CN111354488B - Nuclear fuel assembly vacuum off-line sipping detection device and method - Google Patents
Nuclear fuel assembly vacuum off-line sipping detection device and method Download PDFInfo
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- CN111354488B CN111354488B CN201811571715.7A CN201811571715A CN111354488B CN 111354488 B CN111354488 B CN 111354488B CN 201811571715 A CN201811571715 A CN 201811571715A CN 111354488 B CN111354488 B CN 111354488B
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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
- G21C17/04—Detecting burst slugs
- G21C17/042—Devices for selective sampling, e.g. valves, shutters, rotatable selector valves
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/104—Measuring reactivity
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- 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
Abstract
The invention relates to the field of fuel assembly damage detection, in particular to a vacuum off-line sipping detection method for detecting whether a nuclear fuel assembly is damaged. The invention provides a vacuum off-line sipping detection method for detecting whether a nuclear fuel assembly is damaged. The method can be used for detecting the breakage condition of the nuclear fuel assembly on the premise of not damaging the integrity of the assembly. A nuclear fuel assembly vacuum off-line sipping detection device, comprising: the system comprises a fuel assembly, a sipping barrel, a pressure sensor, a vacuum pump, a radioactive detector, a steam-water separator and a non-radioactive water source. A nuclear fuel assembly vacuum offline sipping detection method comprising: the method comprises the following steps: detecting the air flushing of the loop; step two: sipping the tube for water washing; step three: sipping detection; step four: analyzing the detection data; step five: and finishing the detection. The invention is suitable for offline sipping detection of all fuel assemblies, avoids safety risks possibly caused by heating, and has the advantages of convenient operation and easy implementation.
Description
Technical Field
The invention relates to the field of fuel assembly damage detection, in particular to a vacuum off-line sipping detection method for detecting whether a nuclear fuel assembly is damaged.
Background
The fuel rod cladding of the nuclear fuel assembly is also the most important barrier for preventing radioactive substances from leaking out as the first way of preventing the radioactive substances from leaking out of the nuclear power station, is in a high-temperature, high-pressure and strong-radiation working environment for a long time, and is often influenced by numerous factors such as water flow impact, foreign matters, vibration, corrosion, heat transfer, irradiation and the like in the operation process, wherein some assemblies can be inevitably damaged and leaked, the sealing property and the integrity of the fuel element cladding are damaged, and the safety of a reactor and the environment is seriously influenced.
Off-line sipping detection is a method for qualitatively and quantitatively detecting the damage condition of the fuel assembly cladding. Implementations of off-line sipping techniques are classified into heating and vacuum. The invention provides a vacuum off-line sipping detection method for detecting whether a nuclear fuel assembly is damaged. The method includes detecting a failure condition of the nuclear fuel assembly without destroying the integrity of the assembly.
Disclosure of Invention
Firstly, the purpose is as follows:
the invention mainly aims to provide a method for detecting the integrity of a fuel assembly cladding and qualitatively and quantitatively analyzing the damage condition of the fuel assembly.
The technical scheme is as follows:
after the spent fuel assembly leaves the reactor, the chain fission reaction is stopped, generally speaking, the fissile nuclide is not generated any more, the chain fission reaction generates radioactive fission products such as Xe-133, Kr-85, I-131 and Cs-136, the radioactive fission products exist in the gap of the fuel cladding, once the fuel rod is damaged, the radioactive fission products are leaked from the damaged part along with the change of external environment parameters such as pressure reduction, temperature rise and the like, and the detection object is provided for the detection of the damaged spent fuel.
Fission products within a nuclear fuel assembly include primarily Xe-133, Kr-85, I-131, Cs-136, Cs-134, Cs-137, and isotopes of Xe and Kr. Because the gas sample can enter the detection chamber more quickly, the gas sample is easy to clean and is not easy to cause radioactive contamination of equipment, the detection object of the invention is a gaseous fission product. The gaseous fission products which are not easy to dissolve in water in fission products are mainly Xe-133 and Kr-85, the half-life period of the Xe-133 is 5.24 days, the half-life period of the Kr-85 is 10.7 years, and the radioactive detection of the two radioactive gases can be suitable for detecting fuel assemblies from just coming out of a reactor core to being stored for several years.
