Determination of the Neutron Flux for the Yankee Rowe Experiment in the Ford Nuclear Reactor

2009 ◽  
pp. 628-628-10
Author(s):  
RJ Cacciapouti ◽  
L Petrusha
Keyword(s):  
Neutron Flux ◽  
Nuclear Reactor

scholarly journals Choosing the optimal conditions for irradiation of specimens in the material testing channel of the VVR-M nuclear reactor

2020 ◽  
Vol 19 (4) ◽  
pp. 16-22
Author(s):  
V. I. Borysenko ◽  
◽  
V. V. Goranchuk ◽  
E. M. Chalyi ◽  
V. V. Stadnik ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Flux Density ◽  
Nuclear Reactor ◽  
Irradiation Time ◽  
Material Testing ◽  
Fast Neutrons ◽  
Height Distribution ◽  
Optimal Conditions ◽  
Research Nuclear Reactor

The methodology for choosing the optimal conditions for irradiation of specimens in the material testing channel of the VVR-M research nuclear reactor is presented in the article. The solution to such a problem is necessary to justify the possibility of irradiation of specimens in the material testing channel under given irradiation conditions. In this case, the irradiation conditions include not only the height distribution of the neutron flux density, but also the spectrum of neutrons and the temperature of the specimen in the material testing channel. This approach optimizes the work of VVR-M reactor by placing the maximum possible number of specimens in the material testing channel for irradiation. Also, the optimization of the VVR-M operation involves choosing the location of the research channel in the VVR-M core, where, during the planned irradiation time, the maximum flux density of fast neutrons or neutrons of other energies will be reached, depending on the task. The neutron-physical model of the research nuclear reactor VVR-M in the calculation code SCALE was used for research. The reliability in the determination of neutron-physical characteristics in the VVR-M material testing channel is confirmed by the results of validation carried out at the previous stage of research. It is shown that in order to ensure the necessary accuracy in the determination of the neutron flux parameters in the material testing channel, it is necessary to take into account the fuel burnup, as well as the actual scheme of fuel assemblies rearranging in the VVR-M core for various fuel loads. The results of calculations of important neutronphysical characteristics of the model of a VVR-M nuclear reactor for fuel loading, which is in operation today, on the basis of which it is possible to optimize the choice of the location of the material testing channel in the VVR-M core are presented in the article.

scholarly journals EXPERIMENTAL DETERMINATION OF THE ZERO POWER TRANSFER FUNCTION OF THE AKR-2

2021 ◽  
Vol 247 ◽  
pp. 21009
Author(s):  
Sebastian Hübner ◽  
Alexander Knospe ◽  
Marco Viebach ◽  
Carsten Lange ◽  
Antonio Hurtado
Keyword(s):  
Lower Bound ◽  
Transfer Function ◽  
Neutron Flux ◽  
Basic Characteristic ◽  
Nuclear Reactor ◽  
Power Reactor ◽  
Plateau Region ◽  
Reactor Transfer ◽  
Good Agreement

The transfer function is a basic characteristic of every nuclear reactor. It describes how a perturbation at a given place and time influences the neutron flux. In case of a known perturbation, the determination of characteristic reactor parameters is possible. The present paper shows an experimental method to determine the gain of the zero-power reactor transfer function (ZPTF) of the AKR-2 reactor at TU Dresden and the comparison to the theoretical shape of the ZPTF derived from kinetic parameters simulated with MCNP. For the experiments, a high-precision linear motor axis is used to insert an oscillating perturbation acting at frequencies smaller than the lower bound of the plateau region of the ZPTF. For higher frequencies, a rotating absorber is used. This device emulates an absorber of variable strength. The reactor response is detected with a He-3 counter. The data evaluation shows good agreement between measured and corresponding theoretical values of the gain of the ZPTF.

Determination of 1-keV to 1-MeV Neutron Flux by Radiative Capture (n, $\gamma $ ) on92,94 Zr Dosimeters

2017 ◽  
Vol 64 (3) ◽  
pp. 901-907 ◽  
Author(s):  
Victoria Sergeyeva ◽  
Nicolas Thiollay ◽  
Gunther Korschinek ◽  
Christophe Domergue ◽  
Olivier Vigneau ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Radiative Capture

Determination of the Hydrogen Concentration in Zr-2.5Nb Alloy by a Resonant Ultrasound Spectroscopy

2006 ◽  
Vol 321-323 ◽  
pp. 1576-1579
Author(s):  
Yong Moo Cheong ◽  
Young Suk Kim
Keyword(s):  
Hydrogen Concentration ◽  
Zirconium Alloy ◽  
Nuclear Reactor ◽  
Zirconium Alloys ◽  
Resonant Ultrasound Spectroscopy ◽  
Heavy Water Reactor ◽  
Resonant Ultrasound ◽  
Non Destructive

Zirconium alloys are used for many applications in nuclear components, such as the pressure tube material in a pressurized heavy water reactor, nuclear fuel cladding, etc. One of the problems during the operation of a nuclear reactor is the degradation of the zirconium alloys, which is due to an increase of the hydrogen content in the zirconium alloy. Therefore a non-destructive determination of the hydrogen concentration in zirconium alloy is one of the important issues that need to be addressed. The resonant ultrasound spectroscopy (RUS) technique is evaluated for a characterization of the hydrogen concentration in Zr-2.5Nb alloy. Referring to the terminal solid solubility for dissolution (TSSD) of Zr-2.5Nb alloy, the plot of the mechanical damping coefficient (Q-1) versus the temperature or the deviation of the resonant frequency for the temperature (df/dT) versus the temperature was correlated for the hydrogen concentration in Zr-2.5Nb alloy. It was found that the temperature at an abrupt change of the slope can be correlated with the hydrogen concentration of the Zr-2.5Nb alloy.

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