Determination of Neutron Flux and Neutron Fluence from the Signal Current of a Self-Powered Rhodium Detector

1973 ◽  
Vol 18 (1) ◽  
pp. 25-28
Author(s):  
W. W. Hudritsch
Keyword(s):  
Neutron Flux ◽  
Neutron Fluence ◽  
Self Powered

Implantable self-powered detector for on-line determination of neutron flux in patients during NCT treatment

2004 ◽  
Vol 61 (5) ◽  
pp. 1033-1037 ◽  
Author(s):  
M.E Miller ◽  
L.E Mariani ◽  
M.L.Sztejnberg Gonçalves-Carralves ◽  
M Skumanic ◽  
S.I Thorp
Keyword(s):  
Neutron Flux ◽  
On Line ◽  
Self Powered

scholarly journals Determination of VVER-1000 Thermal Power Based on Background Signals of Self-Powered Neutron Detectors

2019 ◽  
pp. 25-33
Author(s):  
V. Borysenko ◽  
D. Budyk ◽  
V. Goranchuk
Keyword(s):  
Neutron Flux ◽  
Thermal Power ◽  
Weight Coefficient ◽  
Random Errors ◽  
Neutron Detectors ◽  
Fundamental Possibility ◽  
Determination Error ◽  
Self Powered ◽  
Technical And Economic Indicators

The value of the reactor thermal power (RTP) is used in the VVER-1000 control systems in most algorithms for generation of control, blocking and protection signals. Besides, the technical and economic indicators of the power unit are determined by this parameter. Plans to increase VVER‑1000 RTP to 101.5%, and later to 104-107% of the nominal require additional justification of the accuracy of the RTP determination. Therefore, the task of increasing the accuracy of RTP determination is important. The paper describes the ways to improve the accuracy of weighted mean thermal power (WMTP) determination by selecting the optimal weight coefficient (that subsequently is used for WMTP determination) of each of the methods of RTP determination, namely: by thermotechnical parameters of the primary and secondary sides by neutron flux in the in-core monitoring system (ICMS) and in the neutron flux control equipment (NFCE). Another possibility of increasing the accuracy of WMTP determination, namely by increasing the number of methods of RTP determination, is also considered in the paper. The analysis of changes in the background signals of self-powered neutron detectors (SPNDs) during the VVER-1000 fuel campaigns shows the fundamental possibility of using the total background signal as a separate and independent method for RTP determination. The paper presents the results of the calculation of RTP determination error taking into account the coefficients of the components of the total RTP determination error: systematic, dynamic and random errors, which must be determined during the commissioning phase. The results of reduction of the error of WMTP determination in case of application of the additional method of RTP determination based on background signals of the SPNDs are presented. Theoretically, possible minimum values of the WMTP determination error are given depending on the values of the error of the RTP determination by separate methods.

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

A new method for the determination of unknown neutron fluence for 14.0MeV

2006 ◽  
Vol 385-386 ◽  
pp. 1318-1320 ◽  
Author(s):  
Fariha Malik ◽  
Ehsan U. Khan ◽  
Imtinan Qureshi ◽  
Syed N. Husaini ◽  
Waqar Ahmad ◽  
...  
Keyword(s):  
Neutron Fluence ◽  
New Method

Effect of Additional Irradiation at Different Fluxes on RPV Embrittlement

2009 ◽  
Author(s):  
Kenji Dohi ◽  
Kenji Nishida ◽  
Akiyoshi Nomoto ◽  
Naoki Soneda ◽  
Hiroshi Matsuzawa ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Solute Atom ◽  
Volume Fraction ◽  
Neutron Fluence ◽  
Three Dimensional ◽  
Atom Probe ◽  
Atom Clusters ◽  
Neutron Fluences ◽  
The Difference ◽  
Test Reactor

The effect of the neutron flux at high fluence on the microstructural and hardness changes of a reactor pressure vessel (RPV) steel was investigated. An accelerated test reactor irradiation of a RPV material, previously irradiated in commercial reactors, was carried out at the lowest possible neutron fluxes in order to obtain neutron fluences up to approximately 1×1020 n/cm2 (E>1MeV). State-of-the-art experimental techniques such as three-dimensional atom probe were applied to carry out advanced quantitative characterization of defect features in the materials. Results for the same material irradiated in both high and low flux conditions are compared. For neutron fluences above 6×1019 n/cm2 (E>1MeV) the difference in the neutron fluence dependence of the increase in hardness is not seen for any neutron flux condition. The volume fraction of solute atom clusters increases linearly with neutron fluence, and the influence of neutron flux is not significant. The component elements and the chemical composition of the solute atom clusters formed by the irradiation do not change regardless of the neutron fluence and flux. The square root of the volume fraction of the solute atom clusters is a good correlation with the increase in hardness.

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