CN105551551B - A kind of pool type natrium cold fast reactor low power run method that conventional island input is not required - Google Patents
A kind of pool type natrium cold fast reactor low power run method that conventional island input is not required Download PDFInfo
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Abstract
The invention belongs to pool type natrium cold fast reactor designing technique, and in particular to a kind of pool type natrium cold fast reactor low power run method that conventional island input is not required.This method determines total one, the proper heat reduction amount of the major-minor system of secondary circuit in the case where not putting into three circuits, thereby determine that under equilibrium state can longtime running peak power.In addition, sodium total amount is loaded according to one, secondary circuit, according to initial starting temperature, you can determine under conditions of maximum temperature limit value, the highest and its relation of corresponding time that reactor can be run.Therefore, in addition in physics thermodynamic metering, to the related setting valve of control protection, equally accordingly changed, meet the requirement of safety allowance.The present invention improves the economy, reliability and flexibility of reactor on the premise of security allowance is ensured, and can fully effectively improve the utilization ratio of experimental reactor, improves the level of corresponding scientific research activity.
Description
Technical field
The invention belongs to pool type natrium cold fast reactor designing technique, and in particular to a kind of pool type natrium cold that conventional island input is not required
Fast reactor low power run method.
Background technology
During pool type natrium cold fast reactor normal operation, the heat that reactor core produces is under normal circumstances by main heat-transfer system
(being made of primary Ioops, secondary circuit, three circuits) exports, and converts heat into electric energy by Turbo-generator Set.Wherein three times
Road, conventional island is all located at comprising steam turbine and generator etc..China Experiment Fast Reactor (CEFR) is used as research reactor, exists in many cases
Run under low-power and carry out experiment, the equipment such as steam turbine is not reaching to service condition at this time.Since conventional island equipment is more, operation
It is cumbersome, have the characteristics that Meteorological is high, time is long, the situation of experiment demand can be met in face of low-power, there is an urgent need for one
Kind can be under middle low power condition, the scheme that does not put into conventional island system equipment and run, to improve economy and flexibility.
Conventional island is up the downstream links of main heat-transfer system.Without using during conventional island, it is necessary to consider these heat
Amount is discharged by other approach, and determines that the parameters such as reactor temperature are no more than corresponding limit value.
The content of the invention
The purpose of the present invention is under conditions of meeting the premise of nuclear safety and not reducing safety allowance, there is provided one kind is not
The pool type natrium cold fast reactor low power run method for needing conventional island to put into, properly increases economy and reliability.
Technical scheme is as follows：A kind of pool type natrium cold fast reactor low power run side that conventional island input is not required
Method, includes the following steps：
(1) heat removal capacity of reactor other systems in addition to main heat-transfer system is determined, including：
(1-1) is net according to the flow and cold-trap of primary Ioops coolant cleanup system inlet and outlet differential thermal calculation primary Ioops cooling agent
The heat exhaust of change system；
(1-2) imports and exports differential thermal calculation accident afterheat discharge system according to accident afterheat discharge system flow and air cooler
Heat removal capacity；
(1-3) is according to reactor pit ventilating system air quantity and the heat extraction of protection container outer surface temperature computation reactor pit ventilating system
Amount；
(1-4) is according to intermediate heat exchanger secondary side sodium entrance temperature difference, the heat exhaust of the calculating major-minor system of secondary circuit；
(2) temperature rise limitation is calculated according to reactor one, secondary circuit cooling agent thermal capacitance, including：
(2-1) determines one, secondary circuit cooling agent initial temperature；
(2-2) determines overall temperature rise rate according to nuclear heating；
(3) in the case that conventional island is not put into, reactor low power run, it is specified that reactor hoisting power is not more than 1%
Power, side entrance sodium temperature of monitoring intermediate heat exchanger are no more than 365 DEG C, maintain this section different IPs power step operation；
(4) according to step (1), the result of calculation of (2), and the result of the test of step (3), to the phase of Control protection system
Close setting valve to modify, to meet the requirement of safety allowance.
Further, the pool type natrium cold fast reactor low power run method of conventional island input, step (1- are not required as described above
1) in, the heat exhaust formula for calculating primary Ioops coolant cleanup system is as follows：
Q1=G1(Hi-Ho)
Wherein：
Q1For primary Ioops cooling agent (sodium) cleaning system heat exhaust；
G1For flow；
HiFor sodium entrance enthalpy；
HoEnthalpy is returned for sodium.
