11 research outputs found
ΠΡΡΠ»Π΅Π΄ΠΎΠ²Π°Π½ΠΈΠ΅ ΠΏΠ°ΡΠ°ΠΌΠ΅ΡΡΠΈΡΠ΅ΡΠΊΠΈΡ Π²Π·Π°ΠΈΠΌΠΎΠ΄Π΅ΠΉΡΡΠ²ΠΈΠΉ ΠΏΡΠΈ ΡΠ΅Π³ΡΠ»ΠΈΡΠΎΠ²Π°Π½ΠΈΠΈ ΡΠ΄Π΅ΡΠ½ΠΎΠ³ΠΎ ΡΠ΅Π°ΠΊΡΠΎΡΠ° Ρ ΠΎΠ±ΡΠ°ΡΠ½ΠΎΠΉ ΡΠ²ΡΠ·ΡΡ
This article considers the principal theoretical possibility of regulating a nuclear power reactor under changing operating modes conditions when external periodic disturbances take place in conditions of changing the operating mode. By the external periodic perturbation a downward change in the conditions of the heat sink was meant. The magnitude of the changes was preliminarily calculated in such a way that the operating conditions of the power plant did not exceed the boundaries of the safe operation zone of the reactor. In the case of approaching the operation parameters to the critical ones, the heat sink was increased until the working conditions returned to their previous state. In this work the amplitude frequency response of a non-linearly enhanced system in the nuclear power plant operating conditions when non-linearly reacting to external periodic influences has been studied. The external cyclic disturbances effect produced on the reactor that initially existed under stationary operating conditions has been considered. The research was carried out by numerical simulation of the competition between processes occurring in a nuclear power plant and determined by the systemβs reaction time and relaxation time while responding to periodic external influences. Calculations of the relaxation time dependence on the fixed frequency-revealing external influenceβs temperature are presented. Also, the relaxation time dependence on the frequency of external influence at a fixed temperature for systems with various relaxation periods