Effective Neutron Removal Cross Sections For Shielding
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Effective Neutron Removal Cross Sections For Shielding
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Author : G. T. Chapman
language : en
Publisher:
Release Date : 1956
Effective Neutron Removal Cross Sections For Shielding written by G. T. Chapman and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1956 with Neutron cross sections categories.
Effective Neutron Removal Cross Sections For Carbon And Oxygen In Continuous Mediums
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Author : D. K. Trubey
language : en
Publisher:
Release Date : 1958
Effective Neutron Removal Cross Sections For Carbon And Oxygen In Continuous Mediums written by D. K. Trubey and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1958 with Fast neutrons categories.
Measurement Of An Effective Neutron Removal Cross Section Of Lithium At The Lid Tank Shielding Facility
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Author : G. T. Chapman
language : en
Publisher:
Release Date : 1954
Measurement Of An Effective Neutron Removal Cross Section Of Lithium At The Lid Tank Shielding Facility written by G. T. Chapman and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1954 with Lithium categories.
Calculation Of Thermal Neutron Fluxes In Primary Shields
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Author : D. C. Anderson
language : en
Publisher:
Release Date : 1959
Calculation Of Thermal Neutron Fluxes In Primary Shields written by D. C. Anderson and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1959 with Neutron flux categories.
Effective Dose Removal Cross Section Of 14 Mev Neutrons
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Author :
language : en
Publisher:
Release Date : 1983
Effective Dose Removal Cross Section Of 14 Mev Neutrons written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1983 with categories.
The concept of removal cross section devised for fission neutron shielding calculations has been extended to include the case of DT fusion neutrons. Values of 14 MeV neutron dose removal cross sections for Li, C, Al, Ca, Ti, Fe, Cu, Zr, Nb, Mo, W, and Pb followed by polyethylene of various thicknesses are tabulated. Parametric fitting has also been carried out. The results show that the analytic form of the expression obtained for the fission case is equally applicable for the DT fusion neutron case. Study of the systematics of the removal cross sections for elements followed by a thick polyethylene layer showed that the results are consistent with theoretical and phenomenological predictions.
Introduction To Shield Design
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Author : E. P. Blizard
language : en
Publisher:
Release Date : 1952
Introduction To Shield Design written by E. P. Blizard and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1952 with Nuclear reactors categories.
Neutron Cross Sections And Technology
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Author : David T. Goldman
language : en
Publisher:
Release Date : 1968
Neutron Cross Sections And Technology written by David T. Goldman and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1968 with Neutron cross sections categories.
A Summary Of Shielding Constants For Concrete
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Author : R. L. Walker
language : en
Publisher:
Release Date : 1961
A Summary Of Shielding Constants For Concrete written by R. L. Walker and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with Concrete categories.
The present knowledge of the shielding constants of concrete is summarized. The densities, elemental compositions, and mixes, where available, are given for a wide range of concretes. From these data, various constants useful for shielding calculations were computed. These constants include the removal cross sections, total cross sections, average thermal neutron absorption cross sections, thermal neutron diffusion coefficients, reciprocal thermal neutron diffusion lengths, total gamma-ray linear attenuation coefficients, gamma-ray energy absorption linear attenuation coefficients, the effective atomic numbers for the determination of buildup factors, and the capture gamma-ray spectra. Experimental results are included where available.
Barytes Concrete For Radiation Shielding
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Author : William Jackson Grantham
language : en
Publisher:
Release Date : 1961
Barytes Concrete For Radiation Shielding written by William Jackson Grantham and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1961 with Concrete categories.
Procedures For Shielding Calculations
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Author : R. Dennis
language : en
Publisher:
Release Date : 1957
Procedures For Shielding Calculations written by R. Dennis and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1957 with Nuclear merchant ships categories.