Further, the pool type natrium cold fast reactor low power run method of conventional island input, step (1- are not required as described above
2) in, the heat removal capacity computation model of accident afterheat discharge system is as follows：
Heat transfer model in accident afterheat removal system intermediate loop pipeline：
Wherein：
τ-time, s；
tNa- coolant temperature, DEG C；
tSMean temperature in-cooling agent tube wall around, DEG C；
tB0- tube wall ambient air temperature, DEG C；
Z- along coolant flow to coordinate, m；
uNa- coolant flow speed, m/s；
VNaCoolant volume in-unit length pipeline, m3；
VSThe volume of cooling agent tube wall around in-unit length pipeline, m3；
K3- the heat transfer coefficient from cooling agent to tube wall, W/m2·℃；
K4- the heat transfer coefficient from tube wall to surrounding air, W/m2·℃；
F3Heat exchange area on-unit length pipeline between cooling agent and tube wall, m2；
F4Heat exchange area between-unit length pipeline upper tube wall and surrounding air, m2；
CNa- coolant volume thermal capacitance, J/m3·℃；
CSThe average effective volumetric heat capacity of all tube walls around-cooling agent, J/m3·℃；
The heat transfer model of aerial cooler：
Wherein：
tNaCoolant temperature in-air heat exchanger bundle, DEG C；
tBAir themperature in-air heat exchanger, DEG C；
tSThe temperature of-air heat exchanger bundle metal, DEG C；
tSKThe temperature of-air heat exchanger the container acted in view of insulating layer, DEG C；
tB0- tube wall ambient air temperature, DEG C；
Z- is along the coordinate on air heat exchanger bundle length direction, m；
Z*- along the coordinate between air heat exchanger bundle on space length direction, m；
UNaSodium flowing velocity, m/s in-air heat exchanger bundle；
UBSpeed air flow in-air heat exchanger, m/s；
K1- the heat transfer coefficient between sodium and air heat exchanger bundle, W/m2·℃；
K2- tube bank and the heat transfer coefficient of interbank air, W/m2·℃；
K3Heat transfer coefficient between-air heat exchanger bundle between air and air heat exchanger container, W/m2·℃；
K4Heat transfer (considering heat insulation layer) coefficient between-air heat exchanger container and surrounding air, W/m2·℃；
F1Heat exchange area in-unit length between sodium and air heat exchanger bundle, m2；
F2The heat exchange area of air heat exchanger pipeline and interbank air in-unit length, m2；
F3Heat exchange area in-unit length between the interbank air of air heat exchanger and air heat exchanger container, m2；
F4Heat exchange area in-unit length between air heat exchanger container and surrounding air, m2；
CSThe effective volume thermal capacitance of-air heat exchanger bundle, J/m3·℃；
CB- volume of air thermal capacitance, J/m3·℃；
CSK- consider air heat exchanger bundle air heat exchanger container average effective volumetric heat capacity, J/m3·
℃；
CNa- coolant volume thermal capacitance, J/m3·℃；
VNaCoolant volume in-unit length in air heat exchanger bundle, m3；
VSThe volume of air heat exchanger bundle, m in-unit length3；
VBVolume of air between-air heat exchanger bundle in space in unit length, m3；
VSK- consider air heat exchanger volume of a container in the air heat exchanger container unit length of insulating layer,
m3；
The fluid mechanic model of accident afterheat removal system intermediate loop：
Wherein：
τ-time, s；
- descriptionThe vector of circuit units, m；
dPL(τ)-unitOn drive ram, Pa；
dξL(τ)-unitOn Flow Resistant Coefficient, relative unit；
ρL(τ)-unitOn coolant density, kg/m3；
- unitOn coolant velocity, m/s；
- acceleration of gravity, m/s2；
Accident afterheat removal system air flow channel heat exchange models：
Wherein：
τ-time, s；
tBAir themperature in-air flow channel, DEG C；
tS- consider insulating layer and concrete structure air flow channel temperature, DEG C；
tBoThe temperature of-air flow channel surrounding air, DEG C；
uBThe air velocity of-air pipeline, m/s；
K3Heat transfer coefficient in-air pipeline between air and tube wall, W/m2·℃；
K4- the heat transfer coefficient between air pipeline and surrounding air, W/m2·℃；
F3Heat exchange area in-air pipeline unit length between air and pipeline, m2；
F4Heat exchange area in-air pipeline unit length between pipeline and surrounding air, m2；
CB- volume of air thermal capacitance, J/m3·℃；
CSThe average effective volumetric heat capacity of all tube layer of-air pipeline, J/m3·℃；
VBVolume of air in-air pipeline unit length, m3；
VSThe volume of air duct structure in-air pipeline unit length, m3；
Accident afterheat removal system air flow channel fluid mechanic model：
Wherein
τ-time, s；
- descriptionThe vector of circuit units, m；
ΔPwind- the gas differential pressure formed on air flow channel population and outlet, Pa；
ΔPwPressure difference on (N, δ)-air heat exchanger export the breeze door, Pa；
The quantity of blade on N- air heat exchanger export the breeze doors, it is a；
The corner of blade on δ-air heat exchanger export the breeze door, degree；
dξL(τ)-air flow channel unitOn Flow Resistant Coefficient, relative unit；
ρL- air flow channel unitOn coolant density, kg/m3；
The unit of-air flow channelOn coolant velocity, m/s；
- acceleration of gravity, m/s2。
Q2=Q21+Q22
Q21=G21(H21i-H21o)
Q21=G22(H22i-H22o)
Wherein：
Q2For accident afterheat removal system heat exhaust；
Q21For accident afterheat removal system I loop heat exhausts；
Q22For accident afterheat removal system II loop heat exhausts；
G21For accident afterheat removal system I loop traffics；
G22For accident afterheat removal system II loop traffics；
H21iFor accident afterheat removal system I loop independent heat exchanger outlet temperatures；
H21oFor accident afterheat removal system I loop independent heat exchanger inlet temperatures；
H22iFor accident afterheat removal system II loop independent heat exchanger outlet temperatures；
H22oFor accident afterheat removal system II loop independent heat exchanger inlet temperatures.
