Evaluation Method for Steam Generator Tube Bundle Wear
A steam generator, a technology to be evaluated, applied in the direction of testing wear resistance, etc., can solve the problem of not evaluating the wear state of the tube bundle and needs further research and clarification, and achieve the effect of extending service life and ensuring heat exchange efficiency
Active Publication Date: 2021-03-02
LINGDONG NUCLEAR POWER +3
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Problems solved by technology
There are certain problems in the above pipe plugging criteria: (1) There are differences between the tube bundle materials, steam generator design specifications and service conditions, and eddy current detection technology of nuclear power units in my country and the assumed conditions of the above pipe plugging criteria. The applicability of nuclear power units needs to be further studied and clarified; (2) The above tube plugging criterion only compares the eddy current test results of the current overhaul with the minimum allowable wall thickness, and does not evaluate the wear state of the tube bundle in the next operating cycle
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[0118] 1. Basic information of heat transfer tube:
[0119] a) Size information: wall thickness 1mm, outer diameter 19mm;
[0120] b) Material information: yield strength S y : 250MPa, tensile strength S u : 650MPa;
[0121] c) Geometric structure: supporting structure thickness 8mm;
[0122] d) Operating parameters: Effective full power year between this overhaul and last overhaul: 3EFPY, NOPD=11MPa, LAPD=17MPa, PL=18MPa, ASL=8MPa;
[0123] e) Related uncertainty: Yield strength uncertainty σ y 15MPa, tensile strength uncertainty σ u 25MPa, wear defect depth uncertainty σ h 3% TW, function uncertainty σ P , 1.94MPa;
[0124] 2. Acceptance criteria:
[0125] a)P L =Max(3NOPD, 1.4LAPD, 1.2PL+1.0ASL)=33MPa
[0126] 3. Detection data collection:
[0127] a) In this embodiment, eddy current testing is used for data collection of heat transfer tubes.
[0128] 4. Condition Monitoring Evaluation
[0129] a) Substituting the relevant parameters into the formula (1-1), u...
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Abstract
The invention relates to the technical field of steam generator aging evaluation, in particular to a steam generator pipe bundle wear evaluation method. The method includes following steps: determining basic information of a to-be-evaluated heat transfer pipe; selecting applicable acceptance criteria according to design criteria and stress analysis report of the heat transfer pipe; determining wear defect depth h and wear defect length L of the to-be-evaluated heat transfer pipe; performing state monitoring evaluation on the to-be-evaluated heat transfer pipe. The evaluation method can realizestate monitoring evaluation of the to-be-evaluated heat transfer pipe, a prediction result of running evaluation after a previous maintenance period is finished can be verified during state monitoring, effectiveness of the running evaluation method can be judged, and guidance can be provided for formulating the running evaluation method. The evaluation method is of quite important value for reasonably controlling pipe blockage rate of a steam generator, ensuring heat exchange efficiency of the steam generator and prolonging service life of the steam generator.
Description
technical field [0001] The invention relates to the technical field of aging evaluation of steam generators, in particular to a method for evaluating the wear of steam generator tube bundles. Background technique [0002] The steam generator is one of the core main equipment of the pressurized water reactor nuclear power plant. It is mainly used as a heat exchanger to transfer the heat in the coolant of the primary circuit to the feed water of the secondary circuit, and generate saturated steam to supply the power plant of the secondary circuit. The tube bundle is composed of thousands of heat transfer tubes, which is the most critical heat exchange part of the steam generator. At the same time, as an important part of the pressure boundary of the primary circuit (the pressure bearing area accounts for about 80%), it is also an important safety barrier to prevent radioactive leakage. The heat transfer tube will be worn at the support structure during service. When the wear d...
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IPC IPC(8): G01N3/56
CPCG01N3/56
Inventor 梅金娜蔡振韩姚磊张国栋王春辉安英辉李平仁薛飞
Owner LINGDONG NUCLEAR POWER