A nuclear fuel assembly vacuum off-line sipping detection device, comprising: fuel assembly, sipping barrel, pressure sensor, vacuum pump, radioactivity detector, steam-water separator and non-radioactive water source. The fuel assembly is placed in the sipping barrel, the sipping barrel is connected with the steam-water separator through a valve V003, the pressure sensor is connected with the sipping barrel, and the nonradioactive water source is connected with the sipping barrel through a valve V009; one end of the valve V001 is connected with a compressed air source, and the other end of the valve V001 is sequentially connected with the steam-water separator, the valve V003 and the sipping barrel through the check valve; one end of the valve V002 is connected with the steam-water separator through a check valve, the other end of the valve V002 is connected with a vacuum pump, the other end of the vacuum pump is connected with a radioactive detector, the other end of the radioactive detector is connected with a valve V005, and the other end of the valve V005 is connected with a gas discharge system;
one end of the valve V004 is connected with the steam-water separator through a check valve, and the other end of the valve V008 is connected with the valve; the gas discharge system is connected with the bottom of the sipping barrel sequentially through a valve V007, a valve V008, a check valve, a valve V006 and the sipping barrel;
a valve V010 is arranged at the bottom of the sipping barrel;
a nuclear fuel assembly vacuum off-line sipping inspection method comprising:
the method comprises the following steps: detection loop gas flushing
The method comprises the steps of opening valves V001, V002, V004, V005, V007, V008 and a vacuum pump 4, flushing pipelines and chambers of a loop system on water by utilizing non-radioactive gas, monitoring the radioactivity level in the loop by using a radioactivity detector 5 in the flushing process, stopping the flushing process when the radioactivity in the loop is lower than a determined lowest background radioactivity index, and closing the valves V001, V002, V004, V005, V007, V008 and the vacuum pump 4.
Step two: sipping barrel water wash
1. Hoisting the fuel component 1 to be tested in the sipping tube 2 by using a spent fuel pool crane, closing a sealing cover of the sipping tube 2, and sealing the fuel component 1, wherein the periphery of the fuel component is filled with boron-containing water in the spent water pool.
2. Opening valves V009 and V010, injecting clean water from non-radioactive water source 7 from the upper part of sipping tube 2, and simultaneously draining and replacing from the lower part of sipping tube 2, and preferably injecting water with volume n times or more (n is more than 2) sipping tube. After completion of the water displacement process, valves V009 and V010 were closed.
3. Opening valves V001, V004, V006 and V010, filling non-radioactive gas into the sipping barrel 2, simultaneously draining water from the lower part of the sipping barrel 2, forming a gas space with a certain volume at the upper part of the sipping barrel 2, closing the valves V001, V004, V006 and V010, and detecting the gas background N0 at the moment.
Step three: sipping assay
1. Opening valves V003 and V002 and vacuum pump, evacuating sip barrel 2, monitoring pressure indication of pressure sensor 3 until pressure in sip barrel 2 reaches set pressure value P1, and closing valves V003 and V002 and vacuum pump. And after standing for a certain time t, opening valves V003, V002, a vacuum pump, V005, V008 and V006, and circulating the radioactive fission gas escaping from the fuel rods by utilizing gas carrying in the loop so as to uniformly mix the gas in the sip suction tube 2 and the gas in the loop.
2. The mixed gas after uniform mixing continuously circulates in the loop, the radioactivity of the mixed gas is measured by the radioactivity detector 5, and the radioactivity of the target nuclide is analyzed and recorded as N1.
Step four: analysis of test data
1. Comparing N1 and N0, if N1> kN0, it is determined that there is a breakage of the detected fuel assembly 1. K is a judgment coefficient, K is 2 to 10, and the judgment coefficient is determined according to the actual detector precision.
2. If kN0 is more than or equal to N1 is more than or equal to N0, repeating the three operation processes, reducing the pressure value obtained by air suction to P2(P2 is less than P1), and recording the radioactivity of the sample gas as N2 after the measured pressure is reduced to P2.