Further, the pool type natrium cold fast reactor low power run method of conventional island input, step (1- are not required as described above
3) in, the calculation formula of the heat exhaust of reactor pit ventilating system is as follows：
Q3=G3(H3o-H3i)
Wherein：
Q3For reactor pit ventilating system heat exhaust；
G3Pass through the ventilation quantity of reactor pit for reactor pit ventilating system；
H3iFor reactor pit ventilating system intake air enthalpy；
H3oFor reactor pit outlet of ventilating system air enthalpy.
Further, the pool type natrium cold fast reactor low power run method of conventional island input, step (1- are not required as described above
4) in, the heat exhaust calculation formula of the major-minor system of secondary circuit is as follows：
Q4=Q41+Q42
Q41=G41(H41o-H41i)
Q42=G42(H42o-H42i)
Wherein：
Q4For the total heat exhaust of the major-minor system of secondary circuit；
Q41For the total heat exhaust of the major-minor system of secondary circuit I loops；
Q42For the total heat exhaust of the major-minor system of secondary circuit II loops；
G41For secondary circuit I loop total flows；
G42For secondary circuit II loop total flows；
H41iFor secondary circuit I loop intermediate heat exchanger entrance enthalpies；
H41oEnthalpy is exported for secondary circuit I loops intermediate heat exchanger；
H42iFor secondary circuit II loop intermediate heat exchanger entrance enthalpies；
H42oEnthalpy is exported for secondary circuit II loops intermediate heat exchanger.
Further, the pool type natrium cold fast reactor low power run method of conventional island input, step (2- are not required as described above
1) in, one, secondary circuit cooling agent initial temperature be 230-250 DEG C.
Further, the pool type natrium cold fast reactor low power run method of conventional island input, step (2- are not required as described above
2) in, according to the overall heat removal capacity of the other systems in addition to main heat-transfer system, nuclear heating and the equalization point of heat extraction are calculated, and
According to the useful load of the total sodium of one, secondary circuit and its corresponding specific heat capacity, maximum temperaturerise limit value and corresponding time relationship are calculated.
Beneficial effects of the present invention are as follows：The pool type natrium cold fast reactor low-power fortune provided by the present invention for not putting into conventional island
Row method, on the premise of security allowance is ensured, improves economy, reliability and flexibility, and can fully effectively improve reality
The utilization ratio of heap is tested, improves the level of corresponding scientific research activity.
Brief description of the drawings
Fig. 1 is the China Experiment Fast Reactor normal operation flow chart of specific embodiment.
Figure includes the main heat-transfer system including primary Ioops, secondary circuit and three circuits, including accident afterheat removal system
Safety it is ad hoc.
Embodiment
The present invention is described in detail below with reference to the accompanying drawings and embodiments.
The pool type natrium cold fast reactor low power run method provided by the present invention that conventional island input is not required, including determine not
In the case of putting into three circuits, total one, the proper heat reduction amount of the major-minor system of secondary circuit are determined, thereby determining that can grow under equilibrium state
The peak power of phase operation.In addition, sodium total amount is loaded according to one, secondary circuit, according to initial starting temperature, you can determine in highest
Under conditions of temperature limit, highest and its relation of corresponding time that reactor can be run.Therefore, except in physics
Outside thermodynamic metering, to the related setting valve of control protection, equally accordingly changed, meet the requirement of safety allowance.
