CN111128419B - Nuclear power plant fuel assembly integrity judgment method - Google Patents
Nuclear power plant fuel assembly integrity judgment method Download PDFInfo
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- CN111128419B CN111128419B CN201911396837.1A CN201911396837A CN111128419B CN 111128419 B CN111128419 B CN 111128419B CN 201911396837 A CN201911396837 A CN 201911396837A CN 111128419 B CN111128419 B CN 111128419B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
- G21C17/07—Leak testing
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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
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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
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- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
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Abstract
The invention belongs to the technical field of nuclear reactor radiochemistry, and particularly relates to a nuclear power plant fuel assembly integrity judgment method. Sampling the main coolant system to analyze gamma nuclide concentration data, including Xe-133, xe-135; dividing the analyzed Xe-133 concentration data by the Xe-135 concentration data to obtain a ratio; the ratio of Xe-133 to Xe-135 in all the main coolant sampling analysis data in the reactor operating cycle is arranged in ascending order from small to large; performing linear fitting on the data after the ascending arrangement to obtain a fitting linear formula and a linear slope of the fitting linear formula; when the ratio of Xe-133/Xe-135 fits a straight line with a slope >0.01, breakage of the fuel assembly occurs; when the Xe-133/Xe-135 ratio fits a straight line slope <0.005, no breakage of the fuel assembly occurred. The method can quickly and accurately judge whether the fuel assembly is damaged.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor radiochemistry, and particularly relates to a nuclear power plant fuel assembly integrity judgment method.
Background
It is a common occurrence of pressurized water reactor nuclear power plant fuel assemblies breakage during operation. Currently, each nuclear power plant is mainly based on processing the radioactive concentration data of a primary coolant sampling and analyzing gamma nuclide and carrying out fuel assembly integrity judgment during the operation of a reactor by combining the operation state of a sampling time group.
1. Fission product release mechanism
During normal reactor operation, when the fuel rod cladding is breached, coolant can enter the fuel through the cladding gap and fission products (such as highly volatile inert gases and radioactive iodine) will be released into the primary system coolant, causing a sudden increase in the radioactivity level of the primary system coolant. Fission product release may be exacerbated as the coolant breaks through the fuel cladding due to the primary system coolant operating pressure being higher than the fuel rod internal gas pressure.
Radioactive iodine release may also occur during reactor shut-down or power changes. When the temperature within the fuel rod is reduced below saturation through cladding cracking, the liquid water in the primary system coolant will dissolve soluble iodine in the fuel cladding cracks, resulting in an "iodine spike" phenomenon. Thereafter, water from the primary system coolant, which is rich in radioactive iodine, will continue to remain in the fuel clad crevices and will be released during subsequent reactor startup.
2. Common method for fuel assembly breakage
The earliest indication of fuel assembly failure is an abnormally high Xe-133 activity. The radioactive iodine activity change is less correlated when the fuel assembly is initially broken, because a small breach or crack in the fuel cladding does not result in a measurable change in iodine concentration at the unit steady state. The "iodine peak" accompanying the power transient is generally considered by the nuclear power plant as a reliable indicator of the occurrence of the fuel assembly breakage, and is also a common method for determining whether the fuel assembly breakage occurs in the nuclear power plant.
3. Power transient presence or absence of iodine peak
A fuel assembly of a certain nuclear power plant 101, 201, 301, 302, 401 for five operating cycles is damaged and a distinct iodine peak is found in the power transient. The 202 cycle fuel assembly had a visible breach, but no significant iodine peak was found at the power transient. Thus, as long as the power transient has an iodine spike, it can be considered that a fuel assembly is broken; the power transient state has no iodine peak, the fuel assembly is not necessarily not damaged, and other parameters are combined for assisting judgment. The method for determining whether a fuel assembly commonly used in a power plant is damaged has certain defects.
Disclosure of Invention
The invention aims to provide a nuclear power plant fuel assembly integrity judgment method, which can be used for timely and accurately judging the integrity of a fuel assembly during the normal operation of a reactor and making up the defects of the traditional fuel assembly damage judgment method.
