Self-oscillations in automatic reactor power regulator

1991 ◽  
Vol 71 (2) ◽  
pp. 615-621
Author(s):  
A. N. Aleksakov ◽  
E. V. Nikolaev ◽  
L. N. Podlazov
Keyword(s):  
Reactor Power ◽  
Power Regulator ◽  
Automatic Reactor

Performance of automatic reactor-power control system of the first atomic power plant with correction signals derived from in-reactor transducers

1980 ◽  
Vol 49 (1) ◽  
pp. 486-488
Author(s):  
P. T. Potapenko ◽  
V. N. Sarylov ◽  
F. F. Voskresenskii ◽  
V. G. Dunaev ◽  
A. P. Shulekin
Keyword(s):  
Control System ◽  
Power Plant ◽  
Power Control ◽  
Reactor Power ◽  
Atomic Power Plant ◽  
Power Control System ◽  
Automatic Reactor

Digital Systems for Reactor Control: Design, Experience of Operation

2008 ◽  
Author(s):  
Ievgenii S. Bakhmach ◽  
Alexander A. Siora ◽  
Volodymyr T. Bezsalyi ◽  
Mikhail A. Yastrebenetsky
Keyword(s):  
Reactor Power ◽  
Digital Systems ◽  
Reactor Control ◽  
Protection Systems ◽  
Different Types ◽  
Field Programmable ◽  
Program Diversity ◽  
Automatic Reactor ◽  
Safety Systems ◽  
Reactor Protection System

Conversion of traditional analog NPP I&C systems to digital systems is a common tendency for many countries. Digital systems for reactor control designed by «Radiy» Company (Kirovograd, Ukraine) are described below. FPGA (Field Programmable Gates Arrays) were used for implementation of control algorithms. An equivalence between FPGA-projects implementation and schemes of control technological algorithms permitted to simplify development and verification processes and decrease the number of development errors. The platform was used for implementation of different safety important systems: reactor protection systems, automatic reactor power control and limitation systems, rods control systems, control safety systems. The main peculiarity of the reactor protection system is different types of diversity (apparatus and program diversity due to different hardware and different languages in main and diverse divisions; functional diversity; difference of CASE-tools). These systems have been used at 10 units. Reliability measures of systems and their components were determined using operational statistical data. Possible uses for these systems: modernization of different types of existing reactors (not only WWER); as full system or as subsystems; not only for Ukraine, but for other countries; for reactors III+ and IV generations.

Operating experience with automatic reactor-power control system at Obninsk Atomic Power Plant employing signals from in-core self-powered detectors

1979 ◽  
Vol 47 (4) ◽  
pp. 820-823
Author(s):  
M. G. Mitel'man ◽  
N. D. Rozenblyum ◽  
V. B. Tregubov ◽  
Yu. M. Shpiposkikh ◽  
A. I. Shtyfurko
Keyword(s):  
Control System ◽  
Power Plant ◽  
Power Control ◽  
Operating Experience ◽  
Reactor Power ◽  
Atomic Power Plant ◽  
Power Control System ◽  
Automatic Reactor ◽  
Self Powered ◽  
Core Self

Automatic Reactor Power Control for a Pressurized Water Reactor

1993 ◽  
Vol 102 (2) ◽  
pp. 277-286 ◽  
Author(s):  
Jung-In Choi ◽  
Yung-Joon Hah ◽  
Un-Chul Lee
Keyword(s):  
Power Control ◽  
Reactor Power ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Automatic Reactor

scholarly journals Design and heat transfer optimization of a 1 kW free-piston stirling engine for space reactor power system

2021 ◽  
Author(s):  
Zhiwen Dai ◽  
Chenglong Wang ◽  
Dalin Zhang ◽  
Wenxi Tian ◽  
Suizheng Qiu ◽  
...  
Keyword(s):  
Heat Transfer ◽  
Power System ◽  
Reactor Power ◽  
Stirling Engine ◽  
Free Piston ◽  
Space Reactor ◽  
Heat Transfer Optimization ◽  
Free Piston Stirling Engine

scholarly journals Reactor rate modulation oscillation analysis with two detectors in Double Chooz

2021 ◽  
Vol 2021 (1) ◽  
Author(s):  
T. Abrahão ◽  
◽  
H. Almazan ◽  
J. C. dos Anjos ◽  
S. Appel ◽  
...  
Keyword(s):  
Reactor Power ◽  
Background Model ◽  
Fast Neutrons ◽  
Mixing Angle ◽  
Oscillation Analysis ◽  
Central Value ◽  
Double Chooz ◽  
Model Independent ◽  
Best Fit

Abstract A θ13 oscillation analysis based on the observed antineutrino rates at the Double Chooz far and near detectors for different reactor power conditions is presented. This approach provides a so far unique simultaneous determination of θ13 and the total background rates without relying on any assumptions on the specific background contributions. The analysis comprises 865 days of data collected in both detectors with at least one reactor in operation. The oscillation results are enhanced by the use of 24.06 days (12.74 days) of reactor-off data in the far (near) detector. The analysis considers the $$ {\overline{\nu}}_e $$ ν ¯ e interactions up to a visible energy of 8.5 MeV, using the events at higher energies to build a cosmogenic background model considering fast-neutrons interactions and 9Li decays. The background-model-independent determination of the mixing angle yields sin2(2θ13) = 0.094 ± 0.017, being the best-fit total background rates fully consistent with the cosmogenic background model. A second oscillation analysis is also performed constraining the total background rates to the cosmogenic background estimates. While the central value is not significantly modified due to the consistency between the reactor-off data and the background estimates, the addition of the background model reduces the uncertainty on θ13 to 0.015. Along with the oscillation results, the normalization of the anti-neutrino rate is measured with a precision of 0.86%, reducing the 1.43% uncertainty associated to the expectation.

Physical simulation of nuclear reactor power plant systems

1958 ◽  
Author(s):  
J. J. Stone ◽  
B. B. Gordon ◽  
R. S. Boyd
Keyword(s):  
Power Plant ◽  
Nuclear Reactor ◽  
Physical Simulation ◽  
Reactor Power ◽  
Reactor Power Plant
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