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A Prompt D-D Neutron Calibration Of A Plastic Scintillator Detector, Dal H. Jensen
A Prompt D-D Neutron Calibration Of A Plastic Scintillator Detector, Dal H. Jensen
Nuclear Engineering ETDs
ABSTRACT
A new approach to the measurement of the neutron yield of low intensity (~ 2 x 10 neutrons/pulse) 0-0 neutron generators in a single pulse is described. A cylindrical (20.32 cm radius by 20.32 cm height) scintillator of Pilot-Bis optically coupled to a Phillips 57AVP photomultiplier with a 20 cm diameter photocathode. The light pulse resulting from the neutron burst is fed into a voltage integrator calibrated in neutrons/ count.
The initial calibration of the stable neutron generator used in the scintillator calibration was performed using a silver activation detector (PT-502) designed by LASL. The data obtained for the …
Safeguards Considerations For A Htgr Nuclear Fuel Cycle, Philip G. Johnson
Safeguards Considerations For A Htgr Nuclear Fuel Cycle, Philip G. Johnson
Nuclear Engineering ETDs
Given that the prime objective of safeguards for special nuclear materials (SNM) is nonproliferation of nuclear weapons, it is logical that safeguards priorities should be commensurate with the relative suitabilities of the various SNM forms in existence for application in nuclear explosives. The SNM forms in each reactor fuel cycle, for example, should be screened and ordered according to their relative suitabilities for such misapplication. Significant considerations in assigning protection priorities include the relative suitabilities based on materials characteristics, inherent protection features of the mateerials or the processing of the SNM forms, the quantities of these materials in existence, and …
Methods For Calculating Energy Deposition Using Coupled Neutron-Gamma Ray Transport, Lewis Douglas Rigdon
Methods For Calculating Energy Deposition Using Coupled Neutron-Gamma Ray Transport, Lewis Douglas Rigdon
Nuclear Engineering ETDs
In radiation damage problems, it is desirable to know not only the neutron and gamma ray fluxes but also the energy deposition due to those fluxes. Following the recent availability of coupled neutron-gamma ray, multigroup-multitable cross sections and associated fluence-to-KERMA factors, an automated method has been developed for obtaining the energy deposition in a material region due to local neutron and gamma ray fluxes. Cross section sets which combine neutron and photon transport as well as a production matrix for neutron-induced gamma rays are used in the transport calculation. Thus in one discrete ordinates transport calculation, the energy deposition from …