In order to achieve the purpose, the technical scheme adopted by the invention is as follows:
a nuclear power plant fuel assembly integrity determination method samples a main coolant system for analysis of gamma nuclide concentration data, including Xe-133, xe-135; dividing the analyzed Xe-133 concentration data by the Xe-135 concentration data to obtain a ratio; the ratio of Xe-133 to Xe-135 in all the main coolant sampling analysis data in the reactor operating cycle is arranged in ascending order from small to large; performing linear fitting on the data after the ascending sequence arrangement to obtain a fitting linear formula and a linear slope of the fitting linear formula; when the ratio of Xe-133/Xe-135 fits a straight line with a slope >0.01, breakage of the fuel assembly occurs; when the Xe-133/Xe-135 ratio fits a straight line with a slope <0.005, no breakage of the fuel assembly occurs.
The beneficial effects obtained by the invention are as follows:
the method can quickly and accurately judge whether the fuel assembly is damaged or not. The method is used for independently judging the integrity of fuel assemblies of partial domestic nuclear power plants, and the judgment result is consistent with the final conclusion of the integrity of the fuel assemblies of each power plant; the present method determines fuel assembly integrity conditions that cannot be determined using conventional methods and can lead to fuel assembly integrity conclusions earlier than conventional methods. The slope of a straight line fitted by a ratio Xe-133/Xe-135 of a broken fuel cycle in part of domestic nuclear power plants.
When the U2C2 circulating fuel assembly of the domestic A nuclear power plant is subjected to appearance inspection of the fuel assembly during overhaul of a unit, the fuel assembly is found to be damaged, but when the traditional fuel assembly integrity judgment method is adopted, no obvious iodine peak exists, and the conclusion that whether the fuel assembly is damaged or not can not be given. The method can obtain the ratio of Xe-133/Xe-135, the slope of the fitted straight line is 0.0106, the condition that the fuel assembly is damaged is met, and the fuel assembly is judged to be damaged.
When the data of the U3C3 circulation main coolant inert gas of the domestic A nuclear power plant is abnormal, the radioactive iodine equivalent does not have an obvious iodine peak when the unit power is transient, and whether a fuel assembly is damaged or not can not be judged by using a traditional method. The slope of a fitted straight line of the Xe-133/Xe-135 ratio obtained by using the method is 0.0402, meets the condition that the fuel assembly is damaged given by the method, and judges that the fuel assembly is damaged. The cycle also showed a significant iodine peak at month 4 after the conclusion of fuel assembly breakage was made by the present method, which also concluded that fuel assembly breakage occurred using conventional methods.
In the U4C3 fuel circulation of the domestic F nuclear power plant, partial inert gas data are abnormal in the down stage of unit overhaul, but no iodine peak appears. With the conventional method, it is impossible to determine whether the fuel assembly is broken. The slope of a fitted straight line of the Xe-133/Xe-135 ratio obtained by the method is 13.42, meets the condition that the fuel assembly is damaged given by the method, and judges that the fuel assembly is damaged.
Detailed Description
The present invention will be described in detail with reference to specific examples.
The integrity judgment method for the nuclear power plant fuel assembly comprises the following steps:
the main coolant system is sampled to analyze gamma species concentration data, including Xe-133, xe-135. The analyzed Xe-133 concentration data is divided by the Xe-135 concentration data to obtain a ratio. The Xe-133 and Xe-135 ratios in all the primary coolant sampling analysis data over the reactor operating period are ordered in ascending order from small to large. And performing linear fitting on the data after the ascending sequence arrangement to obtain a fitting linear formula and a linear slope of the fitting linear formula. When the ratio of Xe-133/Xe-135 fits a straight line with a slope >0.01, breakage of the fuel assembly occurs; when the Xe-133/Xe-135 ratio fits a straight line with a slope <0.005, no breakage of the fuel assembly occurs.