The present embodiment is by taking the China Experiment Fast Reactor (CEFR) shown in Fig. 1 as an example, the system equipment in Fig. 1 in double dot dash line,
Object as of the present invention, including primary Ioops Major Systems equipment, secondary circuit Major Systems equipment, accident afterheat exclude system
The related system equipment such as Major Systems equipment and the reactor pit ventilation of system.
Technical scheme includes calculating from composition and two parts of reactor operation verification experimental verification, specifically includes
Following steps：
1. determine the heat removal capacity of reactor other systems in addition to main heat-transfer system
(1-1) is net according to the flow and cold-trap of primary Ioops coolant cleanup system inlet and outlet differential thermal calculation primary Ioops cooling agent
The heat exhaust of change system；
Primary Ioops sodium clean-up system is not formal heat-extraction system, but the heat that can shed during its work, is had necessarily
Heat removal capacity.The heat removal capacity of the system can be increased by varying the method for operation (whether using interior economizer, increasing oil cooling energy
Power etc.), while the size of the ability is determined by calculation.
The heat exhaust formula for calculating primary Ioops coolant cleanup system is as follows：
Q1=G1(Hi-Ho)
Wherein：
Q1For primary Ioops cooling agent (sodium) cleaning system heat exhaust；
G1For flow；
HiFor sodium entrance enthalpy；
HoEnthalpy is returned for sodium.
(1-2) imports and exports differential thermal calculation accident afterheat discharge system according to accident afterheat discharge system flow and air cooler
Heat removal capacity；
Accident afterheat discharge system is used to exclude reactor waste during main heat-transfer system failure, same in normal operation
Possesses function.The system exports heat by Natural Circulation, its heat removal capacity is related to reactor temperature.Calculating, reactor is steady
Need to carry out complicated iterative calculation when constant temperature is spent.
The heat removal capacity computation model of accident afterheat discharge system is as follows：
Heat transfer model in accident afterheat removal system intermediate loop pipeline：
Wherein：
τ-time, s；
tNa- coolant temperature, DEG C；
tSMean temperature in-cooling agent tube wall around, DEG C；
tB0- tube wall ambient air temperature, DEG C；
Z- along coolant flow to coordinate, m；
uNa- coolant flow speed, m/s；
VNaCoolant volume in-unit length pipeline, m3；
VSThe volume of cooling agent tube wall around in-unit length pipeline, m3；
K3- the heat transfer coefficient from cooling agent to tube wall, W/m2·℃；
K4- the heat transfer coefficient from tube wall to surrounding air, W/m2·℃；
F3Heat exchange area on-unit length pipeline between cooling agent and tube wall, m2；
F4Heat exchange area between-unit length pipeline upper tube wall and surrounding air, m2；
CNa- coolant volume thermal capacitance, J/m3·℃；
CSThe average effective volumetric heat capacity of all tube walls around-cooling agent, J/m3·℃；
The heat transfer model of aerial cooler：
Wherein：
tNaCoolant temperature in-air heat exchanger bundle, DEG C；
tBAir themperature in-air heat exchanger, DEG C；
tSThe temperature of-air heat exchanger bundle metal, DEG C；
tSKThe temperature of-air heat exchanger the container acted in view of insulating layer, DEG C；
tB0- tube wall ambient air temperature, DEG C；
Z- is along the coordinate on air heat exchanger bundle length direction, m；
Z*- along the coordinate between air heat exchanger bundle on space length direction, m；
UNaSodium flowing velocity, m/s in-air heat exchanger bundle；
UBSpeed air flow in-air heat exchanger, m/s；
K1- the heat transfer coefficient between sodium and air heat exchanger bundle, W/m2·℃；
K2- tube bank and the heat transfer coefficient of interbank air, W/m2·℃；
K3Heat transfer coefficient between-air heat exchanger bundle between air and air heat exchanger container, W/m2·℃；
K4Heat transfer (considering heat insulation layer) coefficient between-air heat exchanger container and surrounding air, W/m2·℃；
F1Heat exchange area in-unit length between sodium and air heat exchanger bundle, m2；
F2The heat exchange area of air heat exchanger pipeline and interbank air in-unit length, m2；
F3Heat exchange area in-unit length between the interbank air of air heat exchanger and air heat exchanger container, m2；
F4Heat exchange area in-unit length between air heat exchanger container and surrounding air, m2；
