that the dose response to the high energy neutron field at CERN of the conventional rem-counters is lower by a factor of 2 to 2.5 if compared to the dose response to a 241Am-Be(α,n) neutron source. The rem-counters exhibiting an additional layer of lead inside the moderating structure showed dose readings which differ only up to 25 %. A thermoluminescent based neutron detector was tested for comparison. These passive detectors revealed a neutron response similar to a rem-counter and may be preferable for situations with highly pulsed beams.
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Dennis, J. A., and L. A. Dennis. "Neutron dose effect relationships at low doses." Radiation and Environmental Biophysics 27, no. 2 (June 1988): 91–101. http://dx.doi.org/10.1007/bf01214599.

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Zhou, Bin, Fei Shen, Zhiliang Hu, Songlin Wang, Xichao Ruan, and Tianjiao Liang. "A Study of Stray Neutron Field Measurements for the Neutron Scattering Instruments at CSNS." Applied Sciences 12, no. 10 (May 12, 2022): 4915. http://dx.doi.org/10.3390/app12104915.

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Stray neutrons might cause several negative impacts. However, it is usually difficult to conduct precise stray neutron simulations using the Monte Carlo method. Therefore, in this study, a measurement technique was proposed to study the stray neutrons experimentally inside the neutron scattering instruments at China Spallation Neutron Source (CSNS). The adopted measurement instruments comprise an extended-range Bonner sphere spectrometer and a commercial neutron ambient-dose-equivalent dosimeter, which enables us to directly measure the neutron spectra and ambient-dose equivalent H*(10) values. Verification experiments were performed inside the BL06 beam line experimental area at CSNS at two exposed locations with different sample conditions. Comparison of the experimentally measured neutron spectra, integral neutron fluence, and H*(10) value with the simulations demonstrated the feasibility of using the proposed method for studying stray neutrons for the neutron instruments.
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D’Avino, Vittoria, Fabrizio Ambrosino, Roberto Bedogni, Abner Ivan C. Campoy, Giuseppe La Verde, Silvia Vernetto, Carlo Francesco Vigorito, and Mariagabriella Pugliese. "Characterization of Thermoluminescent Dosimeters for Neutron Dosimetry at High Altitudes." Sensors 22, no. 15 (July 30, 2022): 5721. http://dx.doi.org/10.3390/s22155721.

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Neutrons constitute a significant component of the secondary cosmic rays and are one of the most important contributors to natural cosmic ray radiation background dose. The study of the cosmic ray neutrons’ contribution to the dose equivalent received by humans is an interesting and challenging task for the scientific community. In addition, international regulations demand assessing the biological risk due to radiation exposure for both workers and the general population. Because the dose rate due to cosmic radiation increases significantly with altitude, the objective of this work was to characterize the thermoluminescent dosimeter (TLDs) from the perspective of exposing them at high altitudes for longtime neutron dose monitoring. The pair of TLD-700 and TLD-600 is amply used to obtain the information on gamma and neutron dose in mixed neutron-gamma fields due to the present difference in 6Li isotope concentration. A thermoluminescence dosimeter system based on pair of TLD-600/700 was characterized to enable it for neutron dosimetry in the thermal energy range. The system was calibrated in terms of neutron ambient dose equivalent in an experimental setup using a 241Am-B radionuclide neutron source coated by a moderator material, polyethylene, creating a thermalized neutron field. Afterward, the pair of TLD-600/700 was exposed at the CERN-EU High-Energy Reference Field (CERF) facility in Geneva, which delivers a neutron field with a spectrum similar to that of secondary cosmic rays. The dosimetric system provided a dose value comparable with the calculated one demonstrating a good performance for neutron dosimetry.
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Konstantin Andreevich Kuznetsov, Pavel Semenovich Kizim, Andrey Yurievich Berezhnoy, Oleksandr Pilipovich Shchus, and Gennadiy Michailovich Onyshchenko. "Cell stress response to low-dose neutron radiation." Magna Scientia Advanced Biology and Pharmacy 1, no. 1 (November 30, 2020): 036–42. http://dx.doi.org/10.30574/msabp.2020.1.1.0022.

