Abstract in simplified Chinese:本发明提供定位于一核反应器中之至少两个电化学感应器,其中该等至少两个电化学感应器中之至少一个具有一锆电极,且对于在其上安装每一该等至少两个电化学感应器的表面,该等至少两个电化学感应器产生与电化学腐蚀电位成比例之电压。本发明亦提供一配置,其经设置以接收借由该等至少两个电化学感应器所产生之电压,其中设置该配置以基于该等至少两个电化学感应器之电压来测定该核反应器中一锆燃料杆之电化学腐蚀电位。
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.
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。
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。
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.
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.
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.
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.