Distribution Of Radiation From A 14 Mev Neutron Source In And Near Structures PDF Download

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Protection Against Neutron Radiation

Protection Against Neutron Radiation
Author: National Council on Radiation Protection and Measurements
Publisher:
Total Pages: 172
Release: 1971
Genre: Science
ISBN:

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Sensitivity of the Transport of 14-MeV Neutrons to the Nitrogen Elastic Angular Distribution

Sensitivity of the Transport of 14-MeV Neutrons to the Nitrogen Elastic Angular Distribution
Author: William B. Beverly
Publisher:
Total Pages: 76
Release: 1973
Genre:
ISBN:

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Calculations have been made to determine the radiation fields that would be generated by the transport of 14 MeV neutrons from a monodirectional point source in uniform nitrogen using two different cross section sets. One set was compiled from the ENDF/B Round-2 nuclear data file. The other set was compiled from the same ENDF/B Round-2 file; however, the shape of the elastic angular distribution was replaced by that of the ENDF/B Round-1 angular distribution. The correlated-sampling, Monte-Carlo, neutron-transport code SAMCEP was used for the calculations in order to facilitate more meaningful comparisons between the calculated answers of the two problems. (Modified author abstract).


Dose Attenuation by Soils and Concrete for Broad, Parallel-beam Neutron Sources

Dose Attenuation by Soils and Concrete for Broad, Parallel-beam Neutron Sources
Author: David Spielberg
Publisher:
Total Pages: 172
Release: 1958
Genre: Neutron sources
ISBN:

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The multi-group theory which was utilized has obvious deficiencies in that certain nuclear scattering characteristics are simplified or ignored. Therefore, the results should not be construed as "scientific-type" data where comparison with experiment can result in gaining some insight regarding the primary nuclear scattering processes.


Technical Concept

Technical Concept
Author: F. F. Haywood
Publisher:
Total Pages: 28
Release: 1965
Genre: Neutron sources
ISBN:

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A small but intense source of 14 Mev neutrons is to be mounted in the hoisting mechanism of the 1500-ft BREN tower at the Nevada Test Site. The experimental program, designated Operation HENRE, will be conducted during the spring and summer of 1965 and will be sufficiently comprehensive to characterize the radiation fields. In addition, a series of applied shielding experiments will include configurations of interest to both military and civilian laboratories. It is important that data be accumulated which will assist in understanding the apparent uncertainties in existing transport calculations, especially data which will give approximate values for effective neutron cross sections for air-over-ground transport. The neutron source will be operated at heights from about 25 ft to 1500 ft above the air-ground interface. The average neutron yield during operational periods of about 4 hours is expected to be equal to or greater than 10 13 n/sec.