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Background. It is a point of discussion whether low-dose ionizing radiation has harmful or stimulating impact on cell. According to high relative biological effectiveness of neutron radiation there is a need of description of any process triggered in the cell by neutrons. Objective. The aim of current work is the investigation of the low dosed neutron radiation effects on human cells by indicators of cell stress such as state of chromatin and cell membrane permeability. Materials and methods. Human buccal epithelium cells from 3 male donors (21, 24, 25 years old) were exposed to fast neutron radiation in dose range 2.3–146.0 mSv from 239Pu-Be source. State of chromatin was evaluated by count of heterochromatin granules quantity in 100 nuclei stained with 2% orcein in 45% acetic acid; ratio of cells with increased membrane permeability stained with 5 mM indigocarmine in 300 cells. Results. Changes in level of heterochromatin granules quantity and in cell membrane permeability revealed wave-shaped dependency with maximum effects at 36.5 mSv. Further increase of dose resulted in return of both chromatin state and membrane permeability levels closely to control or even lower. Conclusion. Membrane restoration and chromatin decompaction under doses higher than 36.5 mSv together can be a sign of hormetic (stimulating) effect of low-dose neutron radiation.
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Chen, Zhao, Peng Yang, Qin Lei, Yumei Wen, Donglin He, Zhangwen Wu, and Chengjun Gou. "COMPARISON OF BNCT DOSIMETRY CALCULATIONS USING DIFFERENT GEANT4 PHYSICS LISTS." Radiation Protection Dosimetry 187, no. 1 (May 28, 2019): 88–97. http://dx.doi.org/10.1093/rpd/ncz144.

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Abstract A comparison of Geant4 physics lists is conducted in the calculation of the total absorbed dose, boron dose, and non-boron dose in phantom, and the total depth-dose, boron depth-dose, and non-boron depth-dose along the beam axis for neutrons in a range of 0.0253 eV to 10 MeV. Physics processes are included for neutrons, photons, and charged particles, and calculations are conducted for neutrons and secondary particles. The results obtained from QBBC, QGSP_BERT, and neutron high precision physics lists with and without S(α, β) data are compared with the FLUKA values. Neutron high precision physics lists with S(α, β) data showed the best agreement with FLUKA in the studied energy range.
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Dissertations / Theses on the topic "Neutron dose"

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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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Veinot, Kenneth Guy. "An angular dependent neutron effective-dose-equivalent dosimeter." Diss., Georgia Institute of Technology, 1999. http://hdl.handle.net/1853/17595.

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Seppälä, Tiina. "FiR epithermal neutron beam model and dose calculation for treatment planning in neutron capture therapy." Helsinki : University of Helsinki, 2002. http://ethesis.helsinki.fi/julkaisut/mat/fysik/vk/seppala/.

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Simpkins, Robert W. "Neutron organ dose and the influence of adipose tissue." Diss., Georgia Institute of Technology, 2003. http://hdl.handle.net/1853/18959.

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Phoenix, Ben. "Synergistic and dose rate effects in Boron Neutron Capture Therapy." Thesis, University of Birmingham, 2013. http://etheses.bham.ac.uk//id/eprint/4084/.

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An investigation of the factors affecting the biological effectiveness of neutron beams suitable for Boron Neutron Capture Therapy (BNCT) has been carried out. The primary experimental work described in this thesis concerns the degree of interaction, if any, between biological damage caused by low LET radiation and that caused by high LET radiation. The second area investigated concerns the biological impact of delivering a BNCT irradiation at differing dose rates. In mixed photon alpha particle irradiations, no synergistic effect was observed above the response from the separate components. Maximum alpha particle doses delivered were 2.54 Gy. In mixed X-ray and alpha particle exposures, no synergy effect was seen with 2.54 Gy of alpha particles delivered to the cells. At the 3.18Gy alpha particle dose level significantly lower cell survival was observed than would be predicted from survival in single fields. Dose rate experiments were carried out in the Massachusetts Institute of Technology (MIT) Fission Converter neutron Beam (FCB). Cells loaded with boric acid were exposed at dose rates differing by a factor of approximately 15. A dose rate effect was observed at both of the irradiation depths used, although this was only clearly significant at 50 mm treatment depth.
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Fortune, Eugene C. IV. "Gamma and neutron dose profiles near a Cf-252 brachytherapy source." Thesis, Georgia Institute of Technology, 2010. http://hdl.handle.net/1853/34781.

