Determination of the neutron spectrum and absolute yield of a plutonium-beryllium source PDF Download

Author: Leona Miller Stewart
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 88

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Author: M. Edward Anderson
Publisher:
ISBN:
Category : Beryllium
Languages : en
Pages : 40

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Author: R. E. Tate
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Category : Neutron sources
Languages : en
Pages : 12

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Author:
Publisher:
ISBN:
Category : Beryllium
Languages : en
Pages : 28

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Author: National Committee on Radiation Protection and Measurements (U.S.)
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 104

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Author:
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ISBN:
Category :
Languages : en
Pages :

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An investigntion of the plutonium-beryllium phase diagram demonstrates the suitability of these alloys and most particularly the intermetallic compound PuBe13 for stable neutron sources. These sources are superior to polonium- beryllium sources in respect to sthbility of neutron yield as a iunction of time and the prediotability of neutroc yield as a function of mass. The gamma-ray emission of plutonium-beryllium sources is very much less intense than that associated with radium beryllium socrces of corresponding neutron strength. The neutron yield is discussed in terms of the microstrocture and in terms of the relative distrihation of plutonium isotopes. Properties of the compound PaBe/sub 13/ pertinent to source fabrication and a methed for preparing suitable material are described. Designs of cylindrical and spherical containers suitable for magnetic handling are presented. A technique for encapsulating the neutron emitting material and testing the integrity of the resulting source is described in detail. (auth).

Author: Paul F Whitworth (Jr)
Publisher:
ISBN:
Category :
Languages : en
Pages : 62

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In this study the manganese-sulfate-bath technique was used to determine the total neutron output of a Plutonium-Beryllium neutron source. Activation trials were conducted using 4 different concentrations of manganese sulfate and 3 different size containers. Correction factors for source absorption, non-leakage, and resonance absorption were calculated using data generated by MORSE, a Monte Carlo neuron transport code. Values for these factors were calculated for manganese sulfate concentrations between 5.56% and 36.00%, and volumes from 17.2 to 160 liters in cylindrical containers. A source strength of 1.07 x 10 to the 7th + or - 3% neutrons per second was found by using experimentally measured manganese activity in conjunction with the computer-predicted correction factors.

Author: John A. Devanney
Publisher:
ISBN:
Category :
Languages : en
Pages : 36

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Plutonium-Beryllium (Pu-Be) neutron sources are calibrated with respect to total output, using a manganese-sulfate bath. When such sources are used as a point isotropic, secondary standard, inaccuracies occur due to the following reasons: (1) The neutron output is not isotropic, (2) the neutron output increases with time due to the build-up of Americium-241, resulting from the impurity of Plutonium-241, (3) the output spectrum is continuous from approximately 0.5 MeV to 10 MeV, (4) gamma rays exceed the number of neutrons emitted from the source. This report (1) presents the angular distribution of the neutron output of an 80 gram (4.81 curie) Plutonium-Beryllium neutron source, (2) shows that the increase in neutron output, due to the build-up of Americium-241 is 5.3 percent for a period of 43 months, (3) presents the neutron and gamma ray spectral distribution and intensity, (4) shows a neutron to gamma ray intensity ratio of 0.61:1 and a neutron to gamma ray dose (first collision-rads tissue) ratio of 9.36:1, (5) shows that a correction factor of 6.6 percent is required when the source is used as a point isotropic source of neutrons. (Author).

Author:
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ISBN:
Category : Industrial safety
Languages : en
Pages : 120

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Author:
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ISBN:
Category :
Languages : en
Pages : 7

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The FRAM code was originally developed to analyze high-resolution gamma spectra from plutonium items. Its capabilities have since been expanded to include analysis of uranium spectra. The flexibility of the software also enables a capable spectroscopist to use FRAM to analyze spectra in which neither plutonium nor uranium is present in significant amounts. This paper documents the use of FRAM to determine the 239Pu/241Am, 243Am/241Am, 237Np/241Am, and 239Np/241Am ratios in americium-beryllium neutron sources. The effective specific power of each neutron source was calculated from the ratios determined by FRAM in order to determine the americium mass of each of these neutron sources using calorimetric assay. We will also discuss the use of FRAM for the general case of isotopic analysis of nonplutonium, nonuranium items.