3. Comparing N2 with N0, if N2 is not less than kN0, it is judged that there is a breakage of the detected fuel assembly 1.
4. If kN0> N2, it is determined that there is no breakage of the fuel assembly 1.
Step five: completion detection
1. After completion of the nuclear fuel assembly vacuum off-line sipping assay, all valves except V001 and V007 are opened, after the assay system returns to normal pressure, valves V003 and V006 are closed, the sipping barrel 2 is opened, and the fuel assembly is slung out.
2. And (4) repeating the step (1), cleaning the loop system, and preparing to perform the next group of nuclear fuel assembly offline sipping detection.
Thirdly, the effect:
the fuel assembly vacuum off-line sipping detection method designed by the invention is suitable for off-line sipping detection of all fuel assemblies. Through detecting gaseous sample, can high efficiency realize the damaged testing process of fuel assembly, through the mode that reduces pressure, avoid the safety risk that the heating probably caused, the detection device convenient operation who designs, easy to carry out.
Drawings
FIG. 1 is a schematic view of a vacuum off-line sipping detection method
1. Fuel assembly 2, sipping barrel 3, pressure sensor 4, vacuum pump 5, radioactive detector 6, steam-water separator 7 and non-radioactive water source
Detailed Description
The following detailed description of the patent refers to the accompanying drawings and specific embodiments:
as shown in fig. 1, the implementation of the method relies on a vacuum offline sipping system, which mainly comprises a sipping barrel 2, a pressure sensor 3, a vacuum pump 4, a radioactive detector 5, a vapor-water separator 6 and a non-radioactive water source 7.
The water loop system mainly comprises a pressure sensor 3, a vacuum pump 4, a radioactive detector 5 and a steam-water separator 6, and the loop is provided with a gas source for radioactive gas and a gas exhaust port for detection.
The sipping tube 2 of the invention is a sealed container which can realize the sealing of the fuel component 1 under water, the sipping tube 2 is arranged under water in the detection process, the upper part and the lower part of the sipping tube 2 are provided with two interfaces, the upper interface of the sipping tube 2 is connected with the front end of a vacuum pump 4 of an over-water loop system, and the lower interface of the sipping tube 2 is connected with the rear end of a radioactive detector 5.
Hoisting the nuclear fuel assembly to be detected into a container (sipping barrel) capable of realizing an underwater sealing function, sealing and isolating the nuclear fuel assembly to be detected, utilizing an over-water loop system connected with the sipping barrel, blowing non-radioactive gas into the sipping barrel, draining a part of water in the sipping barrel, and forming a gas space at the upper part of the sipping barrel. The pressure in the sipping barrel is reduced by pumping a part of the gas in the gas space through the loop system. Once the nuclear fuel assembly is damaged, under the condition that gas exists in the cladding, the radioactive fission gas can be effectively released into the sipping barrel under the external negative pressure condition, then the gas in the sipping barrel is drawn into the radioactive detection device, and the damage condition of the assembly can be quantitatively analyzed by qualitatively and quantitatively detecting the radioactive concentration of the target reflective nuclide.
The detection process of the invention is as follows:
the method comprises the following steps: detection loop gas flushing
The method comprises the steps of opening valves V001, V002, V004, V005, V007, V008 and a vacuum pump 4, flushing pipelines and chambers of a loop system on water by utilizing non-radioactive gas, monitoring the radioactivity level in the loop by using a radioactivity detector 5 in the flushing process, stopping the flushing process when the radioactivity in the loop is lower than a determined lowest background radioactivity index, and closing the valves V001, V002, V004, V005, V007, V008 and the vacuum pump 4.
Step two: sipping barrel water flush
1. Using a spent fuel pool crane to hang the fuel component 1 to be tested in the sipping barrel 2, closing the sealing cover of the sipping barrel 2, sealing the fuel component 1, and filling the periphery of the fuel component with boron-containing water in the spent pool.
2. Opening valves V009 and V010, injecting clean water from non-radioactive water source 7 from the upper part of sipping tube 2, and simultaneously draining and replacing from the lower part of sipping tube 2, and preferably injecting water with volume n times or more (n is more than 2) sipping tube. After completion of the water displacement process, valves V009 and V010 were closed.