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A new generation of medical grade Cf-252 sources was developed in 2002 at the Oak Ridge National Laboratory (ORNL). The combination of small size and large activity of these Cf-252 sources makes them suitable to be used with the conventional high-dose-rate (HDR) remote afterloading systems for interstitial brachytherapy. A recent in-water calibration experiment showed that the measured gamma dose rates near the new source are slightly greater than the neutron dose rates; contradicting the well established neutron-to-gamma dose ratio of approximately 2:1 at locations near a Cf-252 brachytherapy source. Specifically, the MCNP-predicted gamma dose rate is a factor of two higher than the measured gamma dose rate at the distance of 1 cm, and the differences between the two results gradually diminish at distances farther away from the source. To resolve this discrepancy, we updated the source gamma spectrum by including in the ORIGEN-S data library the experimentally measured Cf-252 prompt gamma spectrum as well as the true Cf-252 spontaneous fission yield data to explicitly model delayed gamma emissions from fission products. We also investigated the bremsstrahlung x-rays produced by the beta particles emitted from fission-product decays. The results show that the discrepancy of gamma dose rates is mainly caused by the omission of the bremsstrahlung x-rays in the MCNP runs. By including the bremsstrahlung x-rays, the MCNP results show that the gamma dose rates near a new Cf-252 source agree well with the measured results and that the gamma dose rates are indeed greater than the neutron dose rates. The calibration experiment also showed discrepancies between the experimental and computational neutron dose profiles obtained. Specifically the MCNP-predicted neutron dose rates were ~25% higher than the measured neutron dose rates at all distances. In attempting to resolve this discrepancy the neutron emission rate was verified by the National Institute of Standards and Technology (NIST) and an experiment was performed to explore the effects of bias voltage on ion chamber charge collection. So far the discrepancies between the computational and experimental neutron dose profiles have not been resolved. Further study is needed to completely resolve this issue and some suggestions on how to move forward are given.
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MUNIZ, RAFAEL O. R. "Desenvolvimento de um simulador antropomorfico para simulacao e medidas de dose e fluxo de neutrons na instalacao para estudos em BNCT." reponame:Repositório Institucional do IPEN, 2010. http://repositorio.ipen.br:8080/xmlui/handle/123456789/9559.

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Dissertacao (Mestrado)
IPEN/D
Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP
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Ishikawa, Masayori. "Development of New Absorbed Dose Estimation System for Boron Neutron Capture Therapy." Kyoto University, 2002. http://hdl.handle.net/2433/149649.

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Taulbee, Timothy Dale. "Measurement and model prediction of proton-recoil track length distributions in NTA film dosimeters for neutron energy spectroscopy and retrospective dose assessment." Cincinnati, Ohio : University of Cincinnati, 2009. http://www.ohiolink.edu/etd/view.cgi?acc_num=ucin1235764236.

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Thesis (Ph.D.)--University of Cincinnati, 2009.
Advisors: Henry Spitz PhD (Committee Chair), Bingjing Su PhD (Committee Member), John Christenson PhD (Committee Member). Title from electronic thesis title page (viewed May 1, 2009). Keywords: NTA; proton-recoil; neutron spectroscopy; dose assessment; track length; Monte Carlo; neutron transport; neutron interactions. Includes abstract. Includes bibliographical references.
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Niemkiewicz, John. "A study on the use of removal-diffusion theory to calculate neutron distributions for dose determination in boron neutron capture therapy /." The Ohio State University, 1996. http://rave.ohiolink.edu/etdc/view?acc_num=osu1487934589976468.

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Books on the topic "Neutron dose"

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Tan, Min. Development of a neutron dose-equivalent counter for area monitoring. Birmingham: University of Birmingham, 1994.

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International Commission on Radiation Units and Measurements., ed. Clinical neutron dosimetry, part 1: Determination of absorbed dose in a patient treated by external beams of fast neutrons. Bethesda, Md., U.S.A: The Commission, 1989.

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Sahoo, G. S. Directional neutron ambient dose distribution for heavy ions on thick AL target using CR-39 detector. Mumbai, India: Bhabha Atomic Research Centre, 2012.

