Author: F. A. EsmaelPublisher:
ISBN:
Category :
Languages : en
Pages : 0
Book Description
A Study of the Fast Neutron Spectrum in the Utr-100 Reactor
Author: F. A. EsmaelThermal Neutron Spectrum Studies in a Beam Hole of a Utr-100 Reactor Using a Time of Flight Spectrometer
Author: J. O. S. VegaThermal Neutron Spectrum Measurements at a UTR-100 Beam Hole Utilising a Slow Neutron Chopper
Author: J. O. Saldano-VegaFast Neutron Spectrum and Dosimetry Studies in the Coupled Fast Reactivity Measurements Facility
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
The fast neutron spectrum of the Coupled Fast Reactivity Measurements Facility (CFRMF) at the Idaho National Engineering Laboratory (INEL) is being used to study and standardize fast reactor neutron dosimetry materials and methods. The CFRMF has been designated a ''benchmark experiment'' to test the cross section data of dosimetry materials as well as other materials used and produced in fast reactors. Information about the neutron energy spectrum of the CFRMF is presented. (auth).
FAST NEUTRON SPECTRUM IN ORGEL TYPE REACTORS.
Author: Fast Neutron Spectrum in Orgel Type Reactors
Author: L. AmyotLocal Change of a Neutron Spectrum in the Fast Reactor BOR-60 for Extension of Research Tasks
Author: IV. YakovlevaPublisher:
ISBN:
Category : Activation detector
Languages : en
Pages : 8
Book Description
In the fast reactor BOR-60 there have been conducted experimental and calculational investigations of neutron energy spectrum in a cell of the blanket external row assemblies. Two experiments have been carried out. In the first experiment the cell was surrounded by regular blanket assemblies, and in the second one it was surrounded by assemblies containing zirconium hydride (ZrH2). In the chosen cell extended sets of activation detectors were irradiated. Measured reaction rates for various thermal and fast neutron reactions were used to adjust the neutron spectra. For this purpose the STAYNL computer code was used. In each case, calculated neutron spectra were used as a priori. Calculations of neutron spectra were carried out in the two-dimensional hexagonal geometry with the NF-6 code and in the three-dimensional hexagonal geometry with the JARFR code with the ABBN cross section library. The results of the presented comparisons for two configurations are discussed and the results of the investigation of the accumulation of 153Gd from natural europium in the softened neutron spectrum are adduced.
A Numerical Study of the Fast Neutron Spectrum in Homogeneous Media
Author: G. RowlandsAn Easier Way to a Harder Spectrum
Author: Michael T. Pierce (Jr.)Publisher:
ISBN:
Category :
Languages : en
Pages : 998
Book Description
The TRIGA Mark II research reactor has a flux spectrum with a predominance of thermal neutrons. While most research can be conducted using this thermal neutron flux, an exclusively fast neutron flux is preferred for some experiments, such as radiation damage studies. Although fast neutron flux spectrums are available using fast reactors or neutron generators, only a few fast reactors are currently in operation and neutron generators tend to have low fluxes. As a result, this report evaluated the possibility of generating a fast neutron flux spectrum in a thermal reactor through the use of an irradiator consisting of layers of uranium, boron, and cadmium. Simulations using Monte Carlo N-Particle Code (MCNP) determined that thin layers of these materials in an irradiator inserted into the 3-Element Facility of the UT-Austin TRIGA reactor will generate a fast neutron flux spectrum with negligible thermal flux and where over 91% of the total flux consists of neutrons with energy greater than 10 keV. Further research is recommended to calculate heat dissipation and to determine the reactivity worth of the irradiator
Author: Robert G. Cochran