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1.发明申请Temperature Detection Apparatus For Natural Circulation Boiling Water Reactor 审中-公开自然循环沸腾水反应器温度检测装置公开(公告)号：US20100195782A1
公开(公告)日：2010-08-05
申请号：US12759265
申请日：2010-04-13
IPC分类号： G21C17/112
CPC分类号： G21C17/112
摘要： A natural circulation boiling water reactor includes a reactor pressure vessel, a chimney including a lattice member and arranged above a core in said reactor pressure vessel, and a plurality of thermocouple extension wire pulling conduits into which at least one temperature detection thermocouple and at least one cable connected to the temperature detection thermocouple are inserted. At least one of thermocouple extension wire pulling conduits is disposed on an upper end surface of the lattice member and is directly mounted to the upper end surface of the lattice member.
摘要翻译： 天然循环沸水反应器包括反应堆压力容器，包括晶格构件并且布置在所述反应堆压力容器中的核心上方的烟囱以及多个热电偶延长线拉动管道，至少一个温度检测热电偶和至少一个温度检测热电偶 插入连接到温度检测热电偶的电缆。 热电偶延长线拉拔管道中的至少一个设置在格子部件的上端面上，并直接安装在格子部件的上端面上。
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2.发明申请Temperature Detection Apparatus For Natural Circulation Boiling Water Reactor 审中-公开自然循环沸腾水反应器温度检测装置公开(公告)号：US20090052604A1
公开(公告)日：2009-02-26
申请号：US12250762
申请日：2008-10-14
IPC分类号： G21C17/112
CPC分类号： G21C17/112
摘要： A natural circulation boiling water reactor includes a reactor pressure vessel, a chimney including a lattice member and arranged above a core in the reactor pressure vessel, and at least one thermocouple extension wire pulling conduit into which a temperature detection thermocouple and a cable connected to said temperature detection thermocouple are inserted. The thermocouple extension wire pulling conduit is disposed on an upper end surface of the lattice member and mounted to the upper end surface of the lattice member.
摘要翻译： 自然循环沸水反应器包括反应堆压力容器，包括晶格构件的烟囱，并且布置在反应堆压力容器中的核心上方，以及至少一个热电偶延长线拉动管道，温度检测热电偶和连接到所述 插入温度检测热电偶。 热电偶延长线牵引导管设置在格子部件的上端面上，安装于格子部件的上端面。
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3.发明申请TEMPERATURE DETECTION APPARATUS FOR NATURAL CIRCULATION BOILING WATER REACTOR 审中-公开自然循环锅炉水反应器温度检测装置公开(公告)号：US20070201606A1
公开(公告)日：2007-08-30
申请号：US11678740
申请日：2007-02-26
IPC分类号： G21C15/00
CPC分类号： G21C17/112
摘要： A chimney lattice is arranged in a reactor pressure vessel. Thermocouple extension wire pulling conduits inserting a temperature detection thermocouple and a cable connected to the thermocouple are mounted to the upper end of the chimney lattice. By mounting the thermocouple extension wire pulling conduit on the upper end of the chimney lattice, the thermocouple extension wire pulling conduit does not become an obstacle when the fuel assembly is taken out from the chimney. Because the thermocouple extension wire pulling conduit is installed at the upper end of the chimney, the replacement of the thermocouple damaged is easy.
摘要翻译： 烟囱格子布置在反应堆压力容器中。 插入温度检测热电偶和连接到热电偶的电缆的热电偶延长线牵引导管安装在烟囱格栅的上端。 通过将热电偶延长线拉出管道安装在烟囱格栅的上端，当燃料组件从烟囱中取出时，热电偶延长线拉拔管道不会成为障碍物。 由于热电偶延长线拉拔管道安装在烟囱的上端，所以热电偶损坏的更换变得容易。
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公开(公告)号：US20110200155A1
公开(公告)日：2011-08-18
申请号：US13005928
申请日：2011-01-13
申请人： Atsushi Fushimi , Setsuo Arita , Yoshihiko Ishii , Tomohiko Ikegawa , Shin Hasegawa , Kazuhiko Ishii
发明人： Atsushi Fushimi , Setsuo Arita , Yoshihiko Ishii , Tomohiko Ikegawa , Shin Hasegawa , Kazuhiko Ishii
摘要： In order to stably control a nuclear reactor in a short time, so as not to enter an unstable region that is determined by the relationship between the reactor pressure, the reactor power and the subcooling of the core inlet coolant at start-up time, the nuclear reactor system comprises: an power control apparatus for generating a control rod operation signal for operating a control rod, based on the reactor water temperature change rate; a feed water control apparatus for generating a feed water flow rate signal and a discharge water flow rate signals based on the reactor water level signal; and a process computer for performing overall control of the power control apparatus and the feed water control apparatus, wherein the feed water control apparatus has the reactor water temperature change rate setting section for adjusting the reactor water temperature change rate set value based on the variation of the reactor water level signal.