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Shakshak, Bashir Ibrahim Omar. The measurements of neutron and gamma dose rates in mixed radiation fields, using a liquid scintillation counter. Birmingham: Aston University. Department of Electrical and Electronic Engineering and Applied Physics, 1989.

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Komisopoulos, Georgios A. Boron neutron capture therapy: A study of neutron interactions and dose in the brain. 1996.

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Sublet, J. Ch, F. M. Mann, and C. Ponti. A Neutron Activation, Transmutation, and Dose Rate Benchmark Study (Reports). AEA Technology Plc, 1989.

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D, Stewart R., United States. Dept. of Energy. Assistant Secretary for Environment, Safety, and Health. Office of Health., and Pacific Northwest Laboratory, eds. Calculation of neutron fluence to dose conversion factors for extremities. Richland, Wash: Pacific Northwest Laboratory, 1993.

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Neutron and Gamma-Ray Fluence-To-Dose Factors: Ansi-Ans 6.1.1. Amer Nuclear Society, 1991.

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Ann, Torres Betty, and Armed Forces Radiobiology Research Institute (U.S.), eds. Determination of canine dose conversion factors in mixed neutron and gamma radiation fields. Bethesda, Md: Armed Forces Radiobiology Research Institute, 1996.

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National Council on Radiation Protection and Measurements., ed. Pulsed fast neutron analysis system used in security surveillance. Bethesda, Md: National Council on Radiation Protection and Measurements, 2003.

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Book chapters on the topic "Neutron dose"

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Wheeler, Floyd J., and Daniel E. Wessol. "Dose Calculations Based on Image Reconstructions." In Boron Neutron Capture Therapy, 143–54. Boston, MA: Springer US, 1992. http://dx.doi.org/10.1007/978-1-4615-3408-2_16.

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Russell, John L. "BNCT and Dose Fractionation." In Clinical Aspects of Neutron Capture Therapy, 75–79. Boston, MA: Springer US, 1989. http://dx.doi.org/10.1007/978-1-4684-5622-6_10.

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Carolan, M. G., S. A. Wallace, B. J. Allen, A. B. Rosenfeld, J. N. Mathur, H. A. Meriaty, F. Stecher-Rasmussen, R. L. Moss, C. P. J. Raaijmakers, and M. W. Konijnenberg. "Validation of Monte Carlo Dose Planning Calculations by Epithermal Beam Dose Distribution Measurements in Phantoms." In Cancer Neutron Capture Therapy, 303–10. Boston, MA: Springer US, 1996. http://dx.doi.org/10.1007/978-1-4757-9567-7_44.

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Fairchild, R. G. "Dose Rate and Therapeutic Gain." In Clinical Aspects of Neutron Capture Therapy, 1–7. Boston, MA: Springer US, 1989. http://dx.doi.org/10.1007/978-1-4684-5622-6_1.

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Nakagawa, Yoshinobu, and Teruyoshi Kageji. "Tolerance of Healthy Tissues and Ideal Radiation Dose on BNCT." In Neutron Capture Therapy, 359–65. Berlin, Heidelberg: Springer Berlin Heidelberg, 2012. http://dx.doi.org/10.1007/978-3-642-31334-9_18.

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Ono, K., S. Masunaga, Y. Kinashi, M. Takagaki, T. Kobayashi, Y. Imahori, S. Ueda, and Y. Oda. "The Dose Planning of BNCT for Brain Tumors." In Cancer Neutron Capture Therapy, 563–69. Boston, MA: Springer US, 1996. http://dx.doi.org/10.1007/978-1-4757-9567-7_80.

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Charlton, D. E., and B. J. Allen. "Dose Sparing of Capillary Endothelial Cells for BSH and BPA." In Cancer Neutron Capture Therapy, 479–83. Boston, MA: Springer US, 1996. http://dx.doi.org/10.1007/978-1-4757-9567-7_68.

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Withers, H. Rodney. "Problems of Dose Fractionation in BNCT." In Progress in Neutron Capture Therapy for Cancer, 625–45. Boston, MA: Springer US, 1992. http://dx.doi.org/10.1007/978-1-4615-3384-9_135.

