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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
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
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.
Author: Romel Siqueira França Publisher: ISBN: Category : Languages : en Pages : 137
Book Description
This research presents the characterization, modeling, and design of the UFTR (University of Florida Training Reactor) radiation beam ports for reactor analysis applications. Extensive validation of beam port is required. Using MCNP5 results were produced for the multigroup neutron flux distributions, neutron spectrum and neutron reaction rates. Due to the strength of the neutron source in the reactor core, the neutron flux distribution and reaction rate can be monitored along the radiation beam port. The goal of the design in this research is to determine the neutron flux distribution, neutron energy flux and neutron reaction rate throughout the beam port. The calculation of the neutron flux distribution, neutron spectrum and neutron reaction rates along the beam port were tallied. To compute the multigroup neutron flux distributions, and neutron energy flux FMESH4 and *F4 tallies were used, respectively. Sets of 47 and 62 energy groups were analyzed for these tallies. To calculate neutron reaction rates, the tally F4 along with the tally multiplier FM4 was used.
Author: Y-Q Wang Publisher: ISBN: Category : Flexible tolerance method Languages : en Pages : 8
Book Description
A parametrized approach, called the modified flexible tolerance, is used to unfold the reactor neutron flux spectrum based on the reaction rates measured by detectors. For the thermal neutron reactor, six parameters are involved. For the neutron flux spectrum of intermediate and fast reactors, the parameters may be reduced to four. for such method, no initial spectrum is required. Our calculations show that the neutron flux spectra obtained for China's SPR and HWRR and Japan's KUR with measured values of reaction rate fit well with those obtained with NEUSPAC code (SAND-II type). The result is also good for the ORR, the MOL-?? Facility, the YAYOI and the CFRMF. It can be concluded that this method provides an easy and convenient tool for quantitatively understanding the macroscopic characteristics of the neutron flux spectrum.
Author: Zachary Andrew Kulage
Author: Zachary Andrew Kulage
Author: Joseph Turner Graham
Author: J. C. Robinson
Author: Romel Siqueira França
Author: K. C. Humpherys
Author: Y-Q Wang
Author: National Committee on Radiation Protection and Measurements (U.S.)
Author: F. L. Fillmore
Author: Avery M. Gage
Author: