Measurement of Absorbed Dose of Neutrons, and of Mixtures of Neutrons and Gamma Rays PDF Download
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Author: National Committee on Radiation Protection and Measurements (U.S.)
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 96
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Book Description
Author: National Committee on Radiation Protection and Measurements (U.S.)
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 96
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Book Description
Author: National Committee on Radiation Protection and Measurements (U.S.)
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 96
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Book Description
Author: United States. National Committee on Radiation Protection and Measurements
Publisher:
ISBN:
Category : Gamma rays
Languages : en
Pages : 100
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Author: United States. National Committee on Radiation Protection and Measurements
Publisher:
ISBN: 9780913392089
Category : Gamma rays
Languages : en
Pages : 86
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Author: National Council on Radiation Protection and Measurements
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 172
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Author: E. R. Schleiger
Publisher:
ISBN:
Category : Calorimeters
Languages : en
Pages : 38
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Thirteen 10-min exposures of the TE absorber in the microcalorimeter to fast neutrons from the University of California 60-in. cyclotron at Crocker Laboratory resulted in absorbed dose measurements varying from 24 to 40 rads. The average absorbed dose value was 5 percent higher than the NRDL determination based on flux and spectrum measurements. Microcalorimeter exposures to the 900-Mev alpha particle beam from the University of California 184-in. synchro-cyclotron at Lawrence Radiation Laboratory gave absorbed doses that agreed reasonably well with ionization chamber determinations.
Author: National Committee on Radiation Protection and Measurements (U.S.)
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 104
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Author: R. E. Simpson
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ISBN:
Category : Radiation dosimetry
Languages : en
Pages : 38
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The distribution of steady-state and pulsed, neutron and gamma-ray dose was measured in an animal exposure volume at the TRIGA reactor. The usable volume was restricted to the lower 20 in. of an aluminum irradiation tube having an ID of 9-1/2 in. The tube was inserted into the pool adjacent to the reactor void tank, 134 cm from the core. Dosimetry films were used to determine gamma-ray dose while Sievert ionization chambers were used to determine neutron dose. Gold foils were used to measure the thermal neutron flux. Neutron doses were referenced to sulphur foil monitors. The neutron spectrum was examined with a system of threshold detectors and compared with spectra from Godiva II and the biological port of the Argonne CP-5 reactor. The vertical variation of dose along a lucite board was measured at the midplane of a lucite canister lowered into the tube. The dose in the lower 16 in. varied less than 5%. The ratio of neutron to gamma dose was approximately 6 to 1. A tissue equivalent dog phantom, 20 in. long and 7-1/2 in. in diameter, was designed to determine the absorbed dose in depth. The fast neutron dose was about equal to the gamma-ray dose at the midline of the phantom. The neutron plus gamma-ray dose at the midline was 44% of the dose at the front surface of the phantom. (Author).
Author:
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 272
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Author: William B. Cottrell
Publisher:
ISBN:
Category : Nuclear reactors
Languages : en
Pages : 178
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