Measurement Of Neutron Flux And Spectra For Physical And Biological Applications
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Measurement of Neutron Flux and Spectra for Physical and Biological Applications
Author | : National Committee on Radiation Protection and Measurements (U.S.) |
Publsiher | : Unknown |
Total Pages | : 104 |
Release | : 1960 |
Genre | : Neutrons |
ISBN | : UOM:39015086489658 |
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Measurements of Neutron Flux and Spectra for Physical and Biological Applications
Author | : Anonim |
Publsiher | : Unknown |
Total Pages | : 135 |
Release | : 1960-07-01 |
Genre | : Electronic Book |
ISBN | : 0913392073 |
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Measurement of Neutron Flux and Spectra for Physical and Biological Applications
Author | : United States. National Committee on Radiation Protection and Measurements |
Publsiher | : Unknown |
Total Pages | : 102 |
Release | : 1960 |
Genre | : Neutrons |
ISBN | : UIUC:30112106668152 |
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Flux and Spectral Measurements of Primary and Moderated Neutron Sources
Author | : E. Tochilin |
Publsiher | : Unknown |
Total Pages | : 38 |
Release | : 1962 |
Genre | : Neutron flux |
ISBN | : UOM:39015095208859 |
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Radioactive (a, n) neutron sources include Ra-Be, PuF4, and four PuBe13 sources. Comparative neutron emission rates were determined by two separate methods: (1) the manganese sulfate bath with appropriate corrections made for fast neutron escape or capture and for thermal neutron capture by the source; and (2) long counter measurements corrected for energy response and so rce anisotropy. Agreement to within 1 percent was obtained by the two independent methods. A Ra-Be source calibrated against the NBS neutron standard was used as a primary reference Spectral measurements of PuBe13 and PuF4 neutron sources were made with nuclear emulsions. By the use of cylindrical plastic and lead absorbers, an effort was made to moderate the PuBe13 spectrum and thereby obtain additional calibration points for instrument response studies. Spectral changes were initially studied with the doublemoderator technique, followed by later measurements with nuclear emulsions. From flux and spectral measurements of the primary and moderated radioactive sources, the first collision tissue dose was calculated and, in turn, compared to experimental measurements of absorbed dose with proportional counters designed according to the Bragg-Gray principle. (Author).
Measurement of Neutron Flux and Spectra for Physical and Biological Applications
Author | : National Committee on Radiation Protection and Measurements (U.S.) |
Publsiher | : Unknown |
Total Pages | : 104 |
Release | : 1960 |
Genre | : Neutron flux |
ISBN | : STANFORD:36105002733876 |
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Measurement of Absorbed Dose of Neutrons and of Mixtures of Neutrons and Gamma Rays
Author | : National Committee on Radiation Protection and Measurements (U.S.),United States. National Bureau of Standards |
Publsiher | : Unknown |
Total Pages | : 96 |
Release | : 1961 |
Genre | : Neutrons |
ISBN | : UOM:39015086489682 |
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Public Health Service Publication
Author | : Anonim |
Publsiher | : Unknown |
Total Pages | : 810 |
Release | : 1968 |
Genre | : Public health |
ISBN | : UOM:39015069563958 |
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