Author: Thomas M. JaskunasPublisher:
ISBN:
Category : Neutron cross sections
Languages : en
Pages :
Book Description
Construction and Calibration of a Fast Neutron Spectroscopy System
Author: Thomas M. JaskunasPublisher:
ISBN:
Category : Neutron cross sections
Languages : en
Pages :
Book Description
Construction and Calibration of a Fast Neutron Spectrum Generator
Author: Kenneth Dwight DobbinPublisher:
ISBN:
Category : Neutron sources
Languages : en
Pages : 228
Book Description
A standard fast reactor spectrum can be created by the partial moderation of the U-235 fission spectrum in an air cavity. Spherical natural uranium shells are driven by thermal neutrons from a thermal column. The uranium is placed at the center of a spherical graphite hohlraum to reduce the anisotropic effect of a planar source of thermal neutrons. The Oregon State University (OSU) fast neutron spectrum facility design employs this method which is being used by Albert Fabry in Mol, Belgium and the NISUS assembly in London, United Kingdom, to create a fast neutron spectrum. The OSU facility uses the ther malizing column of a TRIGA Mark II reactor for a thermal neutron source. The mechanical design is presented showing the location of the facility, the aluminum container and internals, and the transport assembly. Two computer codes are introduced in the nuclear design. SLAB is a first approximation diffusion theory code which justifies the use of one foot of graphite backed with water in place of "infinite graphite." FASTSPEC is a diffusion theory approximation code in spherical geometry which shows that the design will produce a spectrum characteristic of a fast reactor. Phase I operation is a mechanical test, health physics evaluation, and a thermal neutron calibration of the facility with a thermal neutron absorber in place of the uranium. The data for phase I is included. Phase II operation will be the insertion of an uranium driver shell and the calibration of the fast spectrum. Only phase I is complete at this time.
CONSTRUCTION AND CALIBRATION OF A FAST NEUTRON SCINTILLATION SPECTROMETER.
Author: קונטרס ועת שלום
Author: Neutron Source Strength Calibrations
Author: E. Dale McGarryPublisher:
ISBN:
Category : Neutron counters
Languages : en
Pages : 68
Book Description
Design of a Transportable High Efficiency Fast Neutron Spectrometer
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 10
Book Description
A transportable fast neutron detection system has been designed and constructed for measuring neutron energy spectra and flux ranging from tens to hundreds of MeV. The transportability of the spectrometer reduces the detector-related systematic bias between different neutron spectra and flux measurements, which allows for the comparison of measurements above or below ground. The spectrometer will measure neutron fluxes that are of prohibitively low intensity compared to the site-specific background rates targeted by other transportable fast neutron detection systems. To measure low intensity high-energy neutron fluxes, a conventional capture-gating technique is used for measuring neutron energies above 20 MeV and a novel multiplicity technique is used for measuring neutron energies above 100 MeV. The spectrometer is composed of two Gd containing plastic scintillator detectors arranged around a lead spallation target. To calibrate and characterize the position dependent response of the spectrometer, a Monte Carlo model was developed and used in conjunction with experimental data from gamma ray sources. Multiplicity event identification algorithms were developed and used with a Cf-252 neutron multiplicity source to validate the Monte Carlo model Gd concentration and secondary neutron capture efficiency. The validated Monte Carlo model was used to predict an effective area for the multiplicity and capture gating analyses. For incident neutron energies between 100 MeV and 1000 MeV with an isotropic angular distribution, the multiplicity analysis predicted an effective area of 500 cm2 rising to 5000 cm2. For neutron energies above 20 MeV, the capture-gating analysis predicted an effective area between 1800 cm2 and 2500 cm2. As a result, the multiplicity mode was found to be sensitive to the incident neutron angular distribution.
Construction and Calibration of Neutron Long Counter
Author: Robert Winfield WoodPublisher:
ISBN:
Category : Nuclear counters
Languages : en
Pages : 74
Book Description
Nuclear Science Abstracts
Author: Proceedings of the Special Session on Fast Neutron Spectroscopy
Author: American Nuclear SocietyPublisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 476
Book Description
Author: Gale Gene Simons