CLUSTER OF NUCLEAR FUEL RODS WITH CORROSION RESISTANCE AND ABRASION RESISTANCE

    公开(公告)号:JPH02271291A

    公开(公告)日:1990-11-06

    申请号:JP1342790

    申请日:1990-01-23

    Abstract: PURPOSE: To improve external corrosion resistance and abrasion resistance by constituting a surface layer having a thickness of 10-25% of the entire thickness of a fuel coating wall with a zirconium base alloy containing, in a specified weight ratio, tin, iron, oxygen and niobium or vanadium. CONSTITUTION: A fuel assembly rod far a reactor contains a nuclear fuel material in a fuel coating which contains an internal pipe-like layer and a surface layer, different from each other, of a zirconium allay. Relating to the rod, its surface layer has a thickness of 10-25% of the entire thickness of a fuel coating wall, and constructed of a zirconium base allay comprising tin by 0.35-0.65%, in weight ratio, iron by 0.20-0.65%, oxygen by 0.09-0.162 and niobium by 0.35-0.65% or vanadium by 0.25-0.35%, and, zirconium, separately from an unavoidable impurities, for the remaining portion.

    沸水式反應器之燃料元件中各燃料棒密度之檢測方法 METHOD TO INSPECT THE DENSITY OF THE FUEL-BARS FOR THE FUEL-ELEMENTS OF A BOILING-WATER REACTOR
    3.
    发明专利
    沸水式反應器之燃料元件中各燃料棒密度之檢測方法 METHOD TO INSPECT THE DENSITY OF THE FUEL-BARS FOR THE FUEL-ELEMENTS OF A BOILING-WATER REACTOR 失效
    沸水式反应器之燃料组件中各燃料棒密度之检测方法 METHOD TO INSPECT THE DENSITY OF THE FUEL-BARS FOR THE FUEL-ELEMENTS OF A BOILING-WATER REACTOR

    公开(公告)号:TWI269310B

    公开(公告)日:2006-12-21

    申请号:TW094138740

    申请日:2005-11-04

    IPC: G21C

    Abstract: 本發明涉及一種沸水式反應器之燃料元件(40)中各燃料棒密度之檢測方法,其中多個燃料元件(40)分別相鄰地配置在沸水式反應器之核心上方柵格(10)之一單元(4)中。形成一分區(5)用之多個單元(4)之燃料元件(40)同時加熱且該分區上設有一罩蓋(6)。由此分區(5)之每一單元(4)中取出至少一種水試樣,形成一組(A, B, C)之各單元(4)之水試樣聚集在一起且對水試樣中所含有的分裂性產物之存在性進行檢測。多個組(A, B, C)在分析裝置(14)之與這些組(A, B, C)的數目相等之測量通道(14A, B, C)中同時互相獨立地進行分析,在組(A)中有正的檢測結果時,水試樣由此組(A)中已存在的各單元(4)互相分開地傳送至分析裝置(14)且在數目相等的測量通道(14A, B, C)中互相分開地進行分析,且分析後有正的檢測結果之單元(4)之各燃料元件(40)分別取出至罩蓋(6)之外部以進行檢測。

    Abstract in simplified Chinese: 本发明涉及一种沸水式反应器之燃料组件(40)中各燃料棒密度之检测方法,其中多个燃料组件(40)分别相邻地配置在沸水式反应器之内核上方栅格(10)之一单元(4)中。形成一分区(5)用之多个单元(4)之燃料组件(40)同时加热且该分区上设有一罩盖(6)。由此分区(5)之每一单元(4)中取出至少一种水试样,形成一组(A, B, C)之各单元(4)之水试样聚集在一起且对水试样中所含有的分裂性产物之存在性进行检测。多个组(A, B, C)在分析设备(14)之与这些组(A, B, C)的数目相等之测量信道(14A, B, C)中同时互相独立地进行分析,在组(A)中有正的检测结果时,水试样由此组(A)中已存在的各单元(4)互相分开地发送至分析设备(14)且在数目相等的测量信道(14A, B, C)中互相分开地进行分析,且分析后有正的检测结果之单元(4)之各燃料组件(40)分别取出至罩盖(6)之外部以进行检测。

    具有可變長度銠發射器之中子偵測器組件 NEUTRON DETECTOR ASSEMBLY WITH VARIABLE LENGTH RHODIUM EMITTERS
    4.
    发明专利
    具有可變長度銠發射器之中子偵測器組件 NEUTRON DETECTOR ASSEMBLY WITH VARIABLE LENGTH RHODIUM EMITTERS 失效
    具有可变长度铑发射器之中子侦测器组件 NEUTRON DETECTOR ASSEMBLY WITH VARIABLE LENGTH RHODIUM EMITTERS

    公开(公告)号:TW200632940A

    公开(公告)日:2006-09-16

    申请号:TW095103095

    申请日:2006-01-26

    IPC: G21C

    Abstract: 本發明揭示一種量測一核燃料組件中之中子通量之系統,其包括:置放於一核燃料組件中之至少兩個偵測器,該等偵測器之每一者具有一外戰及一內部發射器,該發射器具有一接受中子且提供一電訊號之結構,該外鞘形成該發射器得以置放於其中之一內積體;一外部導線;及連接至每一發射器之至少一導線,該導線將該訊號自該發射器傳輸至該外部導線,其中該等至少兩個偵測器具有一不同長度。