was calculated. It is determined that when the dependence between system temperature and the external influence time is calculated, there exists a wide range of possible frequency control. To evaluate the behavior of a nuclear power reactor under conditions of operating modes changes, a fundamental physical mathematical model of the reactorβs state under external harmonic influence is presented. It is based on the nonlinear Riccati equation. The external harmonic effect was simulated by changing the heat supply and heat removal conditions near the critical point.Π Π°ΡΡΠΌΠΎΡΡΠ΅Π½Π° ΠΏΡΠΈΠ½ΡΠΈΠΏΠΈΠ°Π»ΡΠ½Π°Ρ ΡΠ΅ΠΎΡΠ΅ΡΠΈΡΠ΅ΡΠΊΠ°Ρ Π²ΠΎΠ·ΠΌΠΎΠΆΠ½ΠΎΡΡΡ ΡΠ΅Π³ΡΠ»ΠΈΡΠΎΠ²Π°Π½ΠΈΡ ΡΠ΄Π΅ΡΠ½ΠΎΠ³ΠΎ ΡΠ½Π΅ΡΠ³Π΅ΡΠΈΡΠ΅ΡΠΊΠΎΠ³ΠΎ ΡΠ΅Π°ΠΊΡΠΎΡΠ°, Π½Π°Ρ
ΠΎΠ΄ΡΡΠ΅Π³ΠΎΡΡ ΠΏΠΎΠ΄ Π²ΠΎΠ·Π΄Π΅ΠΉΡΡΠ²ΠΈΠ΅ΠΌ Π²Π½Π΅ΡΠ½ΠΈΡ
ΠΏΠ΅ΡΠΈΠΎΠ΄ΠΈΡΠ΅ΡΠΊΠΈΡ
Π²ΠΎΠ·ΠΌΡΡΠ΅Π½ΠΈΠΉ, Π² ΡΡΠ»ΠΎΠ²ΠΈΡΡ
ΠΈΠ·ΠΌΠ΅Π½Π΅Π½ΠΈΡ ΡΠ΅ΠΆΠΈΠΌΠΎΠ² ΡΠ°Π±ΠΎΡΡ. ΠΠΎΠ΄ Π²Π½Π΅ΡΠ½ΠΈΠΌ ΠΏΠ΅ΡΠΈΠΎΠ΄ΠΈΡΠ΅ΡΠΊΠΈΠΌ Π²ΠΎΠ·ΠΌΡΡΠ΅Π½ΠΈΠ΅ΠΌ ΠΏΠΎΠ΄ΡΠ°Π·ΡΠΌΠ΅Π²Π°Π»ΠΎΡΡ ΠΈΠ·ΠΌΠ΅Π½Π΅Π½ΠΈΠ΅ ΡΡΠ»ΠΎΠ²ΠΈΠΉ ΡΠ΅ΠΏΠ»ΠΎΠΎΡΠ²ΠΎΠ΄Π° Π² ΡΡΠΎΡΠΎΠ½Ρ ΡΠΌΠ΅Π½ΡΡΠ΅Π½ΠΈΡ. ΠΠ΅Π»ΠΈΡΠΈΠ½Π° ΠΈΠ·ΠΌΠ΅Π½Π΅Π½ΠΈΠΉ ΠΏΡΠ΅Π΄Π²Π°ΡΠΈΡΠ΅Π»ΡΠ½ΠΎ ΡΠ°ΡcΡΠΈΡΡΠ²Π°Π»Π°ΡΡ ΡΠ°ΠΊΠΈΠΌ ΠΎΠ±ΡΠ°Π·ΠΎΠΌ, ΡΡΠΎΠ±Ρ ΡΡΠ»ΠΎΠ²ΠΈΡ ΡΠ°Π±ΠΎΡΡ ΡΠ½Π΅ΡΠ³Π΅ΡΠΈΡΠ΅ΡΠΊΠΎΠΉ ΡΡΡΠ°Π½ΠΎΠ²ΠΊΠΈ Π½Π΅ Π²ΡΡ
ΠΎΠ΄ΠΈΠ»ΠΈ Π·Π° Π³ΡΠ°Π½ΠΈΡΡ Π·ΠΎΠ½Ρ Π±Π΅Π·ΠΎΠΏΠ°ΡΠ½ΠΎΠΉ ΡΠ°Π±ΠΎΡΡ ΡΠ΅Π°ΠΊΡΠΎΡΠ°. Π ΡΠ»ΡΡΠ°Π΅ ΠΏΡΠΈΠ±Π»ΠΈΠΆΠ΅Π½ΠΈΡ ΠΏΠ°ΡΠ°ΠΌΠ΅ΡΡΠΎΠ² ΡΠ°Π±ΠΎΡΡ ΠΊ ΠΊΡΠΈΡΠΈΡΠ΅ΡΠΊΠΈΠΌ ΡΠ΅ΠΏΠ»ΠΎΠΎΡΠ²ΠΎΠ΄ ΡΠ²Π΅Π»ΠΈΡΠΈΠ²Π°Π»ΡΡ Π΄ΠΎ ΠΌΠΎΠΌΠ΅Π½ΡΠ° Π²ΠΎΠ·Π²ΡΠ°ΡΠ΅Π½ΠΈΡ ΡΡΠ»ΠΎΠ²ΠΈΠΉ ΡΠ°Π±ΠΎΡΡ Π² ΠΏΡΠ΅ΠΆΠ½Π΅Π΅ ΡΠΎΡΡΠΎΡΠ½ΠΈΠ΅. ΠΠ·ΡΡΠ΅Π½ Π°ΠΌΠΏΠ»ΠΈΡΡΠ΄Π½ΡΠΉ ΡΠ°ΡΡΠΎΡΠ½ΡΠΉ ΠΎΡΠΊΠ»ΠΈΠΊ Π½Π΅Π»ΠΈΠ½Π΅ΠΉΠ½ΠΎ ΠΎΠ±ΠΎΡΡΡΠ΅Π½Π½ΠΎΠΉ ΡΠΈΡΡΠ΅ΠΌΡ Π² ΡΡΠ»ΠΎΠ²ΠΈΡΡ