CSThe effective volume thermal capacitance of-air heat exchanger bundle, J/m3·℃；
CB- volume of air thermal capacitance, J/m3·℃；
CSK- consider air heat exchanger bundle air heat exchanger container average effective volumetric heat capacity, J/m3·
℃；
CNa- coolant volume thermal capacitance, J/m3·℃；
VNaCoolant volume in-unit length in air heat exchanger bundle, m3；
VSThe volume of air heat exchanger bundle, m in-unit length3；
VBVolume of air between-air heat exchanger bundle in space in unit length, m3；
VSK- consider air heat exchanger volume of a container in the air heat exchanger container unit length of insulating layer,
m3；
The fluid mechanic model of accident afterheat removal system intermediate loop：
Wherein：
τ-time, s；
- descriptionThe vector of circuit units, m；
dPL(τ)-unitOn drive ram, Pa；
dξL(τ)-unitOn Flow Resistant Coefficient, relative unit；
ρL(τ)-unitOn coolant density, kg/m3；
- unitOn coolant velocity, m/s；
- acceleration of gravity, m/s2；
Accident afterheat removal system air flow channel heat exchange models：
Wherein：
τ-time, s；
tBAir themperature in-air flow channel, DEG C；
tS- consider insulating layer and concrete structure air flow channel temperature, DEG C；
tBoThe temperature of-air flow channel surrounding air, DEG C；
uBThe air velocity of-air pipeline, m/s；
K3Heat transfer coefficient in-air pipeline between air and tube wall, W/m2·℃；
K4- the heat transfer coefficient between air pipeline and surrounding air, W/m2·℃；
F3Heat exchange area in-air pipeline unit length between air and pipeline, m2；
F4Heat exchange area in-air pipeline unit length between pipeline and surrounding air, m2；
CB- volume of air thermal capacitance, J/m3·℃；
CSThe average effective volumetric heat capacity of all tube layer of-air pipeline, J/m3·℃；
VBVolume of air in-air pipeline unit length, m3；
VSThe volume of air duct structure in-air pipeline unit length, m3；
Accident afterheat removal system air flow channel fluid mechanic model：
Wherein
τ-time, s；
- descriptionThe vector of circuit units, m；
ΔPwind- the gas differential pressure formed on air flow channel population and outlet, Pa；
ΔPwPressure difference on (N, δ)-air heat exchanger export the breeze door, Pa；
The quantity of blade on N- air heat exchanger export the breeze doors, it is a；
The corner of blade on δ-air heat exchanger export the breeze door, degree；
dξL(τ)-air flow channel unitOn Flow Resistant Coefficient, relative unit；
ρL- air flow channel unitOn coolant density, kg/m3；
The unit of-air flow channelOn coolant velocity, m/s；
- acceleration of gravity, m/s2。
Q2=Q21+Q22
Q21=G21(H21i-H21o)
Q21=G22(H22i-H22o)
Wherein：
Q2For accident afterheat removal system heat exhaust；
Q21For accident afterheat removal system I loop heat exhausts；
Q22For accident afterheat removal system II loop heat exhausts；
G21For accident afterheat removal system I loop traffics；
G22For accident afterheat removal system II loop traffics；
H21iFor accident afterheat removal system I loop independent heat exchanger outlet temperatures；
H21oFor accident afterheat removal system I loop independent heat exchanger inlet temperatures；
H22iFor accident afterheat removal system II loop independent heat exchanger outlet temperatures；
H22oFor accident afterheat removal system II loop independent heat exchanger inlet temperatures.
(1-3) is according to reactor pit ventilating system air quantity and the heat extraction of protection container outer surface temperature computation reactor pit ventilating system
Amount；
Reactor pit ventilating system is used to cool down reactor pit, therefore inevitably takes the heat of reactor primary tank out of.Calculating
Simultaneous other factors are needed to carry out complicated iterative calculation during reactor equilibrium temperature.
The calculation formula of the heat exhaust of reactor pit ventilating system is as follows：
Q3=G3(H3o-H3i)
Wherein：
Q3For reactor pit ventilating system heat exhaust；
G3Pass through the ventilation quantity of reactor pit for reactor pit ventilating system；
H3iFor reactor pit ventilating system intake air enthalpy；
H3oFor reactor pit outlet of ventilating system air enthalpy.
(1-4) is according to intermediate heat exchanger secondary side sodium entrance temperature difference, the heat exhaust of the calculating major-minor system of secondary circuit；
By adjust secondary sodium revolution speed, secondary sodium cleaning system flow, secondary sodium analyze detecting system flow,
Major-minor system electrical heating of secondary circuit etc., can carry out secondary circuit heat exhaust adjustment control to a certain extent.
