Download or read book Measurement of Neutron Spectra for Determining Dose Equivalent Rates at the Texas A M University Nuclear Science Center written by Bruce Jerome Sanza and published by . This book was released on 1986 with total page 130 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Influence of Neutron Spectra and Fluence Response Data on the Determination of Dose Equivalent with Bonner Spheres written by Alexandru V. Alevra and published by . This book was released on 1986 with total page 136 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Measurement of Absorbed Dose of Neutrons and of Mixtures of Neutrons and Gamma Rays written by National Committee on Radiation Protection and Measurements (U.S.) and published by . This book was released on 1961 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Measurement of Neutron Flux and Spectra for Physical and Biological Applications written by National Committee on Radiation Protection and Measurements (U.S.) and published by . This book was released on 1960 with total page 104 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Measurement of Absorbed Dose of Neutrons and of Mixtures of Neutrons and Gamma Rays written by National Committee on Radiation Protection and Measurements (U.S.) and published by . This book was released on 1961 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book A Comparison of the Neutron Dose Rates Obtained with the Single sphere Instrument Multisphere Method and Hurst Proportional Counter written by Dale E. Hankins and published by . This book was released on 1964 with total page 54 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Measurement of Neutron Flux and Spectra for Physical and Biological Applications written by National Committee on Radiation Protection and Measurements (U.S.) and published by . This book was released on 1960 with total page 104 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Measurement of Absorbed Dose of Neutrons and of Mixtures of Neutrons and Gamma Rays written by United States. National Committee on Radiation Protection and Measurements and published by . This book was released on 1961 with total page 100 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Guidelines on Calibration of Neutron Measuring Devices written by Georg Burger and published by Bernan Press(PA). This book was released on 1988 with total page 92 pages. Available in PDF, EPUB and Kindle. Book excerpt: The majority of the existing Secondary Standard Dosimetry Laboratories (SSDLs) were established primarily to work with X rays and gamma rays. Neutron sources are, however, increasingly being applied in industrial processes, research, nuclear power development, and radiation biology and medicine. This publication deals primarily with methods of applying radioactive neutron sources for calibration of instrumentation and gives an indication of the space, manpower and facilities needed to fulfil the minimum requirements of a calibration laboratory for neutron work. Its intention is to serve as a guide for centres about to start on neutron dosimetry standardization and calibration.
Download or read book Neutron Spectrum Measurements for Radiation Protection Purposes written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The energy spectra of low-intensity neutron sources used for calibrating personnel neutron dose-rate meters and dosimeters and for characterizing the neutron fields to which personnel are exposed were measured. Several detector-analyzer systems that will measure in the energy range 50 keV to 20 MeV at intensities from 10−1 to 105 n/cm2-s are described. The systems include NE213 and stilbene organic scintillators as well as H2, 3He, and CH4 proportional counters. Also described are pulse-height analysis and pulse-shape discrimination systems. An unfolding code, NUTSPEC, reduces the pulse-height data to an absolute differential neutron flux phi(E) for the above detectors. The code uses a derivative unfolding method for the scintillation detectors, and for the proportional counters it calculates a response matrix and uses an iterative unfolding method to determine phi(E). The unfolded flux distribution combined with published conversion factors produces differential neutron dose-equivalent and kerma rates. Spectral segments obtained with different detectors from several measurements merge into a single differential flux spectrum over the range 50 keV to 20 MeV, together with the corresponding differential kerma and neutron dose-equivalent distributions. Also reported are spectrum measurements near 252Cf and 238PuBe sources with various moderators.
Download or read book Neutron Dosimetry at Commercial Nuclear Plants written by G. W. R. Endres and published by . This book was released on 1981 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Results of Monte Carlo Calculations of Neutron Spectra and Doses Outside the BDMS Shielding written by and published by . This book was released on 2000 with total page 43 pages. Available in PDF, EPUB and Kindle. Book excerpt: A set of Monte Carlo calculations of the neutron dose rates and neutron spectra outside Blend Down Monitoring System (BDMS) shielding were performed with U.S. and Russian neutron fluence-to-dose conversion coefficients. The purpose of these calculations was to facilitate the proper interpretation of the dose rate measurements from rem meters outside the BDMS shielding. An accurate determination of the dose rate is of particular interest so that dose rate can be compared with the applicable regulatory limit. The calculations show that the neutrons outside the BDMS shielding are significantly reduced in energy, i.e. the spectrum is shifted (moderated) towards the lower energies and contains significantly larger amount of neutrons in the energy range below 100 keV. The result of these calculations indicates that the dose measurement for the BDMS neutrons is overestimated from 25% to 55% depending on the location around BDMS when using either Russian or U.S. dose conversion coefficients. For an accurate neutron dose determination the application of an appropriate correcting factor to the neutron dose measurement is necessary.
Download or read book Measurement of Neutron Flux and Spectra for Physical and Biological Applications written by United States. National Committee on Radiation Protection and Measurements and published by . This book was released on 1960 with total page 102 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975-03 with total page 988 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Two plate Method of Measuring Fast Neutron Energy Spectra when the Direction of the Incident Neutrons Cannot be Determined written by John E. Evans and published by . This book was released on 1952 with total page 56 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Neutron Dosimetry written by H. G. Menzel and published by . This book was released on 1997 with total page 612 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Measurement of the Neutron Spectrum and Ambient Neutron Dose Rate Equivalent from the Small 252Cf Source at 1 Meter written by and published by . This book was released on 2015 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: NASA Langley Research Center requested a measurement of the neutron spectral distribution and fluence from the 252Cf source (model NS-120, LLNL serial # 7001677, referred as the SMALL Cf source) and determination of the ambient neutron dose rate equivalent and kerma at 100 cm for the Radiation Budget Instrument Experiment (Rad- X). The dosimetric quantities should be based on the neutron spectrum and the current neutron-to-dose conversion coefficients.