ΡΠ°Π±ΠΎΡΡ ΡΠ΄Π΅ΡΠ½ΠΎΠΉ ΡΠ½Π΅ΡΠ³Π΅ΡΠΈΡΠ΅ΡΠΊΠΎΠΉ ΡΡΡΠ°Π½ΠΎΠ²ΠΊΠΈ, Π½Π΅Π»ΠΈΠ½Π΅ΠΉΠ½ΠΎ ΡΠ΅Π°Π³ΠΈΡΡΡΡΠ΅ΠΉ Π½Π° Π²Π½Π΅ΡΠ½ΠΈΠ΅ ΠΏΠ΅ΡΠΈΠΎΠ΄ΠΈΡΠ΅ΡΠΊΠΈΠ΅ Π²ΠΎΠ·Π΄Π΅ΠΉΡΡΠ²ΠΈΡ. Π Π°ΡΡΠΌΠΎΡΡΠ΅Π½ΠΎ Π²ΠΎΠ·Π΄Π΅ΠΉΡΡΠ²ΠΈΠ΅ Π²Π½Π΅ΡΠ½ΠΈΡ
ΡΠΈΠΊΠ»ΠΈΡΠ΅ΡΠΊΠΈΡ
Π²ΠΎΠ·ΠΌΡΡΠ΅Π½ΠΈΠΉ Π½Π° ΡΠ΅Π°ΠΊΡΠΎΡ, ΠΈΡΡ
ΠΎΠ΄Π½ΠΎ Π½Π°Ρ
ΠΎΠ΄ΡΡΠΈΠΉΡΡ Π² ΡΡΠ°ΡΠΈΠΎΠ½Π°ΡΠ½ΠΎΠΌ ΡΠ°Π±ΠΎΡΠ΅ΠΌ ΡΠΎΡΡΠΎΡΠ½ΠΈΠΈ. ΠΡΠΎΠ²Π΅Π΄Π΅Π½Ρ ΠΈΡΡΠ»Π΅Π΄ΠΎΠ²Π°Π½ΠΈΡ ΠΏΡΡΠ΅ΠΌ ΡΠΈΡΠ»Π΅Π½Π½ΠΎΠ³ΠΎ ΠΌΠΎΠ΄Π΅Π»ΠΈΡΠΎΠ²Π°Π½ΠΈΡ ΠΊΠΎΠ½ΠΊΡΡΠ΅Π½ΡΠΈΠΈ ΠΏΡΠΎΡΠ΅ΡΡΠΎΠ², ΠΏΡΠΎΡΠ΅ΠΊΠ°ΡΡΠΈΡ
Π² ΡΠ΄Π΅ΡΠ½ΠΎΠΉ ΡΠ½Π΅ΡΠ³Π΅ΡΠΈΡΠ΅ΡΠΊΠΎΠΉ ΡΡΡΠ°Π½ΠΎΠ²ΠΊΠ΅, ΠΊΠΎΡΠΎΡΡΠ΅ ΠΎΠΏΡΠ΅Π΄Π΅Π»ΡΡΡΡΡ Π²ΡΠ΅ΠΌΠ΅Π½Π΅ΠΌ ΡΠ΅Π°ΠΊΡΠΈΠΈ ΠΈ Π²ΡΠ΅ΠΌΠ΅Π½Π΅ΠΌ ΡΠ΅Π»Π°ΠΊΡΠ°ΡΠΈΠΈ ΡΠΈΡΡΠ΅ΠΌΡ Π½Π° ΠΏΠ΅ΡΠΈΠΎΠ΄ΠΈΡΠ΅ΡΠΊΠΎΠ΅ Π²Π½Π΅ΡΠ½Π΅Π΅ Π²ΠΎΠ·Π΄Π΅ΠΉΡΡΠ²ΠΈΠ΅. ΠΡΠ΅Π΄ΡΡΠ°Π²Π»Π΅Π½Ρ ΡΠ°ΡΡΠ΅ΡΡ Π·Π°Π²ΠΈΡΠΈΠΌΠΎΡΡΠΈ Π²ΡΠ΅ΠΌΠ΅Π½ΠΈ ΡΠ΅Π»Π°ΠΊΡΠ°ΡΠΈΠΈ ΠΎΡ ΡΠ΅ΠΌΠΏΠ΅ΡΠ°ΡΡΡΡ Π²Π½Π΅ΡΠ½Π΅Π³ΠΎ Π²ΠΎΠ·Π΄Π΅ΠΉΡΡΠ²ΠΈΡ ΠΏΡΠΈ ΡΠΈΠΊΡΠΈΡΠΎΠ²Π°Π½Π½ΠΎΠΉ ΡΠ°ΡΡΠΎΡΠ΅, Π²ΡΠ΅ΠΌΠ΅Π½ΠΈ ΡΠ΅Π»Π°ΠΊΡΠ°ΡΠΈΠΈ ΠΎΡ ΡΠ°ΡΡΠΎΡΡ Π²Π½Π΅ΡΠ½Π΅Π³ΠΎ Π²ΠΎΠ·Π΄Π΅ΠΉΡΡΠ²ΠΈΡ ΠΏΡΠΈ ΡΠΈΠΊΡΠΈΡΠΎΠ²Π°Π½Π½ΠΎΠΉ ΡΠ΅ΠΌΠΏΠ΅ΡΠ°ΡΡΡΠ΅ Π΄Π»Ρ ΡΠΈΡΡΠ΅ΠΌ Ρ ΡΠ°Π·Π½ΡΠΌ Π²ΡΠ΅ΠΌΠ΅Π½Π΅ΠΌ ΡΠ΅Π»Π°ΠΊΡΠ°ΡΠΈΠΈ. ΠΠΏΡΠ΅Π΄Π΅Π»Π΅Π½ΠΎ, ΡΡΠΎ ΠΏΡΠΈ ΡΠ°ΡΡΠ΅ΡΠ΅ Π·Π°Π²ΠΈΡΠΈΠΌΠΎΡΡΠΈ ΡΠ΅ΠΌΠΏΠ΅ΡΠ°ΡΡΡΡ ΡΠΈΡΡΠ΅ΠΌΡ ΠΎΡ Π²ΡΠ΅ΠΌΠ΅Π½ΠΈ Π²Π½Π΅ΡΠ½Π΅Π³ΠΎ Π²ΠΎΠ·Π΄Π΅ΠΉΡΡΠ²ΠΈΡ ΡΡΡΠ΅ΡΡΠ²ΡΠ΅Ρ ΡΠΈΡΠΎΠΊΠ°Ρ Π·ΠΎΠ½Π° Π²ΠΎΠ·ΠΌΠΎΠΆΠ½ΠΎΠ³ΠΎ ΡΠ°ΡΡΠΎΡΠ½ΠΎΠ³ΠΎ ΡΠ΅Π³ΡΠ»ΠΈΡΠΎΠ²Π°Π½ΠΈΡ. ΠΠ»Ρ ΠΎΡΠ΅Π½ΠΊΠΈ ΠΏΠΎΠ²Π΅Π΄Π΅Π½ΠΈΡ ΡΠ΄Π΅ΡΠ½ΠΎΠ³ΠΎ ΡΠ½Π΅ΡΠ³Π΅ΡΠΈΡΠ΅ΡΠΊΠΎΠ³ΠΎ ΡΠ΅Π°ΠΊΡΠΎΡΠ° Π² ΡΡΠ»ΠΎΠ²ΠΈΡΡ
ΠΈΠ·ΠΌΠ΅Π½Π΅Π½ΠΈΡ ΡΠ΅ΠΆΠΈΠΌΠΎΠ² ΡΠ°Π±ΠΎΡΡ ΡΠΎΠ·Π΄Π°Π½Π° ΠΏΡΠΈΠ½ΡΠΈΠΏΠΈΠ°Π»ΡΠ½Π°Ρ ΡΠΈΠ·ΠΈΠΊΠΎ-ΠΌΠ°ΡΠ΅ΠΌΠ°ΡΠΈΡΠ΅ΡΠΊΠ°Ρ ΠΌΠΎΠ΄Π΅Π»Ρ ΡΠΎΡΡΠΎΡΠ½ΠΈΡ ΡΠ΅Π°ΠΊΡΠΎΡΠ°, Π½Π°Ρ