The heat exhaust calculation formula of the major-minor system of secondary circuit is as follows：
Q4=Q41+Q42
Q41=G41(H41o-H41i)
Q42=G42(H42o-H42i)
Wherein：
Q4For the total heat exhaust of the major-minor system of secondary circuit；
Q41For the total heat exhaust of the major-minor system of secondary circuit I loops；
Q42For the total heat exhaust of the major-minor system of secondary circuit II loops；
G41For secondary circuit I loop total flows；
G42For secondary circuit II loop total flows；
H41iFor secondary circuit I loop intermediate heat exchanger entrance enthalpies；
H41oEnthalpy is exported for secondary circuit I loops intermediate heat exchanger；
H42iFor secondary circuit II loop intermediate heat exchanger entrance enthalpies；
H42oEnthalpy is exported for secondary circuit II loops intermediate heat exchanger.
2. temperature rise limitation is calculated according to reactor one, secondary circuit cooling agent thermal capacitance
(2-1) determines one, secondary circuit cooling agent initial temperature；
At present under the cold shutdown state of the reality of CEFR, one, the temperature of secondary sodium be between 230~250 DEG C, Ke Yigen
It is adjusted according to needs.
(2-2) determines overall temperature rise rate according to nuclear heating；
By calculating the generation and discharge of heat, with reference to the thermal capacitance of one, secondary sodium, the rising of reactor temperature can be calculated
Speed.This obvious speed is not constant.
The present invention is according to the overall heat removal capacity of the other systems in addition to main heat-transfer system, the specific ginseng of association reaction heap
Number, calculates nuclear heating and the equalization point of heat extraction, and the useful load according to the total sodium of one, secondary circuit and its corresponding specific heat capacity, calculates
Maximum temperaturerise limit value and corresponding time relationship.The principle of the calculating and specific computational methods are the ordinary skill in the art.
3. reactor low power run
In the case that conventional island is not put into, reactor low power run, reactor hoisting power is not more than 1% specified work(
Rate, side entrance sodium temperature of monitoring intermediate heat exchanger are no more than 365 DEG C, maintain this section different IPs power step operation
4. according to the result of calculation and result of the test of above-mentioned steps, the related setting valve of Control protection system is repaiied
Change, to meet the requirement of safety allowance.Under low-power, under conditions of safety limit is met, part protection seting value is changed,
Lift safety allowance, for example power-level safety setting, core exit sodium temperature, one, the control of secondary circuit sodium pump interlocks etc..
China Experiment Fast Reactor power be less than 10% in the case of, power-level safety setting 11%, the value in three circuits not
In the case of putting into operation, it is necessary to for actual motion power, adjust accordingly.In addition, the protection of core exit sodium temperature
The related protection seting value such as value, period protection, will carry out tightened up limitation according to the actual requirements, in the case of necessary, increase
Part interlock protection, such as the control interlocking of one, secondary circuit sodium pump, intermediate heat exchanger entrance sodium temperature protection seting value etc..
China Experiment Fast Reactor carries out low power run in this way, and parameters meet Technical specification requirement.Also,
Operating standard can be formulated according to the method, for common operations staff according to guidelines.
Obviously, various changes and modifications can be made to the invention without departing from essence of the invention by those skilled in the art
God and scope.If in this way, belong to the model of the claims in the present invention and its equivalent technology to these modifications and changes of the present invention
Within enclosing, then the present invention is also intended to comprising including these modification and variations.
Claims (7)
1. a kind of pool type natrium cold fast reactor low power run method that conventional island input is not required, includes the following steps：
(1) heat removal capacity of reactor other systems in addition to main heat-transfer system is determined, including：
(1-1) imports and exports differential thermal calculation primary Ioops coolant purification system according to the flow and cold-trap of primary Ioops coolant cleanup system
The heat exhaust of system；
(1-2) imports and exports the heat extraction of differential thermal calculation accident afterheat discharge system according to accident afterheat discharge system flow and air cooler
Ability；
(1-3) is according to reactor pit ventilating system air quantity and the heat exhaust of protection container outer surface temperature computation reactor pit ventilating system；
(1-4) is according to intermediate heat exchanger secondary side sodium entrance temperature difference, the heat exhaust of the calculating major-minor system of secondary circuit；
(2) temperature rise limitation is calculated according to reactor one, secondary circuit cooling agent thermal capacitance, including：
(2-1) determines one, secondary circuit cooling agent initial temperature；
(2-2) determines overall temperature rise rate according to nuclear heating；
(3) in the case that conventional island is not put into, reactor low power run, reactor hoisting power is not more than 1% rated power,
Monitor side entrance sodium temperature of intermediate heat exchanger and be no more than 365 DEG C, maintain this section different IPs power step operation；
(4) according to step (1), the result of calculation of (2), and the result of the test of step (3), to the related whole of Control protection system
Definite value is modified, to meet the requirement of safety allowance.