3. Opening valves V001, V004, V006 and V010, filling nonradioactive gas into the sipping suction tube 2, simultaneously draining water from the lower part of the sipping suction tube 2, forming a certain volume of gas space at the upper part of the sipping suction tube 2, closing the valves V001, V004, V006 and V010, and detecting the gas background N0 at the moment.
Step three: sipping detection
1. Opening the valves V003 and V002 and the vacuum pump, evacuating the sipping tube 2, monitoring the pressure indication of the pressure sensor 3 until the pressure in the sipping tube 2 reaches the set pressure value P1, and closing the valves V003 and V002 and the vacuum pump. And after standing for a certain time t, opening valves V003, V002, a vacuum pump, V005, V008 and V006, and circulating the radioactive fission gas escaping from the fuel rods by utilizing gas carrying in the loop so as to uniformly mix the gas in the sip suction tube 2 and the gas in the loop.
2. The mixed gas after uniform mixing continuously circulates in the loop, the radioactivity of the mixed gas is measured by the radioactivity detector 5, and the radioactivity of the target nuclide is analyzed and recorded as N1.
Step four: analysis of test data
1. Comparing N1 and N0, if N1> kN0, it is determined that there is a breakage of the detected fuel assembly 1. K is a judgment coefficient, K is 2 to 10, and the judgment coefficient is determined according to the actual detector precision.
2. If kN0 is more than or equal to N1 more than or equal to N0, repeating the three steps, reducing the pressure value of the air suction to P2(P2< P1), and recording the radioactivity of the sample gas as N2 after the measured pressure is reduced to P2.
3. Comparing N2 with N0, if N2 is not less than kN0, it is judged that there is a breakage of the detected fuel assembly 1.
4. If kN0> N2, it is determined that there is no breakage of the fuel assembly 1.
Step five: completion detection
1. Completing the vacuum off-line sipping test of the fuel assembly, opening all valves except V001 and V007, after the test system recovers to normal pressure, closing valves V003 and V006, opening sipping barrel 2, and lifting the fuel assembly out.
2. And repeating the first step, cleaning the loop system and preparing to perform the next group of nuclear fuel assembly offline sipping detection.
Claims (6)
1. A nuclear fuel assembly vacuum off-line sipping inspection method, comprising: the device comprises: the system comprises a fuel assembly (1), a sipping suction tube (2), a pressure sensor (3), a vacuum pump (4), a radiation detector (5), a steam-water separator (6) and a non-radioactive water source (7); the fuel assembly (1) is placed in the sipping barrel (2), the sipping barrel (2) is connected with the steam-water separator (6) through a valve V003, the pressure sensor (3) is connected with the sipping barrel (2), and the nonradioactive water source (7) is connected with the sipping barrel (2) through a valve V009; one end of the valve V001 is connected with a compressed air source, and the other end is respectively connected with the valve V002 and the valve V004 and is connected with the steam-water separator (6) through a check valve; one end of a valve V002 is connected with a steam-water separator (6) through a check valve, the other end of the valve V002 is connected with a vacuum pump (4), the other end of the vacuum pump (4) is connected with a radioactive detector (5), the other end of the radioactive detector (5) is connected with a valve V005, the other end of the valve V005 is connected with a gas discharge system through a connecting valve V007 and a valve V008;
one end of the valve V004 is connected with the steam-water separator (6) through a check valve, and the other end of the valve V008 is connected with a check valve of a gas discharge system; the gas discharge system is connected with the bottom of the sipping barrel (2) through a valve V007, a valve V008, a check valve, a valve V006 and the sipping barrel in sequence;
the bottom of the sipping barrel (2) is provided with a valve V010;
the detection method comprises the following steps: the method comprises the following steps: detecting the air flushing of the loop; step two: sipping the tube for water washing; step three: sipping detection; step four: analyzing the detection data; step five: completing detection; the third step is that: a sipping assay comprising the steps of:
(1) opening the valve V003, the valve V002 and the vacuum pump, evacuating the sipping tube (2), monitoring the pressure indication of the pressure sensor (3) at the same time until the pressure in the sipping tube (2) reaches a set pressure value P1, and closing the valve V003, the valve V002 and the vacuum pump;
(2) standing for a certain time t, opening a valve V003, a valve V002, a vacuum pump, a valve V005, a valve V008 and a valve V006, and circulating radioactive fission gas escaping from the fuel rods by utilizing gas carrying belts in the loop to make the gas in the sipping barrel (2) and the gas in the loop uniformly mixed;
(3) the mixed gas after being uniformly mixed continuously circulates in the loop, the radioactivity of the mixed gas is measured by a radiation detector (5), and the radioactivity of the target nuclide is analyzed and recorded as N1.