    Abstract in simplified Chinese: 本发明揭示一种量测一核燃料组件中之中子通量之系统,其包括:置放于一核燃料组件中之至少两个侦测器,该等侦测器之每一者具有一外战及一内部发射器,该发射器具有一接受中子且提供一电信号之结构,该外鞘形成该发射器得以置放于其中之一内积体;一外部导线;及连接至每一发射器之至少一导线,该导线将该信号自该发射器传输至该外部导线,其中该等至少两个侦测器具有一不同长度。

    沸水式反應器之燃料元件用之間隔支件
    6.
    发明专利
    沸水式反應器之燃料元件用之間隔支件 失效
    沸水式反应器之燃料组件用之间隔支件

    公开(公告)号:TW594792B

    公开(公告)日:2004-06-21

    申请号:TW092105349

    申请日:2003-03-12

    IPC: G21C

    Abstract: 一種沸水式反應器之燃料元件用之間隔支件,其各單元(4)由相交配置之內條(2)及以框架形式圍繞內條(2)所用之外條(3)所形成,其具有至少一導引裝置(11),該導引裝置(11)包含一配置在外條(3)中之流通孔(12)及一(在冷卻劑之導流方向(16)中觀看時)配置在該通孔(16)之前且由外條(3)之內側(6)突出之導引元件(13),其依據文杜利管-噴嘴之形式而與該流通孔(12)共同作用。

    Abstract in simplified Chinese: 一种沸水式反应器之燃料组件用之间隔支件,其各单元(4)由相交配置之内条(2)及以框架形式围绕内条(2)所用之外条(3)所形成,其具有至少一导引设备(11),该导引设备(11)包含一配置在外条(3)中之流通孔(12)及一(在冷却剂之导流方向(16)中观看时)配置在该通孔(16)之前且由外条(3)之内侧(6)突出之导引组件(13),其依据文杜利管-喷嘴之形式而与该流通孔(12)共同作用。

    Method of determination of a nuclear core loading pattern

    公开(公告)号:US12254996B2

    公开(公告)日:2025-03-18

    申请号:US17786516

    申请日:2020-12-16

    Applicant: FRAMATOME

    Abstract: A method of determination of a nuclear core loading pattern defining the disposition of fuel assemblies. The method includes defining at least one potential core loading pattern and calculating predictive bowing of the fuel assemblies at the end of the operation cycle for each potential core loading pattern. The calculation is carried out by an automatic learning algorithm trained on a training data set that includes a plurality of other core loading patterns. The set also includes, for each of the other core loading patterns, measurements of bowing of fuel assemblies at the end of operation cycle. The method also includes evaluating the at least one potential core loading pattern based on the predictive bowing calculations and at least one predetermined criteria. The method further includes selecting one of the potential core loading patterns based at least in part on the evaluating.

    Hydrogenation system for a pressurized water reactor

    公开(公告)号:US12243659B2

    公开(公告)日:2025-03-04

    申请号:US17617292

    申请日:2019-07-03

    Applicant: FRAMATOME GmbH

    Abstract: A pressurized water reactor includes a primary reactor coolant circuit flown through by a primary reactor coolant during operation, and a chemical and volume control system for the primary reactor coolant. The chemical and volume control system includes, along the direction of flow of the primary reactor coolant, a letdown line, a high-pressure charging pump with a given discharge pressure, and a charging line leading to the primary reactor coolant circuit. The chemical and volume control system further includes a hydrogenation system with a hydrogen supply and a hydrogen feeding line. In order to achieve efficient and fast hydrogen injection into the primary reactor coolant, a high-pressure feeding pump is arranged in the feeding line to provide a gas pressure higher than the discharge pressure of the charging pump. The feeding line discharges into the charging line.

    Using xenon concentration in controlling a nuclear power plant

    公开(公告)号:US12191044B2

    公开(公告)日:2025-01-07

    申请号:US17784036

    申请日:2019-12-12

    Applicant: FRAMATOME GmbH

    Abstract: A method is for controlling a nuclear power plant comprising a pressurized water nuclear reactor. The method includes determining that an obtained waiting period and/or a remaining waiting period is greater than a first predetermined time allowing raising of a Xenon concentration to maximal value. The method further includes, responsive to the determination, moving one or more control rods out of the reactor core for compensating the reactivity loss due to an increase of the Xenon concentration, and moving the one or more control rods into the reactor core to a control rod setpoint for the start of power ramp up before the end of the obtained waiting period and/or remaining waiting period.

    Method for protecting a nuclear reactor and corresponding nuclear reactor

    公开(公告)号:US12051515B2

    公开(公告)日:2024-07-30

    申请号:US17275424

    申请日:2019-09-12

    Applicant: FRAMATOME

    CPC classification number: G21D3/001 G21C3/047 G21C9/00 G21C17/108

    Abstract: A method for protecting a nuclear reactor includes reconstructing a maximum linear power density released among the fuel rods of the nuclear fuel assemblies of the core; calculating the thermomechanical state and the burnup fraction of the rods; calculating a mechanical stress or deformation energy density in the cladding of one of the rods by using the said reconstructed maximum linear power density, the calculated thermomechanical states and the calculated burnup fractions, by means of a meta-model of a thermomechanical code; comparing the calculated mechanical stress or the calculated deformation energy density with a respective threshold; and stopping the nuclear reactor if the calculated mechanical stress or the calculated deformation energy density exceeds the respective threshold.

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