Method for prediction of light water reactor fuel defects using a fuel condition index
원문보기
IPC분류정보
국가/구분
United States(US) Patent
등록
국제특허분류(IPC7판)
G21C-017/07
G21C-007/06
출원번호
US-0259955
(2014-04-23)
등록번호
US-9472311
(2016-10-18)
발명자
/ 주소
Pop, Mihai G. M.
Lockamon, Brian Glenn
출원인 / 주소
AREVA Inc.
대리인 / 주소
Davidson, Davidson & Kappel, LLC
인용정보
피인용 횟수 :
0인용 특허 :
32
초록▼
A method to assess light water reactor fuel integrity is presented having the steps of granting access in a nuclear reactor fuel pool to at least one of a discharged fuel rod and a nuclear fuel assembly, calculating an operating flux for the fuel rod, measuring a thickness of CRUD on the fuel rod, m
A method to assess light water reactor fuel integrity is presented having the steps of granting access in a nuclear reactor fuel pool to at least one of a discharged fuel rod and a nuclear fuel assembly, calculating an operating flux for the fuel rod, measuring a thickness of CRUD on the fuel rod, measuring a thickness of oxide on the fuel rod, calculating a maximized flux for the at least one fuel rod for a position of the one fuel rod in a nuclear reactor, calculating a maximized deposit for the fuel rod, calculating a maximized oxide thickness for the fuel rod, calculating a fuel condition index of the fuel rod, comparing the fuel condition index to an index constant, and removing the fuel rod from operation when the fuel condition index is greater than the index constant.
대표청구항▼
1. A method to assess light water reactor fuel integrity after a given time of operation of the light water reactor, the method comprising: granting access in a nuclear reactor fuel pool to at least one of a discharged fuel rod and a discharged nuclear fuel assembly, wherein the at least one dischar
1. A method to assess light water reactor fuel integrity after a given time of operation of the light water reactor, the method comprising: granting access in a nuclear reactor fuel pool to at least one of a discharged fuel rod and a discharged nuclear fuel assembly, wherein the at least one discharged fuel rod or discharged nuclear fuel assembly experienced a heat flux;determining the heat flux experienced by the at least one discharged fuel rod or discharged nuclear fuel assembly;measuring a thickness of oxide on the at least one discharged fuel rod or discharged nuclear fuel assembly;determining a maximum possible heat flux for the at least one discharged fuel rod or discharged nuclear fuel assembly for a position of the at least one discharged fuel rod or discharged nuclear fuel assembly in the light water reactor on a life of the nuclear fuel assembly;determining a Deposit Factor for CRUD on the at least one discharged fuel rod or discharged nuclear fuel assembly, the Deposit Factor being a value that increases with an amount of CRUD on the at least one discharged fuel rod or discharged nuclear fuel assembly;determining a maximum possible oxide thickness for the at least one discharged fuel rod or discharged nuclear fuel assembly in the light water reactor;calculating a fuel condition index of the at least one discharged fuel rod or discharged nuclear fuel assembly in a calculation comprising calculating a ratio of the experienced heat flux to the maximum possible heat flux, and calculating a ratio of the measured oxide thickness to the maximum possible oxide thickness, the fuel condition index being based on the ratio of the experienced heat flux to the maximum possible heat flux, the ratio of the measured oxide thickness to the maximum possible oxide thickness and the value of the Deposit Factor;comparing the fuel condition index to an index constant; andremoving the at least one of the discharged fuel rod and the discharged nuclear fuel assembly from operation when the fuel condition index is greater than the index constant. 2. The method according to claim 1, wherein the fuel condition index is calculated as: [(PeakAssyFluxMaximumFlux)B+DepositFactor+(OperatingOxideThicknessMaximumOxideThickness)D]=FCIwhere B is a flow adjustment factor, D is a fuel design adjustment factor,FCI is the fuel condition index,Peak Assy Flux is the experienced peak operating heat flux,Maximum Flux is the maximum possible heat flux,Operating Oxide Thickness is the measured oxide thickness,Maximum Oxide Thickness is the maximum possible oxide thickness, andDeposit Factor is the value of the Deposit Factor. 3. The method according to claim 2, wherein the flow adjustment factor and the fuel design adjustment factor each have values between 0.3 to 1.4. 4. The method according to claim 1, wherein the index constant has a value determined as a function of a size of a safety margin, the safety margin being a percentage that with an increasing value decreases the value of the index constant. 5. The method according to claim 4, wherein the index constant has a value of 3.0 when the value of the safety margin is 0%. 6. The method according to claim 1, wherein the light water reactor is identified as being high, medium or low risk based on the calculated fuel condition index, a value above a first threshold indicating a high risk, a value below the first threshold and above a second threshold that is lower than the first threshold indicating a medium risk and value below the second threshold indicating a low risk. 7. The method according to claim 1, wherein the light water reactor is one of a boiling water reactor and a pressurized water reactor. 8. The method according to claim 1, wherein determining the Deposit Factor includes visually examining the amount of CRUD on the at least one discharged fuel rod or discharged nuclear fuel assembly. 9. The method according to claim 8, wherein determining the Deposit Factor includes determining the Deposit Factor for CRUD on the discharged nuclear fuel assembly, the determining the Deposit Factor including comparing amounts of CRUD deposited on at least two different components of the discharged nuclear fuel assembly. 10. The method according to claim 9, wherein the at least two different components include a fuel rod of the discharged nuclear fuel assembly and a spacer grid of the discharged nuclear fuel assembly.
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