Author: Gašper Žerovnik
Publisher:
ISBN:
Category :
Languages : en
Pages : 10
Book Description
Characterization of the neutron flux and spectrum in the irradiation channels of the TRIGA reactor at IJS
Neutron Spectrum Unfolding in Three Irradiation Channels of the JSI TRIGA Mark II Reactor with the GRUPINT Code
Characterization of Neutron Flux Spectra for Radiation Effects Studies
Author: Joseph Turner Graham
Publisher:
ISBN:
Category :
Languages : en
Pages : 176
Book Description
The effects of neutron displacement damage on materials are sensitive to neutron energy spectra. In controlled neutron damage experiments, a well characterized neutron flux spectrum is critical in determining the equivalent dose for displacement damage. Two techniques were used to characterize the neutron flux spectra in the University of Texas at Austin TRIGA research nuclear reactor. The first technique uses a standard method of measuring the reaction rates of two identical metal foils, one of which was irradiated in a Cd cover, the other of which was irradiated bare. Assuming an analytic form of the neutron spectrum the reaction rates were used to determine an approximate spectrum. The second technique uses the reaction rates measured from a set of activated metal foils along with two spectral unfolding techniques to approximate and then refine the neutron spectrum. A Matlab code was developed which fits radiative capture reaction rates to an approximate spectrum using a least squares approach. The result was used as an initial guess in a second Matlab code which refines the epithermal and fast energy ranges of the spectrum using reaction rates from threshold reactions. Errors in the reaction rates calculated from the resulting spectrum to the measured reaction rates were used to assess the accuracy of the final neutron spectrum.
Publisher:
ISBN:
Category :
Languages : en
Pages : 176
Book Description
The effects of neutron displacement damage on materials are sensitive to neutron energy spectra. In controlled neutron damage experiments, a well characterized neutron flux spectrum is critical in determining the equivalent dose for displacement damage. Two techniques were used to characterize the neutron flux spectra in the University of Texas at Austin TRIGA research nuclear reactor. The first technique uses a standard method of measuring the reaction rates of two identical metal foils, one of which was irradiated in a Cd cover, the other of which was irradiated bare. Assuming an analytic form of the neutron spectrum the reaction rates were used to determine an approximate spectrum. The second technique uses the reaction rates measured from a set of activated metal foils along with two spectral unfolding techniques to approximate and then refine the neutron spectrum. A Matlab code was developed which fits radiative capture reaction rates to an approximate spectrum using a least squares approach. The result was used as an initial guess in a second Matlab code which refines the epithermal and fast energy ranges of the spectrum using reaction rates from threshold reactions. Errors in the reaction rates calculated from the resulting spectrum to the measured reaction rates were used to assess the accuracy of the final neutron spectrum.
Measurements and calculations of the neutron spectrum in different irradiation channels of the TRIGA Mark II reactor, Slovenia
Characterization of the Neutron Flux Spectrum at the Missouri University of Science and Technology Research Reactor
Author: Zachary Andrew Kulage
Publisher:
ISBN:
Category : Least squares
Languages : en
Pages : 0
Book Description
"A new remotely accessible shielded cell is being constructed at the Missouri University of Science and Technology Research Reactor (MSTR). The heavily shielded cell will be able to receive highly irradiated specimens directly from the reactor and will be equipped with radiation-hardened cameras, remote manipulators and gamma spectroscopy. The cell will allow the manipulation and monitoring of highly activated specimens from both a workstation at the MSTR and at remote locations using a Webbased internet interface. The ability to access and control the shielded cell via a remote internet connection will make it useful to a wide variety of users. Samples will be transferred to and from the cell using a pneumatic rabbit system that is directly attached to the nuclear reactor core. In support of the shielded cell the neutron spectrum has been measured using foil flux monitors. Multiple foils were irradiated and iterative runs were completed using the SAND-II program. An MCNP model was also developed to provide an approximate neutron flux spectrum to serve as an initial estimate for the SAND-II least squares fitting technique. The results showed a strong agreement in the thermal neutron energy region"--Abstract, leaf iv
Publisher:
ISBN:
Category : Least squares
Languages : en
Pages : 0
Book Description
"A new remotely accessible shielded cell is being constructed at the Missouri University of Science and Technology Research Reactor (MSTR). The heavily shielded cell will be able to receive highly irradiated specimens directly from the reactor and will be equipped with radiation-hardened cameras, remote manipulators and gamma spectroscopy. The cell will allow the manipulation and monitoring of highly activated specimens from both a workstation at the MSTR and at remote locations using a Webbased internet interface. The ability to access and control the shielded cell via a remote internet connection will make it useful to a wide variety of users. Samples will be transferred to and from the cell using a pneumatic rabbit system that is directly attached to the nuclear reactor core. In support of the shielded cell the neutron spectrum has been measured using foil flux monitors. Multiple foils were irradiated and iterative runs were completed using the SAND-II program. An MCNP model was also developed to provide an approximate neutron flux spectrum to serve as an initial estimate for the SAND-II least squares fitting technique. The results showed a strong agreement in the thermal neutron energy region"--Abstract, leaf iv
Neutron Flux and Spectra Measurements in the Void Tank of the TRIGA Mark-F Reactor
Author: K. C. Humpherys
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 22
Book Description
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 22
Book Description
Measurement of Neutron Flux and Spectra for Physical and Biological Applications
Author: National Committee on Radiation Protection and Measurements (U.S.)
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 104
Book Description
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 104
Book Description
Measurement of Neutron Flux and Spectra for Physical and Biological Applications
Author: National Committee on Radiation Protection and Measurements (U.S.)
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 104
Book Description
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 104
Book Description
The Energy Spectrum of Leakage Neutrons from a Homogeneous Reactor
Revised Neutron Flux, Spectrum, and Tissue Dose Measurements at the Godiva II Critical Assembly
Author: Joseph A. Sayeg
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 50
Book Description
Publisher:
ISBN:
Category : Neutron flux
Languages : en
Pages : 50
Book Description