Author: Stewart Whittlestone
Publisher:
ISBN: 9780642997647
Category : Beryllium
Languages : en
Pages : 5
Book Description
Neutron Energy Spectra from the Thick Target 9Be(d,n)10 B Reaction
Author: Stewart Whittlestone
Publisher:
ISBN: 9780642997647
Category : Beryllium
Languages : en
Pages : 5
Book Description
Publisher:
ISBN: 9780642997647
Category : Beryllium
Languages : en
Pages : 5
Book Description
Neutron Energy Spectra from the Thick Target Beryllium 9(d,n) Boron 10 Reaction
Author: S. Whittlestone
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages :
Book Description
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages :
Book Description
The Neutron Spectra of Po-B and Po-Be
Author: I. H. Perlman
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 22
Book Description
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 22
Book Description
Neutron Angular Distributions and Spectra Produced by the Bombardment of Thick Targets by Deuterons
Author: C. E. Falk
Publisher:
ISBN:
Category : Deuterons
Languages : en
Pages : 288
Book Description
Publisher:
ISBN:
Category : Deuterons
Languages : en
Pages : 288
Book Description
The Thick-target 9Be(d, N) Neutron Spectra for Deuteron Energies Between 2.6 and 7.0-MeV.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 49
Book Description
The measurement of the zero deg. neutron spectra and yields from deuterons incident on thick beryllium metal targets is described. 235U and 238U fission ion chambers were used as neutron detectors to span the neutron energy range above 0.05-MeV with a time resolution of (less-than or equal to) 3 nanosec. Measurements were made for incident deuteron energies from 2.6 to 7.0-MeV, at 0.4-MeV intervals, using time-of-flight techniques with flight paths of 2.7 and 6.8 meters. The results are presented in graphical form and in tables.
Publisher:
ISBN:
Category :
Languages : en
Pages : 49
Book Description
The measurement of the zero deg. neutron spectra and yields from deuterons incident on thick beryllium metal targets is described. 235U and 238U fission ion chambers were used as neutron detectors to span the neutron energy range above 0.05-MeV with a time resolution of (less-than or equal to) 3 nanosec. Measurements were made for incident deuteron energies from 2.6 to 7.0-MeV, at 0.4-MeV intervals, using time-of-flight techniques with flight paths of 2.7 and 6.8 meters. The results are presented in graphical form and in tables.
The Thick-target Sup 9 Be(d, N) Neutron Spectra for Deuteron Energies Between 2. 6 and 7. 0-MeV.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 49
Book Description
The measurement of the zero deg. neutron spectra and yields from deuterons incident on thick beryllium metal targets is described. 235U and 238U fission ion chambers were used as neutron detectors to span the neutron energy range above 0.05-MeV with a time resolution of (less-than or equal to) 3 nanosec. Measurements were made for incident deuteron energies from 2.6 to 7.0-MeV, at 0.4-MeV intervals, using time-of-flight techniques with flight paths of 2.7 and 6.8 meters. The results are presented in graphical form and in tables.
Publisher:
ISBN:
Category :
Languages : en
Pages : 49
Book Description
The measurement of the zero deg. neutron spectra and yields from deuterons incident on thick beryllium metal targets is described. 235U and 238U fission ion chambers were used as neutron detectors to span the neutron energy range above 0.05-MeV with a time resolution of (less-than or equal to) 3 nanosec. Measurements were made for incident deuteron energies from 2.6 to 7.0-MeV, at 0.4-MeV intervals, using time-of-flight techniques with flight paths of 2.7 and 6.8 meters. The results are presented in graphical form and in tables.
Comparison of (alpha, N) Thick-target Neutron Yields and Spectra from ORINGEN-S and SOURCES.
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Both ORIGEN-S and SOURCES generate thick-target neutron yields and energy spectra from ([alpha], n) reactions in homogeneous materials. SOURCES calculates yield and spectra for any material containing [alpha]-emitting and ([alpha], n) target elements by simulating reaction physics, using [alpha]-emission energy spectra, elemental stopping cross sections, ([alpha], n) cross sections for target nuclei, and branching fractions to produce-nuclide energy levels. This methodology results in accurate yield and spectra. ORIGEN-S has two options for calculating yields and spectra. The UO[sub 2] option (default) estimates yields and spectra assuming the input [alpha]-emitters to be infinitely dilute in UO[sub 2]. The borosilicate-glass option estimates yields from the total input material composition and generates spectra purportedly representative of spectra generated by [sup 238]Pu, [sup 241]Am, [sup 242]Cm, and [sup 244]Cm infinitely dilute in borosilicate glass, even if none of these four [alpha]-emitters are present in the input material composition. Because yields from the borosilicate-glass option in ORIGEN-S are based on entire input material composition and are reasonably accurate, the same is often assumed to be true for spectra. The input/output functionality of the borosilicate-glass option, along with ambiguity in ORIGEN-S documentation, gives the incorrect impression that spectra representative of input compositions are generated. This impression is reinforced by wide usage of the SCALE code system and its ORIGEN-S module and their sponsorship by the US Nuclear Regulatory Commission.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Both ORIGEN-S and SOURCES generate thick-target neutron yields and energy spectra from ([alpha], n) reactions in homogeneous materials. SOURCES calculates yield and spectra for any material containing [alpha]-emitting and ([alpha], n) target elements by simulating reaction physics, using [alpha]-emission energy spectra, elemental stopping cross sections, ([alpha], n) cross sections for target nuclei, and branching fractions to produce-nuclide energy levels. This methodology results in accurate yield and spectra. ORIGEN-S has two options for calculating yields and spectra. The UO[sub 2] option (default) estimates yields and spectra assuming the input [alpha]-emitters to be infinitely dilute in UO[sub 2]. The borosilicate-glass option estimates yields from the total input material composition and generates spectra purportedly representative of spectra generated by [sup 238]Pu, [sup 241]Am, [sup 242]Cm, and [sup 244]Cm infinitely dilute in borosilicate glass, even if none of these four [alpha]-emitters are present in the input material composition. Because yields from the borosilicate-glass option in ORIGEN-S are based on entire input material composition and are reasonably accurate, the same is often assumed to be true for spectra. The input/output functionality of the borosilicate-glass option, along with ambiguity in ORIGEN-S documentation, gives the incorrect impression that spectra representative of input compositions are generated. This impression is reinforced by wide usage of the SCALE code system and its ORIGEN-S module and their sponsorship by the US Nuclear Regulatory Commission.
The Neutron Energy Spectrum at 0° from the Reaction D(9Be, 1°B)n for a Deuteron Energy of 1.8 MeV
Author: P.J. Clements
Publisher:
ISBN: 9780705803939
Category :
Languages : en
Pages : 5
Book Description
Publisher:
ISBN: 9780705803939
Category :
Languages : en
Pages : 5
Book Description