2. The method for detecting vacuum sipping of a nuclear fuel assembly of claim 1, wherein: the second step is that: sipping barrel water flush, comprising the steps of:
(1) hoisting the fuel component (1) to be tested in the sipping tube (2) by using a spent fuel pool crane, closing a sealing cover of the sipping tube (2), and sealing the fuel component (1), wherein the periphery of the fuel component is filled with boron-containing water in a spent water pool;
(2) opening the valve V009 and the valve V010, injecting clean water without radioactive water source (7) from the upper part of the sipping barrel (2), and simultaneously draining and replacing from the drain opening at the lower part of the sipping barrel (2), and suggesting that water with n times of the volume of the sipping barrel (2) is injected, wherein n is more than 2; after the water replacement process is finished, closing the valve V009 and the valve V010;
(3) opening the valve V001, the valve V004, the valve V006 and the valve V010, filling non-radioactive gas into the sipping barrel (2), simultaneously draining water from the lower part of the sipping barrel (2), forming a gas space with a certain volume at the upper part of the sipping barrel (2), closing the valve V001, the valve V004, the valve V006 and the valve V010, and detecting the gas background N0 at the moment.
3. The method of claim 1, wherein the off-line sipping inspection of the nuclear fuel assembly comprises: the first step is as follows: detecting a loop gas flush comprising the steps of: opening a valve V001, a valve V002, a valve V004, a valve V005, a valve V007, a valve V008 and a vacuum pump (4), flushing the pipeline and the cavity of the water upper loop system by using non-radioactive gas, monitoring the radioactivity level in the loop by using a radiation detector (5) in the flushing process, stopping the flushing process when the radioactivity in the loop is lower than a determined lowest background radioactivity index, and closing the valve V001, the valve V002, the valve V004, the valve V005, the valve V007, the valve V008 and the vacuum pump (4).
4. The method of claim 2, wherein the off-line sipping inspection method comprises: the fourth step is that: analysis of detection data, comprising the steps of:
(1) comparing N1 with N0, if N1> kN0, judging that the detected fuel assembly (1) is broken; k is a judgment coefficient, the numerical value is 2 to 10, and the judgment coefficient is determined according to the precision of the actual detector;
(2) if kN0 is more than or equal to N1 more than or equal to N0, repeating the operation process of the third step, reducing the pressure value obtained by air suction to P2, wherein P2 is less than P1, and the radioactivity of the sample gas after the measured pressure is reduced to P2 is recorded as N2.
5. The method of claim 4, wherein the off-line sipping inspection of the nuclear fuel assembly comprises: the fourth step is that: the detection data analysis also comprises the following steps:
(1) comparing N2 with N0, and if N2 is more than or equal to kN0, judging that the detected fuel assembly (1) is damaged;
(2) if kN0> N2, it is determined that there is no breakage of the fuel assembly (1).
6. The method of claim 3, wherein the off-line sipping inspection of the nuclear fuel assembly comprises: the fifth step is as follows: completing the detection, further comprising the following steps:
(1) completing the vacuum off-line sipping detection of the fuel assembly, opening all valves except the valve V001 and the valve V007, closing the valve V003 and the valve V006, opening the sipping barrel (2) and hanging out the fuel assembly after the detection system recovers the normal pressure;
(2) and repeating the first step, cleaning the loop system and preparing to perform the next group of nuclear fuel assembly offline sipping detection.
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