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Howard, W. B., and J. C. Yanch. "Shielding Design and Dose Assessment for an Accelerator-Based BNCT Facility." In Cancer Neutron Capture Therapy, 439–44. Boston, MA: Springer US, 1996. http://dx.doi.org/10.1007/978-1-4757-9567-7_62.

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Wielopolski, L., and B. Ciesielski. "Determination of Boron Dose for BNCT Using Fricke and EPR Dosimetry." In Cancer Neutron Capture Therapy, 467–71. Boston, MA: Springer US, 1996. http://dx.doi.org/10.1007/978-1-4757-9567-7_66.

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Conference papers on the topic "Neutron dose"

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Klett, Alfred, and Albrecht Leuschner. "A pulsed neutron dose monitor." In 2007 IEEE Nuclear Science Symposium Conference Record. IEEE, 2007. http://dx.doi.org/10.1109/nssmic.2007.4436542.

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Xia, Wenming, Mingchun Jia, and Zhirong Guo. "The Design of a Neutron Dosimeter." In 18th International Conference on Nuclear Engineering. ASMEDC, 2010. http://dx.doi.org/10.1115/icone18-29047.

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At present, most of the developed neutron dosimeters that have a moderator with a single counter, applied in neutron radiation fields within large range energies from thermal to MeV neutrons, are not a satisfaction to energy response. The purpose of the article is designing a suitable neutron dosimeter for the radiation protection purpose. In order to overcome the disadvantage of the energy response of the neutron dosimeters combined a single sphere with a single counter, three spheres and three 3He counters were combined for the detector design. The response function of moderators with different thicknesses combined with SP9 3He counters were calculated with MCNP program MCNP4C [1]. The selection of three different thicknesses of the moderating polyethylene sphere was done with a Matlab program [2]. A suitable combination of three different thicknesses was confirmed for the detector design. The electronic system of the neutron dosimeter was introduced. The fluence to ambient dose-equivalent conversion coefficient were calculated, analyzed and compared with the values recommended in the ICRP 74 Publication [3]. The calculated result explain that it is very significance to this design of neutron dosimeter, it may be applied to the monitor of the ambient dose in the neutron radiation fields, improving at present the status of the energy response of neutron dosimeters.
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Klett, Alfred, and Albrecht Leuschner. "Pulsed Neutron Dose Monitoring - A New Approach." In 2006 IEEE Nuclear Science Symposium Conference Record. IEEE, 2006. http://dx.doi.org/10.1109/nssmic.2006.355973.

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Vega-Carrillo, H. R., L. Paredes-Gutierrez, and C. G. Borja-Hernandez. "Neutron spectrum and dose in a CMOS." In MEDICAL PHYSICS: Twelfth Mexican Symposium on Medical Physics. AIP, 2012. http://dx.doi.org/10.1063/1.4764584.

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Lv, Jinxu, Ning Lv, Huiping Guo, Mingyan Sun, Kuo Zhao, Wenhui Lv, Zhihao Wei, Qizhan Xiao, Daji Li, and Yang Liu. "Study on On-Site Calibration Method of Stationary Neutron Dosimeter." In 2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/icone2020-16144.

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Abstract:
Abstract The on-site calibration system of stationary neutron ambient dose equivalent instrument is mainly comprised of a small controllable neutron source and a reference neutron ambient dose equivalent instrument. According to the principle of “relative calibration method”, a small controllable neutron source continuously emits neutrons at the calibration site to construct a neutron radiation field. The calibration factor (NB) can be obtained by comparing the response numbers from two instrument, the instrument to be calibrated and the reference instrument, which are symmetrically placed in the neutron radiation field. In order to complete the transfer of the ambient dose equivalent calibration coefficient of the reference instrument from National Metrology Center (252CfStandard radiation field) to nuclear facility site, the calibration coefficient needs to be corrected, that is, multiplied by the “energy correction coefficient”. Energy correction coefficient includes: (1) “Instrument Energy Response Correction Coefficient” kε for neutron fluence to neutron counting of the instrument, (2) “Conversion Correction Coefficient” kΦ for neutron fluence to neutron ambient dose equivalent. Tests have shown that the ambient dose equivalent rate measurement error of the instrument which have been calibrated but without energy correction was 16.5%, by contrast the measurement error was 2.9% with energy correction. It can be seen that the energy correction is necessary and effective for the measuring instrument of neutron ambient dose equivalent during the on-site calibration process.
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Weizhen Wang, Kejun Kang, and Jianmin Li. "The research on neutron dose equivalent meter for pulse neutron radiation field." In 2008 IEEE Nuclear Science Symposium and Medical Imaging conference (2008 NSS/MIC). IEEE, 2008. http://dx.doi.org/10.1109/nssmic.2008.4774826.

