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.

scholarly journals Determination of the safety rods (SA, SB) for optimized power reactor 1000 using the Core simulator OPR1000

2018 ◽  
Vol 1 (6) ◽  
pp. 177-184
Author(s):  
Son An Nguyen ◽  
Nguyen Trung Tran
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Nuclear Reactor ◽  
Boron Concentration ◽  
Power Reactor ◽  
Experimental Simulation ◽  
The Core ◽  
Operation Process

In order to operate a nuclear power plant, ensuring safety is the most important factor. The function of safety rods are to shut down the reactor in case of emergency. The purpose of this paper to show the result of research and determine the value of safety rods SA, SB. Determination of the Boron concentration corresponding to each group of safety rods of OPR1000 nuclear reactor ensures the safely in the whole operation process. Experimental simulation is carried out in the system simulating core reactor OP1R1000 (CoSi OPR1000). The expermental result corresponds with the theoretic calculated result of Sa and Sb with 1500 pcm, 4000 pcm. The concentrations of Boron appropriately are 134 ppm and 284 ppm, respectively.

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.

COMPARATIVE ACTION OF VARIOUS OESTROGENIC COMPOUNDS ON MOUSE VAGINAL SIALIC ACIDS (II)

1969 ◽  
Vol 62 (4) ◽  
pp. 663-670 ◽  
Author(s):  
Lars Carlborg
Keyword(s):  
Sialic Acid ◽  
Response Curve ◽  
Sialic Acids ◽  
Clear Cut ◽  
Suitable Parameter ◽  
Sufficient Degree ◽  
Comparative Action ◽  
Relative Potencies ◽  
Good Agreement

ABSTRACT Oestrogens administered in lower doses than necessary to induce full cornification of the mouse vagina induce mucification. It was shown previously that the degree of mucification could be estimated by quantitative determination of sialic acids. A suitable parameter for oestrogen assay was the measurement of vaginal sialic acid concentration which exhibited a clear cut dose response curve. Eleven assays of various oestrogens were performed with this method. Their estimated relative potencies were in good agreement with other routine oestrogen assays. A statistically sufficient degree of precision was found. The sensitivity was of the same order, or slightly higher, than the Allen-Doisy test.

An Automated Method for the Determination of Serum Calcium with Glyoxal Bis (2-Hydroxyanil)

1967 ◽  
Vol 13 (6) ◽  
pp. 515-520 ◽  
Author(s):  
Genevieve Farese ◽  
Janice L Schmidt ◽  
Milton Mager
Keyword(s):  
Serum Calcium ◽  
Automated Analysis ◽  
Automated Method ◽  
Good Agreement

Abstract A completely automated analysis is described for the determination of serum calcium with glyoxal bis (2-hydroxyanil) solution (GBHA). The method is simple and precise, and the data obtained are in good agreement with results obtained by the manual GBHA procedure.

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
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