CN111180094A - Temperature rise calculation method for nuclear power plant spent fuel pool coolant loss accident - Google Patents

Temperature rise calculation method for nuclear power plant spent fuel pool coolant loss accident Download PDF

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Publication number
CN111180094A
CN111180094A CN201911348219.XA CN201911348219A CN111180094A CN 111180094 A CN111180094 A CN 111180094A CN 201911348219 A CN201911348219 A CN 201911348219A CN 111180094 A CN111180094 A CN 111180094A
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Prior art keywords
spent fuel
fuel pool
temperature
pool
power plant
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CN201911348219.XA
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Chinese (zh)
Inventor
李振振
孟凡锋
蔡光明
郑东佳
章圣斌
彭超
黄丹宾
高原
兰蛟龙
张鹏
耿飞
程宏亚
张羽
肖冰山
顾蔚泉
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CNNC Fujian Nuclear Power Co Ltd
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CNNC Fujian Nuclear Power Co Ltd
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • G21C17/038—Boiling detection in moderator or coolant
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention belongs to the technical field of nuclear power plant operation, and particularly relates to a temperature rise calculation method for a spent fuel pool of a nuclear power plant under a loss accident of a coolant. According to the method, the spent fuel exposure time of the nuclear power plant spent fuel pool in the accident of losing cooling can be evaluated, a basis is provided for making decisions and relieving measures of the nuclear power plant in the accident, and similar accidents of different reactor types can be evaluated according to the method.