Claims (1)
1. A nuclear power plant fuel assembly integrity determination method is characterized by comprising the following steps: sampling the main coolant system to analyze gamma nuclide concentration data, including Xe-133, xe-135; dividing the analyzed Xe-133 concentration data by the Xe-135 concentration data to obtain a ratio; the ratio of Xe-133 to Xe-135 in all the main coolant sampling analysis data in the reactor operating period is arranged in ascending order from small to large; performing linear fitting on the data after the ascending sequence arrangement to obtain a fitting linear formula and a linear slope of the fitting linear formula; when the ratio of Xe-133/Xe-135 fits a straight line with a slope >0.01, breakage of the fuel assembly occurs; when the Xe-133/Xe-135 ratio fits a straight line with a slope <0.005, no breakage of the fuel assembly occurs.
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| CN201911396837.1A CN111128419B (en) | 2019-12-30 | 2019-12-30 | Nuclear power plant fuel assembly integrity judgment method |
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| CN201911396837.1A CN111128419B (en) | 2019-12-30 | 2019-12-30 | Nuclear power plant fuel assembly integrity judgment method |
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| CN111128419B true CN111128419B (en) | 2023-01-24 |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN113782238A (en) * | 2020-06-09 | 2021-12-10 | 中核武汉核电运行技术股份有限公司 | Method for identifying fuel assembly damage by on-line sipping |
| CN113571213B (en) * | 2021-06-23 | 2024-03-22 | 中国原子能科学研究院 | Method for detecting neptunium target integrity in irradiation process |
| CN113358076A (en) * | 2021-07-09 | 2021-09-07 | 中国工程物理研究院机械制造工艺研究所 | Wedge block assembly detection device and method |
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| JPS5574495A (en) * | 1978-11-24 | 1980-06-05 | Commissariat Energie Atomique | Method of detecting and measuring failure characteristic of reactor fuel cladding |
| US4759902A (en) * | 1986-10-07 | 1988-07-26 | Advanced Process Technology | Use of electrochemical potential to predict radiation buildup on nuclear reactor coolant piping |
| EA201001590A1 (en) * | 2010-10-06 | 2012-02-28 | Зао "Диаконт" | METHOD FOR AUTOMATED CONTROL OF LEAKAGE THERMAL-RELATING ASSEMBLY OF THE REACTOR IN OVERLOAD AND SYSTEM FOR ITS IMPLEMENTATION |
| CN109346198A (en) * | 2018-09-18 | 2019-02-15 | 深圳中广核工程设计有限公司 | A kind of fuel for nuclear power plant clad failure diagnostic system and its diagnostic method |
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| NL269759A (en) * | 1961-03-04 | |||
| US3278386A (en) * | 1964-08-14 | 1966-10-11 | James E French | Delay bed system for purification of nuclear fuel element purge stream |
| US4080250A (en) * | 1973-11-20 | 1978-03-21 | The United States Of America As Represented By The United States Department Of Energy | Method of locating a leaking fuel element in a fast breeder power reactor |
| CN109615110B (en) * | 2018-11-13 | 2022-12-13 | 中国原子能科学研究院 | Fast reactor core coolant flow partitioning method |
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| JPS5574495A (en) * | 1978-11-24 | 1980-06-05 | Commissariat Energie Atomique | Method of detecting and measuring failure characteristic of reactor fuel cladding |
| US4759902A (en) * | 1986-10-07 | 1988-07-26 | Advanced Process Technology | Use of electrochemical potential to predict radiation buildup on nuclear reactor coolant piping |
| EA201001590A1 (en) * | 2010-10-06 | 2012-02-28 | Зао "Диаконт" | METHOD FOR AUTOMATED CONTROL OF LEAKAGE THERMAL-RELATING ASSEMBLY OF THE REACTOR IN OVERLOAD AND SYSTEM FOR ITS IMPLEMENTATION |
| CN109346198A (en) * | 2018-09-18 | 2019-02-15 | 深圳中广核工程设计有限公司 | A kind of fuel for nuclear power plant clad failure diagnostic system and its diagnostic method |
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