Abstract
The purpose of this work is to estimate the life of the prompt neutrons, i, of a nuclear reactor utilizing the neutron noise analysis. This technique carry to development of mathematical model that is valid for lower powers reactor. The equation resulting convey to the observation about power spectrum behaviour respect to the frecquency. In this case, the reactor in study is the Triga Mark III of Nuclear Center of Mexico that it was provided of fission chambers for register the neutron fluxes. These fluxes was digitized and storage in computer disc as signals dependents of time, for later apply the Fourier Transformation and obtain the spectras. The spectras measured to different reactor powers were adjusted to the development equation before, using the method of square minimum and so estimate the parameter i. The analysis of results throw a value of 22.73 +/- 0.92 {mu}s. On the other hand, the calculate value to the resolve the kinetic equation of reactor defer in lower than 4 % about the estimate. Of this, it concludes that the model utilized is trusty with a good mistake margin, moreover of that the technique of Neutron Noise analysis demonstrate be competitive (Author).
Citation Formats
Ortiz Servin, J J.
Lifetime measurement of prompt neutrons using the neutronic noise analysis.; Medicion del tiempo de vida de los neutrones inmediatos usando analisis de ruido neutronico..
Mexico: N. p.,
1992.
Web.
Ortiz Servin, J J.
Lifetime measurement of prompt neutrons using the neutronic noise analysis.; Medicion del tiempo de vida de los neutrones inmediatos usando analisis de ruido neutronico..
Mexico.
Ortiz Servin, J J.
1992.
"Lifetime measurement of prompt neutrons using the neutronic noise analysis.; Medicion del tiempo de vida de los neutrones inmediatos usando analisis de ruido neutronico."
Mexico.
@misc{etde_10132050,
title = {Lifetime measurement of prompt neutrons using the neutronic noise analysis.; Medicion del tiempo de vida de los neutrones inmediatos usando analisis de ruido neutronico.}
author = {Ortiz Servin, J J}
abstractNote = {The purpose of this work is to estimate the life of the prompt neutrons, i, of a nuclear reactor utilizing the neutron noise analysis. This technique carry to development of mathematical model that is valid for lower powers reactor. The equation resulting convey to the observation about power spectrum behaviour respect to the frecquency. In this case, the reactor in study is the Triga Mark III of Nuclear Center of Mexico that it was provided of fission chambers for register the neutron fluxes. These fluxes was digitized and storage in computer disc as signals dependents of time, for later apply the Fourier Transformation and obtain the spectras. The spectras measured to different reactor powers were adjusted to the development equation before, using the method of square minimum and so estimate the parameter i. The analysis of results throw a value of 22.73 +/- 0.92 {mu}s. On the other hand, the calculate value to the resolve the kinetic equation of reactor defer in lower than 4 % about the estimate. Of this, it concludes that the model utilized is trusty with a good mistake margin, moreover of that the technique of Neutron Noise analysis demonstrate be competitive (Author).}
place = {Mexico}
year = {1992}
month = {Dec}
}
title = {Lifetime measurement of prompt neutrons using the neutronic noise analysis.; Medicion del tiempo de vida de los neutrones inmediatos usando analisis de ruido neutronico.}
author = {Ortiz Servin, J J}
abstractNote = {The purpose of this work is to estimate the life of the prompt neutrons, i, of a nuclear reactor utilizing the neutron noise analysis. This technique carry to development of mathematical model that is valid for lower powers reactor. The equation resulting convey to the observation about power spectrum behaviour respect to the frecquency. In this case, the reactor in study is the Triga Mark III of Nuclear Center of Mexico that it was provided of fission chambers for register the neutron fluxes. These fluxes was digitized and storage in computer disc as signals dependents of time, for later apply the Fourier Transformation and obtain the spectras. The spectras measured to different reactor powers were adjusted to the development equation before, using the method of square minimum and so estimate the parameter i. The analysis of results throw a value of 22.73 +/- 0.92 {mu}s. On the other hand, the calculate value to the resolve the kinetic equation of reactor defer in lower than 4 % about the estimate. Of this, it concludes that the model utilized is trusty with a good mistake margin, moreover of that the technique of Neutron Noise analysis demonstrate be competitive (Author).}
place = {Mexico}
year = {1992}
month = {Dec}
}