Description

Temperature rise calculation method for nuclear power plant spent fuel pool coolant loss accident
Technical Field
The invention belongs to the technical field of nuclear power plant operation, and particularly relates to a temperature rise calculation method for a spent fuel pool coolant loss accident of a nuclear power plant.
Background
In 2011, after the fukushima nuclear accident, the importance of the cooling problem of the spent fuel pool is concerned by each expert. At present, after each nuclear power plant loses cooling to the spent fuel, the time for the temperature of the spent fuel pool to rise to 100 ℃ is calculated, but the leakage risk of the spent fuel pool under the actual accident and the worst working condition that the spent fuel is exposed are not considered, so the time has smaller practical application significance.
When the spent fuel is stored in the spent fuel pool, decay heat generated by decay of 239U, 239Np and other actinides and fission products is mainly led out by a heat exchanger, so that the temperature of the spent fuel pool is less than 50 ℃.
When the spent fuel pool loses cooling, the decay heat can not be transmitted to the cold source to cause the temperature of the spent fuel pool to rise, but after the temperature of the spent pool rises to 100 ℃, the decay heat is vaporized and taken out of the spent fuel pool, if the spent fuel pool can not be recovered after being cooled for a long time, the spent fuel component can be exposed, and further the fuel component is damaged.
If the spent fuel pool is not cooled and a leakage accident of the spent fuel pool occurs at the same time, the temperature of the spent fuel pool can be raised to 100 ℃, the exposure time of fuel assemblies can be shortened, and the like, so that the simultaneous occurrence needs to be considered.
Disclosure of Invention
The invention aims to provide a temperature rise calculation method for a spent fuel pool of a nuclear power plant under a loss accident of a coolant.
The invention comprises the following steps:
a temperature rise calculation method under the nuclear power plant spent fuel pool coolant loss accident is characterized in that a spent fuel pool is exposed from loss of cooling to fuel assemblies, and the method can be divided into the following two processes:
in the first case, the temperature of the spent fuel pool rises from the temperature when the cooling is lost to the boiling temperature of water of 100 ℃;
in the second condition, the temperature of the spent fuel pool reaches 100 ℃ and begins to evaporate until the liquid level is reduced to the upper tube base of the spent fuel assembly.
When the temperature of the spent fuel pool rises to the boiling temperature of water 100 ℃ from the loss of cooling, the method can be divided into the following steps:
a. lose cooling but no leakage from dead pool
b. Lost cooling and spent pool leakage.
For case a, the time for the spent fuel pool to rise from the temperature at which cooling is lost to the boiling temperature of water of 100 ℃ can be determined by the following equation:
t＝cpρQ0ΔT/P0(1)
in the formula: p0: decay heat of spent fuel in spent fuel pool
t: time required for temperature of spent fuel pool to rise by delta T
cp: constant pressure specific heat capacity (kJ/kg) of water under standard atmospheric pressure
ρ: density of water at standard atmospheric pressure
Q0: water capacity of spent fuel pool
Δ T: the temperature change of the spent fuel pool is generally equal to 100-T0Wherein T is0The temperature of the spent fuel pool when cooling is lost.
For case b, the rate of temperature rise can be represented by the following formula;
Figure RE-GDA0002448145280000031
integrate (2) and use boundary conditions to deduce:
Figure RE-GDA0002448145280000032
in the formula: q: the leakage rate of the spent fuel pool is shown.
When the temperature of the spent fuel pool reaches 100 ℃, the spent fuel pool begins to evaporate until the liquid level is reduced to the upper tube base of the spent fuel assembly,
after the temperature of the spent fuel pool reaches 100 ℃, the liquid level reduction rate caused by evaporation is as follows:
v1＝P0/(Wr*S) (4)
the rate of liquid level drop due to leakage is:
v2＝q/S (5)
in the formula: wr: latent heat of vaporization of water at standard atmospheric pressure;
s: the surface area of the spent fuel pool;
considering the lower descending rate in two cases of evaporation and leakage;
v＝v1+v2(6)。
therefore, the time from the evaporation of the spent fuel pool to the liquid level reduction to the upper tube seat of the spent fuel assembly when the temperature of the spent fuel pool reaches 100 ℃ is the smaller of the following two formulas:
t＝(h0-t0v2)/v (7)
t＝h0/v2(8)
in the formula: h is0: the water surface of the spent pool is according to the distance of the upper tube seat of the spent fuel when the spent pool loses cooling;
t0: the time for the spent fuel pool to reach 100 ℃.
The method is suitable for the condition that the spent fuel pool loses cooling.
The invention has the following beneficial effects:
according to the method, the spent fuel exposure time of the nuclear power plant spent fuel pool in the accident of losing cooling can be evaluated, a basis is provided for making decisions and relieving measures of the nuclear power plant in the accident, and similar accidents of different reactor types can be evaluated according to the method.
Detailed Description
The invention will be further illustrated with reference to specific examples:
a temperature rise calculation method under the nuclear power plant spent fuel pool coolant loss accident is characterized in that a spent fuel pool is exposed from loss of cooling to fuel assemblies, and the method can be divided into the following two processes:
1. the temperature of the spent fuel pool rises from the temperature when the cooling is lost to the boiling temperature of water of 100 ℃;
2. the temperature of the spent fuel pool reaches 100 ℃, and the spent fuel pool begins to evaporate until the liquid level is reduced to the upper tube base of the spent fuel assembly.
The temperature of the spent fuel pool rises from the cooling loss to the boiling temperature of water of 100 ℃, and the spent fuel pool can be divided into:
a. lose cooling but no leakage from dead pool
b. Lost cooling and spent pool leakage.
For case a, the time for the spent fuel pool to rise from the temperature at which cooling is lost to the boiling temperature of water of 100 ℃ can be determined by the following equation:
t＝cpρQ0ΔT/P0(1)
in the formula: p0: decay heat of spent fuel in spent fuel pool
t: time required for temperature of spent fuel pool to rise by delta T
cp: constant pressure specific heat capacity (kJ/kg) of water under standard atmospheric pressure
ρ: density of water at standard atmospheric pressure
Q0: water capacity of spent fuel pool
Δ T: the temperature change of the spent fuel pool is generally equal to 100-T0Wherein T is0Temperature of spent fuel pool when cooling is lost
For case b, the rate of temperature rise may be represented by the following formula:
Figure RE-GDA0002448145280000051
integrate (2) and use boundary conditions to deduce:
Figure RE-GDA0002448145280000052
in the formula: q: for spent fuel pool leakage rate
The temperature of the spent fuel pool reaches 100 ℃, and the spent fuel pool begins to evaporate to a liquid level and falls to an upper pipe seat of the spent fuel assembly
After the temperature of the spent fuel pool reaches 100 ℃, the liquid level reduction rate caused by evaporation is as follows:
v1＝P0/(Wr*S) (4)
the rate of liquid level drop due to leakage is:
v2＝q/S (5)
in the formula: wr: latent heat of vaporization of water at standard atmospheric pressure
S: surface area of spent fuel pool
Considering the rate of descent in both evaporation and leakage
v＝v1+v2(6)
Therefore, the time from the evaporation of the spent fuel pool to the liquid level reduction to the upper tube seat of the spent fuel assembly when the temperature of the spent fuel pool reaches 100 ℃ is the smaller of the following two formulas:
t＝(h0-t0v2)/v (7)
t＝h0/v2(8)
in the formula: h is0: distance between water surface of spent pool and upper tube base of spent fuel when spent pool loses cooling
t0: the time for the spent fuel pool to reach 100 ℃.
1. Acquiring design parameters of a spent fuel pool of a nuclear power plant as known quantities, wherein the design parameters are shown in the following table:
Figure RE-GDA0002448145280000061
2. when the accidents of the loss of cooling and the loss of water content of the spent fuel pool occur in the nuclear power plant, obtaining the decay heat and the leakage rate of the spent fuel pool at the moment;
3. and substituting the parameters into a formula of the technical scheme according to different situations to obtain the related data.