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Tan, Min, D. R. Weaver, Malcolm C. Scott, and David J. Thomas. "New dose-equivalent counter for neutron area monitoring." In 4th International Conference on Applications of Nuclear Techniques: Neutrons and their Applications, edited by George Vourvopoulos and Themis Paradellis. SPIE, 1995. http://dx.doi.org/10.1117/12.204166.

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Henschel, Henning, Otmar Koehn, S. Metzger, Marc C. Decreton, Paul de Vos, Olivier Deparis, Johannes Kirchhof, and Stephan Grimm. "Neutron fluence and dose measurements by optical fibers." In Fifth International Conference on Applications of Nuclear Techniques: Neutrons in Research and Industry, edited by George Vourvopoulos. SPIE, 1997. http://dx.doi.org/10.1117/12.267918.

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Urban, Tomas, and Jaroslav Klusoň. "Estimation of Secondary Neutron Dose during Proton Therapy." In SNA + MC 2013 - Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo, edited by D. Caruge, C. Calvin, C. M. Diop, F. Malvagi, and J. C. Trama. Les Ulis, France: EDP Sciences, 2014. http://dx.doi.org/10.1051/snamc/201405118.

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Degtiarenko, Pavel V. "NDX: Neutron Dose Rate Meters with Extended Capabilities." In 2019 IEEE Nuclear Science Symposium and Medical Imaging Conference (NSS/MIC). IEEE, 2019. http://dx.doi.org/10.1109/nss/mic42101.2019.9059727.

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Reports on the topic "Neutron dose"

1

Henzlova, Daniela, and Howard Olsen Menlove. High-dose neutron detector development. Office of Scientific and Technical Information (OSTI), January 2016. http://dx.doi.org/10.2172/1235220.

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Marcath, Matthew, Tucker McClanahan, Douglas Mayo, Joshua Spencer, and Kimberly Klain. Silicon-Equivalent Neutron Dose Estimations. Office of Scientific and Technical Information (OSTI), September 2021. http://dx.doi.org/10.2172/1821355.

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Menlove, Howard Olsen, and Daniela Constance Henzlova. High-dose neutron detector project update. Office of Scientific and Technical Information (OSTI), September 2018. http://dx.doi.org/10.2172/1473778.

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Menlove, Howard Olsen, and Daniela Henzlova. High-dose neutron detector project update. Office of Scientific and Technical Information (OSTI), August 2017. http://dx.doi.org/10.2172/1375134.

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Menlove, Howard Olsen, and Daniela Henzlova. High-dose neutron detector project update. Office of Scientific and Technical Information (OSTI), August 2016. http://dx.doi.org/10.2172/1296699.

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Mclean, Thomas Donaldson. Introduction to neutron dose and dosimetry. Office of Scientific and Technical Information (OSTI), March 2018. http://dx.doi.org/10.2172/1425755.

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Holman-Abbott, Michelle, and Alan Boone. Portable Neutron Dose Rate Instrument Evaluation. Office of Scientific and Technical Information (OSTI), May 2018. http://dx.doi.org/10.2172/1462170.

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Menlove, Howard Olsen, and Daniela Henzlova. High-dose neutron detector project update. Office of Scientific and Technical Information (OSTI), March 2017. http://dx.doi.org/10.2172/1351208.

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Worgul, B. V. Low dose neutron late effects: Cataractogenesis. Office of Scientific and Technical Information (OSTI), December 1991. http://dx.doi.org/10.2172/5816375.

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Mihalczo, John T., Michael C. Wright, Seth M. McConchie, Daniel E. Archer, and Blake A. Palles. Transportable, Low-Dose Active Fast-Neutron Imaging. Office of Scientific and Technical Information (OSTI), August 2017. http://dx.doi.org/10.2172/1400208.

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