摘要翻译： 为了在短时间内稳定地控制核反应堆，为了不进入由反应堆压力，反应堆功率和启动时的核心入口冷却剂的过冷度之间的关系确定的不稳定区域， 核反应堆系统包括：功率控制装置，用于基于反应堆水温度变化率产生用于操作控制棒的控制棒操作信号; 用于产生基于反应堆水位信号的给水流量信号和排放水流量信号的给水控制装置; 以及用于执行动力控制装置和给水控制装置的整体控制的处理计算机，其中，给水控制装置具有反应堆水温变化率设定部，其用于基于变化而调整反应堆水温变化率设定值 反应堆水位信号。
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公开(公告)号：US20100272223A1
公开(公告)日：2010-10-28
申请号：US11657456
申请日：2007-01-25
申请人： Atsushi Fushimi , Setsuo Arita , Yoshihiko Ishii , Tomohiko Ikegawa , Shin Hasegawa , Kazuhiko Ishii
发明人： Atsushi Fushimi , Setsuo Arita , Yoshihiko Ishii , Tomohiko Ikegawa , Shin Hasegawa , Kazuhiko Ishii
摘要： In order to stably control a nuclear reactor in a short time, so as not to enter an unstable region that is determined by the relationship between the reactor pressure, the reactor power and the subcooling of the core inlet coolant at start-up time, the nuclear reactor system comprises: an power control apparatus for generating a control rod operation signal for operating a control rod, based on the reactor water temperature change rate; a feed water control apparatus for generating a feed water flow rate signal and a discharge water flow rate signals based on the reactor water level signal; and a process computer for performing overall control of the power control apparatus and the feed water control apparatus, wherein the feed water control apparatus has the reactor water temperature change rate setting section for adjusting the reactor water temperature change rate set value based on the variation of the reactor water level signal.
摘要翻译： 为了在短时间内稳定地控制核反应堆，为了不进入由反应堆压力，反应堆功率和启动时的核心入口冷却剂的过冷度之间的关系确定的不稳定区域， 核反应堆系统包括：功率控制装置，用于基于反应堆水温度变化率产生用于操作控制棒的控制棒操作信号; 用于产生基于反应堆水位信号的给水流量信号和排放水流量信号的给水控制装置; 以及用于执行动力控制装置和给水控制装置的整体控制的处理计算机，其中，给水控制装置具有反应堆水温变化率设定部，其用于基于变化而调整反应堆水温变化率设定值 反应堆水位信号。
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公开(公告)号：US08363776B2
公开(公告)日：2013-01-29
申请号：US10804112
申请日：2004-03-19
申请人： Renzou Takeda , Motoo Aoyama , Junichi Miwa , Tomohiko Ikegawa , Kumiaki Moriya
发明人： Renzou Takeda , Motoo Aoyama , Junichi Miwa , Tomohiko Ikegawa , Kumiaki Moriya
IPC分类号： G21C3/32
摘要： A ratio of the number of fuel assemblies loaded on a core to the number of control rod drive mechanisms is 3 or more. The fuel assembly itself contains mixed oxides of a low enrichment concentration uranium oxide containing 3 to 8 wt % in the average enrichment concentration of the fuel assembly, or mixed oxide containing not less than 2 wt %, but less than 6 wt % in the average enrichment concentration of fissile plutonium of. In the burner type BWR core on which the fuel assemblies are loaded, an average weight density of uranium, plutonium and minor actinides is 2.1 to 3.4 kg/L as a conversion at the value of unburned state.