2. the pool type natrium cold fast reactor low power run method of conventional island input is not required as claimed in claim 1, its feature exists
In：In step (1-1), the heat exhaust formula for calculating primary Ioops coolant cleanup system is as follows：
Q1=G1(Hi-Ho)
Wherein：
Q1For primary Ioops coolant cleanup system heat exhaust；
G1For flow；
HiFor sodium entrance enthalpy；
HoEnthalpy is returned for sodium.
3. the pool type natrium cold fast reactor low power run method of conventional island input is not required as claimed in claim 1, its feature exists
In：In step (1-2), the heat removal capacity computation model of accident afterheat discharge system is as follows：
Heat transfer model in accident afterheat removal system intermediate loop pipeline：
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Wherein：
τ-time, s；
tNa- coolant temperature, DEG C；
tSMean temperature in-cooling agent tube wall around, DEG C；
tB0- tube wall ambient air temperature, DEG C；
Z- along coolant flow to coordinate, m；
uNa- coolant flow speed, m/s；
VNaCoolant volume in-unit length pipeline, m3；
VSThe volume of cooling agent tube wall around in-unit length pipeline, m3；
K3- the heat transfer coefficient from cooling agent to tube wall, W/m2·℃；
K4- the heat transfer coefficient from tube wall to surrounding air, W/m2·℃；
F3Heat exchange area on-unit length pipeline between cooling agent and tube wall, m2；
F4Heat exchange area between-unit length pipeline upper tube wall and surrounding air, m2；
CNa- coolant volume thermal capacitance, J/m3·℃；
CSThe average effective volumetric heat capacity of all tube walls around-cooling agent, J/m3·℃；
The heat transfer model of aerial cooler：
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Wherein：
tNaCoolant temperature in-air heat exchanger bundle, DEG C；
tBAir themperature in-air heat exchanger, DEG C；
tSThe temperature of-air heat exchanger bundle metal, DEG C；
tSKThe temperature of-air heat exchanger the container acted in view of insulating layer, DEG C；
tB0- tube wall ambient air temperature, DEG C；
Z- is along the coordinate on air heat exchanger bundle length direction, m；
Z*- along the coordinate between air heat exchanger bundle on space length direction, m；
UNaSodium flowing velocity, m/s in-air heat exchanger bundle；
UBSpeed air flow in-air heat exchanger, m/s；
K1- the heat transfer coefficient between sodium and air heat exchanger bundle, W/m2·℃；
K2- tube bank and the heat transfer coefficient of interbank air, W/m2·℃；
K3Heat transfer coefficient between-air heat exchanger bundle between air and air heat exchanger container, W/m2·℃；
K4Heat transfer (considering heat insulation layer) coefficient between-air heat exchanger container and surrounding air, W/m2·℃；
F1Heat exchange area in-unit length between sodium and air heat exchanger bundle, m2；
F2The heat exchange area of air heat exchanger pipeline and interbank air in-unit length, m2；
F3Heat exchange area in-unit length between the interbank air of air heat exchanger and air heat exchanger container, m2；
F4Heat exchange area in-unit length between air heat exchanger container and surrounding air, m2；
CSThe effective volume thermal capacitance of-air heat exchanger bundle, J/m3·℃；
CB- volume of air thermal capacitance, J/m3·℃；
CSK- consider air heat exchanger bundle air heat exchanger container average effective volumetric heat capacity, J/m3·℃；
CNa- coolant volume thermal capacitance, J/m3·℃；
VNaCoolant volume in-unit length in air heat exchanger bundle, m3；VSAir heat exchanger in-unit length
The volume of tube bank, m3；
VBVolume of air between-air heat exchanger bundle in space in unit length, m3；
VSK- consider air heat exchanger volume of a container in the air heat exchanger container unit length of insulating layer, m3；
The fluid mechanic model of accident afterheat removal system intermediate loop：
Wherein：
τ-time, s；
- descriptionThe vector of circuit units, m；
dPL(τ)-unitOn drive ram, Pa；
dξL(τ)-unitOn Flow Resistant Coefficient, relative unit；
ρL(τ)-unitOn coolant density, kg/m3；
- unitOn coolant velocity, m/s；
- acceleration of gravity, m/s2；
Accident afterheat removal system air flow channel heat exchange models：
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Wherein：
τ-time, s；
tBAir themperature in-air flow channel, DEG C；
tS- consider insulating layer and concrete structure air flow channel temperature, DEG C；
tBoThe temperature of-air flow channel surrounding air, DEG C；
uBThe air velocity of-air pipeline, m/s；
K3Heat transfer coefficient in-air pipeline between air and tube wall, W/m2·℃；
K4- the heat transfer coefficient between air pipeline and surrounding air, W/m2·℃；
F3Heat exchange area in-air pipeline unit length between air and pipeline, m2；
F4Heat exchange area in-air pipeline unit length between pipeline and surrounding air, m2；