ΠΎΠ΄ΡΡΠ΅Π³ΠΎΡΡ ΠΏΠΎΠ΄ Π²Π½Π΅ΡΠ½ΠΈΠΌ Π³Π°ΡΠΌΠΎΠ½ΠΈΡΠ΅ΡΠΊΠΈΠΌ Π²ΠΎΠ·Π΄Π΅ΠΉΡΡΠ²ΠΈΠ΅ΠΌ, Π½Π° ΠΎΡΠ½ΠΎΠ²Π΅ Π½Π΅Π»ΠΈΠ½Π΅ΠΉΠ½ΠΎΠ³ΠΎ ΡΡΠ°Π²Π½Π΅Π½ΠΈΡ Π ΠΈΠΊΠΊΠ°ΡΠΈ. ΠΠ½Π΅ΡΠ½Π΅Π΅ Π³Π°ΡΠΌΠΎΠ½ΠΈΡΠ΅ΡΠΊΠΎΠ΅ Π²ΠΎΠ·Π΄Π΅ΠΉΡΡΠ²ΠΈΠ΅ ΠΌΠΎΠ΄Π΅Π»ΠΈΡΠΎΠ²Π°Π»ΠΎΡΡ ΠΏΡΡΠ΅ΠΌ ΠΈΠ·ΠΌΠ΅Π½Π΅Π½ΠΈΡ ΡΡΠ»ΠΎΠ²ΠΈΠΉ ΡΠ΅ΠΏΠ»ΠΎΠΏΠΎΠ΄Π²ΠΎΠ΄Π° ΠΈ ΡΠ΅ΠΏΠ»ΠΎΠΎΡΠ²ΠΎΠ΄Π° Π²Π±Π»ΠΈΠ·ΠΈ ΠΊΡΠΈΡΠΈΡΠ΅ΡΠΊΠΎΠΉ ΡΠΎΡΠΊΠΈ
ΠΡΡΠ»Π΅Π΄ΠΎΠ²Π°Π½ΠΈΠ΅ ΠΏΠ°ΡΠ°ΠΌΠ΅ΡΡΠΈΡΠ΅ΡΠΊΠΈΡ Π²Π·Π°ΠΈΠΌΠΎΠ΄Π΅ΠΉΡΡΠ²ΠΈΠΉ ΠΏΡΠΈ ΡΠ΅Π³ΡΠ»ΠΈΡΠΎΠ²Π°Π½ΠΈΠΈ ΡΠ΄Π΅ΡΠ½ΠΎΠ³ΠΎ ΡΠ΅Π°ΠΊΡΠΎΡΠ° Ρ ΠΎΠ±ΡΠ°ΡΠ½ΠΎΠΉ ΡΠ²ΡΠ·ΡΡ
This article considers the principal theoretical possibility of regulating a nuclear power reactor under changing operating modes conditions when external periodic disturbances take place in conditions of changing the operating mode. By the external periodic perturbation a downward change in the conditions of the heat sink was meant. The magnitude of the changes was preliminarily calculated in such a way that the operating conditions of the power plant did not exceed the boundaries of the safe operation zone of the reactor. In the case of approaching the operation parameters to the critical ones, the heat sink was increased until the working conditions returned to their previous state. In this work the amplitude frequency response of a non-linearly enhanced system in the nuclear power plant operating conditions when non-linearly reacting to external periodic influences has been studied. The external cyclic disturbances effect produced on the reactor that initially existed under stationary operating conditions has been considered. The research was carried out by numerical simulation of the competition between processes occurring in a nuclear power plant and determined by the systemβs reaction time and relaxation time while responding to periodic external influences. Calculations of the relaxation time dependence on the fixed frequency-revealing external influenceβs