Time-Dependent Thermal-Neutron Energy Spectra in a Monoatomic Heavy Gas

Time-Dependent Thermal-Neutron Energy Spectra in a Monoatomic Heavy Gas PDF Author:
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Languages : en
Pages :

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The time-dependent thermal neutron energy spectra, for times greater thsn the slowing-down time, were generated in a monoatomic heavy gas using multigroup formalism. These spectra were obtained for infinite as well as finite media of Be and graphite. The behavior of asymptotic energy spectra during the last stage of neutron thermalization and diffusion periods was studied. The thermalization time constant for the establishment of the final Maxwellian velocity distribution of neutrons, in a monoatomic heavy gas, was estimated to be equal to (l.l74 xi SIGMA /sub so/v/sub o/)/sup -1/. Total thermalization times for neutrons in Be and graphite were found to be equal to 114 and 238 mu sec, respectively. Using the energy-dependent transport mean free path, the diffusion cooling coefficient for Be was calculated to be equal to 0.890 cm/sup 2/. For graphite, under the constant diffusion coefficient assumption, the diffusion cooling coefficient was determined to be equal to 1.922 cm/sup 2/. (auth).

Time-Dependent Thermal-Neutron Energy Spectra in a Monoatomic Heavy Gas

Time-Dependent Thermal-Neutron Energy Spectra in a Monoatomic Heavy Gas PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
The time-dependent thermal neutron energy spectra, for times greater thsn the slowing-down time, were generated in a monoatomic heavy gas using multigroup formalism. These spectra were obtained for infinite as well as finite media of Be and graphite. The behavior of asymptotic energy spectra during the last stage of neutron thermalization and diffusion periods was studied. The thermalization time constant for the establishment of the final Maxwellian velocity distribution of neutrons, in a monoatomic heavy gas, was estimated to be equal to (l.l74 xi SIGMA /sub so/v/sub o/)/sup -1/. Total thermalization times for neutrons in Be and graphite were found to be equal to 114 and 238 mu sec, respectively. Using the energy-dependent transport mean free path, the diffusion cooling coefficient for Be was calculated to be equal to 0.890 cm/sup 2/. For graphite, under the constant diffusion coefficient assumption, the diffusion cooling coefficient was determined to be equal to 1.922 cm/sup 2/. (auth).

Time Dependent Neutron Energy Spectra In Pulsed Media

Time Dependent Neutron Energy Spectra In Pulsed Media PDF Author: Surendra N. Purohit
Publisher:
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Category :
Languages : en
Pages : 166

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Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
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ISBN:
Category : Nuclear energy
Languages : en
Pages : 1644

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TID.

TID. PDF Author:
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ISBN:
Category : Energy development
Languages : en
Pages : 176

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Neutron Noise, Waves and Pulse Propagation

Neutron Noise, Waves and Pulse Propagation PDF Author:
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Category : Neutrons
Languages : en
Pages : 784

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Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
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Category : Nuclear energy
Languages : en
Pages : 1162

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Experimental Neutron Thermalisation

Experimental Neutron Thermalisation PDF Author: Peter A. Egelstaff
Publisher: Pergamon
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Category : Science
Languages : en
Pages : 424

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Proceedings of the Brookhaven Conference on Neutron Thermalization, April 30-May 2, 1962: Neutron spectra in lattices and infinite media

Proceedings of the Brookhaven Conference on Neutron Thermalization, April 30-May 2, 1962: Neutron spectra in lattices and infinite media PDF Author: Brookhaven National Laboratory
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Category : Neutrons
Languages : en
Pages : 598

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Graphite

Graphite PDF Author: U.S. Atomic Energy Commission
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Category : Graphite
Languages : en
Pages : 176

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This compilation contains 958 references to report and published literature. The references pertain primarily to reactor grade graphite, although information on the manufacture and uses of graphite in other fields is included. The references were selected from Nuclear Science Abstracts (NSA), covering the period 1948 through mid-1961. Subject, author, and availability indexes are provided.

A Review of the Methods for Computing Thermal Neutron Spectra

A Review of the Methods for Computing Thermal Neutron Spectra PDF Author: Henry C. Honeck
Publisher:
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Category : Neutrons
Languages : en
Pages : 76

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