摘要翻译： 加载在核心上的燃料组件的数量与控制棒驱动机构的数量的比率为3以上。 燃料组件本身含有燃料组合物的平均富集浓度为3〜8重量％的低浓度浓度铀氧化物的混合氧化物，或平均浓度为2重量％以上但小于6重量％的混合氧化物 易裂变钚的浓缩浓度。 在装有燃料组件的燃烧器型BWR铁心中，作为未燃烧状态值的转化率，铀，钚和次锕系元素的平均重量密度为2.1〜3.4kg / L。
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公开(公告)号：US20130003908A1
公开(公告)日：2013-01-03
申请号：US10804112
申请日：2004-03-19
申请人： Renzou Takeda , Motoo Aoyama , Junichi Miwa , Tomohiko Ikegawa , Kumiaki Moriya
发明人： Renzou Takeda , Motoo Aoyama , Junichi Miwa , Tomohiko Ikegawa , Kumiaki Moriya
IPC分类号： G21C1/08
摘要： A ratio of the number of fuel assemblies loaded on a core to the number of control rod drive mechanisms is 3 or more. The fuel assembly itself contains mixed oxides of a low enrichment concentration uranium oxide containing 3 to 8 wt % in the average enrichment concentration of the fuel assembly, or mixed oxide containing not less than 2 wt %, but less than 6 wt % in the average enrichment concentration of fissile plutonium of. In the burner type BWR core on which the fuel assemblies are loaded, an average weight density of uranium, plutonium and minor actinides is 2.1 to 3.4 kg/L as a conversion at the value of unburned state.
摘要翻译： 加载在核心上的燃料组件的数量与控制棒驱动机构的数量的比率为3以上。 燃料组件本身含有燃料组合物的平均富集浓度为3〜8重量％的低浓度浓度铀氧化物的混合氧化物，或平均浓度为2重量％以上但小于6重量％的混合氧化物 易裂变钚的浓缩浓度。 在装有燃料组件的燃烧器型BWR铁心中，作为未燃烧状态值的转化率，铀，钚和次锕系元素的平均重量密度为2.1〜3.4kg / L。
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公开(公告)号：US20060210009A1
公开(公告)日：2006-09-21
申请号：US11376415
申请日：2006-03-16
申请人： Renzou Takeda , Motoo Aoyama , Junichi Miwa , Tomohiko Ikegawa , Kumiaki Moriya
发明人： Renzou Takeda , Motoo Aoyama , Junichi Miwa , Tomohiko Ikegawa , Kumiaki Moriya
IPC分类号： G21G1/06
摘要： A ratio of the number of fuel assemblies loaded on a core to the number of control rod drive mechanisms is 3 or more. The fuel assembly itself contains mixed oxides of a low enrichment concentration uranium oxide containing 3 to 8 wt % in the average enrichment concentration of the fuel assembly, or mixed oxide containing not less than 2 wt %, but less than 6 wt % in the average enrichment concentration of fissile plutonium of. In the burner type BWR core on which the fuel assemblies are loaded, an average weight density of uranium, plutonium and minor actinides is 2.1 to 3.4 kg/L as a conversion at the value of unburned state.
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公开(公告)号：US07349518B2
公开(公告)日：2008-03-25
申请号：US11376415
申请日：2006-03-16
申请人： Renzou Takeda , Motoo Aoyama , Junichi Miwa , Tomohiko Ikegawa , Kumiaki Moriya
发明人： Renzou Takeda , Motoo Aoyama , Junichi Miwa , Tomohiko Ikegawa , Kumiaki Moriya
IPC分类号： G21C3/32
摘要： A ratio of the number of fuel assemblies loaded on a core to the number of control rod drive mechanisms is 3 or more. The fuel assembly itself contains mixed oxides of a low enrichment concentration uranium oxide containing 3 to 8 wt % in the average enrichment concentration of the fuel assembly, or mixed oxidecontaining not less than 2 wt %, but less than 6 wt % in the average enrichment concentration of fissile plutonium of. In the burner type BWR core on which the fuel assemblies are loaded, an average weight density of uranium, plutonium and minor actinides is 2.1 to 3.4 kg/L as a conversion at the value of unburned state.
摘要翻译： 加载在核心上的燃料组件的数量与控制棒驱动机构的数量的比率为3以上。 燃料组件本身含有燃料组合物的平均富集浓度为3〜8重量％的低浓度浓度铀氧化物的混合氧化物，或平均浓度为2重量％以上但小于6重量％的混合氧化物 易裂变钚的浓缩浓度。 在装有燃料组件的燃烧器型BWR铁心中，作为未燃烧状态值的转化率，铀，钚和次锕系元素的平均重量密度为2.1〜3.4kg / L。
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