temperature are presented. Also, the relaxation time dependence on the frequency of external influence at a fixed temperature for systems with various relaxation periods was calculated. It is determined that when the dependence between system temperature and the external influence time is calculated, there exists a wide range of possible frequency control. To evaluate the behavior of a nuclear power reactor under conditions of operating modes changes, a fundamental physical mathematical model of the reactorβs state under external harmonic influence is presented. It is based on the nonlinear Riccati equation. The external harmonic effect was simulated by changing the heat supply and heat removal conditions near the critical point
Dimensioness method of assessing the conditions of thermal shock to the reactor vessel
During the prolongation of the terms of the nuclear power plants operation the main issue is the substantiation of the possibility of the terms of the reactor vessel operation, which determines the economic necessity to con-tinue operating the unit as a whole. Significant effect on the residual life of the reactor pressure vessel is to com-mit thermal loads, including thermal shock in case of the accident with leaky reactor circuit. The dimensionless method is developed concerning the rating conditions of the thermal shock to reactor vessels. Moreover, the at-tention is focused not on the known correlation approaches, but on the additional criteria, related to the com-pleteness of the heat transfer and terms strength of metal under thermal loading. Proposed methods can be the basic for the rapid diagnosis of the conditions of thermal shock to reactor in the accidents with leaky reactor cir-cuit