FIELD: monitoring neutron flux to check up, control, and protect tank reactors.
SUBSTANCE: proposed nuclear reactor neutron flux monitoring system has neutron flux sensors as well as input signal processing and protection signal generating device. Neutron flux sensors are disposed along vertical axis beyond reactor vessel. There are three neutron flux sensors. One of them is installed in center of reactor core height and two other ones, above and below core center. Input signal processing and protection signal generation device is made in the for of a number of modules. First module functions to evaluate axial offset, variation factor of axial energy distribution mean for reactor core, and reactor thermal capacity corrected including correction factors. First module is coupled with three neutron flux sensors and with following reactor process inspection sensors: control element position sensors and coolant temperature sensors at inlet of rector circulation loops. Second module functions to evaluate reactor thermal capacity corrected including desired limitation of correction factor and generation of signals initiating protection responses to enhancement of mentioned capacity admissible value. Second module is coupled with first output of first module and also directly with top and bottom neutron-flux sensors. Third module functions to evaluate margin to maximal admissible linear energy release, margin to burnout, and to generate signals initiating protective properties upon attaining mentioned maximal admissible margins. Third module is coupled with second output of first module as well as with following sensors of reactor process inspection systems: reactor pressure sensors, flow sensors of coolant discharge through core. Second and third modules are coupled with reactor control and protection system.
EFFECT: enhanced reliability of rector protective gear.
4 cl, 2 dwg
Title | Year | Author | Number |
---|---|---|---|
METHOD FOR CORRECTING THE ERROR OF THE READINGS OF THE POWER OF A NUCLEAR REACTOR | 2021 |
|
RU2771891C1 |
METHOD OF OPERATING NUCLEAR REACTOR WITH ON-LINE CALCULATION OF SAFETY FACTOR BEFORE HEAT EXCHANGE CRISIS | 2019 |
|
RU2808104C2 |
PROTECTION METHOD OF REACTOR CORE OF WATER-COOLED POWER REACTOR AS PER LOCAL PARAMETERS USING READINGS OF IN-CORE NEUTRON DETECTORS | 2010 |
|
RU2438198C1 |
METHOD FOR CONTROLLING AND PROTECTING A FAST NEUTRON NUCLEAR REACTOR AND A SYSTEM FOR ITS IMPLEMENTATION | 2022 |
|
RU2798480C1 |
NUCLEAR REACTOR CONTROL PROCESS | 2000 |
|
RU2190267C2 |
OPERATING PROCESS FOR LIGHT-WATER TANK REACTOR | 1992 |
|
RU2046406C1 |
METHOD OF CONTROLLING NUCLEAR POWER PLANT WITH PRESSURISED WATER REACTOR WITH VARIATION OF REACTOR POWER OR EXTERNAL LOAD | 2011 |
|
RU2470391C1 |
METHOD OF CONTROLLING NUCLEAR REACTOR | 2011 |
|
RU2470392C1 |
SPACE NUCLEAR DUAL-MODE POWER PLANT OF TRANSPORT-POWER MODULE | 2014 |
|
RU2592069C2 |
METHOD FOR REDUCING NONUNIFORMITY OF THERMAL RESOURCES DISTRIBUTION IN FUEL ASSEMBLIES OF NUCLEAR REACTOR CORE (ALTERNATIVES) | 2001 |
|
RU2219600C2 |
Authors
Dates
2007-11-10—Published
2006-02-28—Filed