CB- volume of air thermal capacitance, J/m3·℃；
CSThe average effective volumetric heat capacity of all tube layer of-air pipeline, J/m3·℃；
VBVolume of air in-air pipeline unit length, m3；
VSThe volume of air duct structure in-air pipeline unit length, m3；
Accident afterheat removal system air flow channel fluid mechanic model：
Wherein
τ-time, s；
- descriptionThe vector of circuit units, m；
ΔPwind- the gas differential pressure formed on air flow channel population and outlet, Pa；
ΔPwPressure difference on (N, δ)-air heat exchanger export the breeze door, Pa；
The quantity of blade on N- air heat exchanger export the breeze doors, it is a；
The corner of blade on δ-air heat exchanger export the breeze door, degree；
dξL(τ)-air flow channel unitOn Flow Resistant Coefficient, relative unit；
ρL- air flow channel unitOn coolant density, kg/m3；
The unit of-air flow channelOn coolant velocity, m/s；
- acceleration of gravity, m/s2；
Q2=Q21+Q22
Q21=G21(H21i-H21o)
Q21=G22(H22i-H22o)
Wherein：
Q2For accident afterheat removal system heat exhaust；
Q21For accident afterheat removal system I loop heat exhausts；
Q22For accident afterheat removal system II loop heat exhausts；
G21For accident afterheat removal system I loop traffics；
G22For accident afterheat removal system II loop traffics；
H21iFor accident afterheat removal system I loop independent heat exchanger outlet temperatures；
H21oFor accident afterheat removal system I loop independent heat exchanger inlet temperatures；
H22iFor accident afterheat removal system II loop independent heat exchanger outlet temperatures；
H22oFor accident afterheat removal system II loop independent heat exchanger inlet temperatures.
4. the pool type natrium cold fast reactor low power run method of conventional island input is not required as claimed in claim 1, its feature exists
In：In step (1-3), the calculation formula of the heat exhaust of reactor pit ventilating system is as follows：
Q3=G3(H3o-H3i)
Wherein：
Q3For reactor pit ventilating system heat exhaust；
G3Pass through the ventilation quantity of reactor pit for reactor pit ventilating system；
H3iFor reactor pit ventilating system intake air enthalpy；
H3oFor reactor pit outlet of ventilating system air enthalpy.
5. the pool type natrium cold fast reactor low power run method of conventional island input is not required as claimed in claim 1, its feature exists
In：In step (1-4), the heat exhaust calculation formula of the major-minor system of secondary circuit is as follows：
Q4=Q41+Q42
Q41=G41(H41o-H41i)
Q42=G42(H42o-H42i)
Wherein：
Q4For the total heat exhaust of the major-minor system of secondary circuit；
Q41For the total heat exhaust of the major-minor system of secondary circuit I loops；
Q42For the total heat exhaust of the major-minor system of secondary circuit II loops；
G41For secondary circuit I loop total flows；
G42For secondary circuit II loop total flows；
H41iFor secondary circuit I loop intermediate heat exchanger entrance enthalpies；
H41oEnthalpy is exported for secondary circuit I loops intermediate heat exchanger；
H42iFor secondary circuit II loop intermediate heat exchanger entrance enthalpies；
H42oEnthalpy is exported for secondary circuit II loops intermediate heat exchanger.
6. the pool type natrium cold fast reactor low power run method of conventional island input is not required as claimed in claim 1, its feature exists
In：In step (2-1), one, secondary circuit cooling agent initial temperature be 230-250 DEG C.
7. the pool type natrium cold fast reactor low power run method of conventional island input is not required as claimed in claim 1, its feature exists
In：In step (2-2), according to the overall heat removal capacity of the other systems in addition to main heat-transfer system, nuclear heating and heat extraction are calculated
Equalization point, and the useful load according to the total sodium of one, secondary circuit and its corresponding specific heat capacity, calculate maximum temperaturerise limit value and time pair
It should be related to.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
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| RU2691755C2 (en) * | 2017-07-24 | 2019-06-18 | Российская Федерация, от имени которой выступает Государственная корпорация по атомной энергии "Росатом" | Method of natural circulation of a liquid metal coolant of a fast neutron reactor |
| CN109033529B (en) * | 2018-06-28 | 2020-05-19 | 西安交通大学 | Method for determining heat transfer and dry-up point of fragment bed after sodium-cooled fast reactor serious accident |
| CN110472270B (en) * | 2019-06-28 | 2022-09-27 | 合肥通用机械研究院有限公司 | Modeling optimization method of sodium cooled reactor passive waste heat removal system |
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