Claims (7)

1. A temperature rise calculation method under the nuclear power plant spent fuel pool coolant loss accident is characterized in that a spent fuel pool is exposed from loss of cooling to fuel assemblies, and the method can be divided into the following two processes:
the method is characterized in that: in the first case, the temperature of the spent fuel pool rises from the temperature when the cooling is lost to the boiling temperature of water of 100 ℃;
in the second condition, the temperature of the spent fuel pool reaches 100 ℃ and begins to evaporate until the liquid level is reduced to the upper tube base of the spent fuel assembly.
2. The method for calculating the temperature rise of the nuclear power plant spent fuel pool in the event of coolant loss according to claim 1, is characterized in that: when the temperature of the spent fuel pool rises to the boiling temperature of water 100 ℃ from the loss of cooling, the method can be divided into the following steps:
a. lose cooling but no leakage from dead pool
b. Lost cooling and spent pool leakage.
3. The method for calculating the temperature rise of the nuclear power plant spent fuel pool in the event of coolant loss according to claim 2, characterized in that:
for case a, the time for the spent fuel pool to rise from the temperature at which cooling is lost to the boiling temperature of water of 100 ℃ can be determined by the following equation:
t＝cpρQ0ΔT/P0(1)
in the formula: p0: decay heat of spent fuel in spent fuel pool
t: time required for temperature of spent fuel pool to rise by delta T
cp: constant pressure specific heat capacity (kJ/kg) of water under standard atmospheric pressure
ρ: density of water at standard atmospheric pressure
Q0: water capacity of spent fuel pool
Δ T: the temperature change of the spent fuel pool is generally equal to 100-T0Wherein T is0The temperature of the spent fuel pool when cooling is lost.
4. The method for calculating the temperature rise of the nuclear power plant spent fuel pool in the event of coolant loss according to claim 2, characterized in that: for case b, the rate of temperature rise can be represented by the following formula;
Figure FDA0002333990080000021
integrate (2) and use boundary conditions to deduce:
Figure FDA0002333990080000022
in the formula: q: the leakage rate of the spent fuel pool is shown.
5. The method for calculating the temperature rise of the nuclear power plant spent fuel pool in the event of coolant loss according to claim 1, is characterized in that: when the temperature of the spent fuel pool reaches 100 ℃, the spent fuel pool begins to evaporate until the liquid level is reduced to the upper tube base of the spent fuel assembly,
after the temperature of the spent fuel pool reaches 100 ℃, the liquid level reduction rate caused by evaporation is as follows:
v1＝P0/(Wr*S) (4)
the rate of liquid level drop due to leakage is:
v2＝q/S (5)
in the formula: wr: latent heat of vaporization of water at standard atmospheric pressure;
s: the surface area of the spent fuel pool;
considering the lower descending rate in two cases of evaporation and leakage;
v＝v1+v2(6)。
6. the method for calculating the temperature rise of the nuclear power plant spent fuel pool in the event of coolant loss according to claim 5, characterized in that: therefore, the time from the evaporation of the spent fuel pool to the liquid level reduction to the upper tube seat of the spent fuel assembly when the temperature of the spent fuel pool reaches 100 ℃ is the smaller of the following two formulas:
t＝(h0-t0v2)/v (7)
t＝h0/v2(8)
in the formula: h is0: the water surface of the spent pool is according to the distance of the upper tube seat of the spent fuel when the spent pool loses cooling;
t0: the time for the spent fuel pool to reach 100 ℃.
7. The method for calculating the temperature rise in the nuclear power plant spent fuel pool coolant loss accident according to any one of claims 1 to 6, is characterized in that: the method is suitable for the condition that the spent fuel pool loses cooling.
CN201911348219.XA 2019-12-24 2019-12-24 Temperature rise calculation method for nuclear power plant spent fuel pool coolant loss accident Pending CN111180094A (en)

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Publication number Priority date Publication date Assignee Title
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CN107644694A (en) * 2017-09-20 2018-01-30 岭东核电有限公司 A kind of nuclear power plant's large break crash analysis method
CN107887043A (en) * 2017-10-10 2018-04-06 福建福清核电有限公司 A kind of reactor capability coefficient measuring method

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Publication number Priority date Publication date Assignee Title
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Application publication date: 20200519