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    • 1. 发明申请
    • Core of a Boiling Water Reactor
    • 沸水堆的核心
    • US20090196391A1
    • 2009-08-06
    • US12026634
    • 2008-02-06
    • Junichi MiwaRenzo TakedaTakeshi MitsuyasuKumiaki Moriya
    • Junichi MiwaRenzo TakedaTakeshi MitsuyasuKumiaki Moriya
    • G21C19/28
    • G21C3/326G21C5/00Y02E30/31Y02E30/38
    • A core of a boiling water reactor as a burner type core of the boiling water reactor having a ratio of 3 or more of number of fuel assemblies loaded in the core to number of control rods installed in the nuclear reactor and using an oxide of low enriched uranium having a mean enrichment of the fuel assemblies of 3 wt % to 8 wt % or a mixed oxide having a mean fissile plutonium enrichment of the fuel assemblies of 2 wt % to less than 7 wt %,wherein a mean weight of at least one of uranium and plutonium included in a unit volume of a core region is 2.25 to 3.4 kg/l when load of the fuel assemblies having a burnup of 0 into the core is finished, anda mean thickness of the channel box of the fuel assemblies is 2.10 to 3.55 mm.
    • 作为沸水反应器的燃烧器型核心的沸水反应堆的核心,其中装载在核心中的燃料组件的数量与安装在核反应堆中的控制棒的数量的比例为3以上,并且使用低浓度的氧化物 具有3重量%至8重量%的燃料组件的平均富集的铀或燃料组件的平均裂变钚富集浓度为2重量%至小于7重量%的混合氧化物,其中平均重量为至少一个 包含在核心区域的单位体积中的铀和钚的总量为2.25至3.4kg / l,当燃料组件的燃料组件的负荷为零时,完成燃料组件的通道箱的平均厚度为 2.10到3.55毫米。
    • 3. 发明申请
    • Core of Light Water Reactor and Fuel Assembly
    • 轻水反应堆和燃料组件的核心
    • US20120177169A1
    • 2012-07-12
    • US13411091
    • 2012-03-02
    • Renzo TakedaJunichi MiwaKumiaki Moriya
    • Renzo TakedaJunichi MiwaKumiaki Moriya
    • G21C7/00G21C3/30
    • G21C3/326G21C3/42G21C2003/3267Y02E30/38
    • A core of a light water reactor having a plurality of fuel assemblies, which are loaded in said core, having nuclear fuel material containing a plurality of isotopes of transuranium nuclides, an upper blanket zone, a lower blanket zone, and a fissile zone, in which the transuranium nuclides are contained, disposed between the upper blanket zone and the lower blanket zone, wherein a ratio of Pu-239 in all the transuranium nuclides contained in the loaded fuel assembly is in a range of 40 to 60% when burnup of the fuel assembly is 0, sum of a height of the lower blanket zone and a height of the upper blanket zone is in a range of 250 to 600 mm, and the height of said lower blanket zone is in a range of 1.6 to 12 times the height of the upper blanket zone.
    • 具有多个燃料组件的轻水反应堆的核心,其装载在所述芯体中,具有含有多个氮氧化物的多个同位素的核燃料材料,上覆层区域,下覆盖区域和裂变区域 其中包含超氧化物核素,其设置在上覆盖区域和下覆盖层区域之间,其中,当燃烧所述载体燃料组件时,包含在所述负载的燃料组件中的所有经核素核素中的Pu-239的比例在40至60%的范围内 燃料组件为0,下橡皮布区域的高度与上覆层区域的高度之和在250至600mm的范围内,并且所述下橡皮布区域的高度在1.6至12倍的范围内 上层毯的高度。
    • 4. 发明授权
    • Core of light water reactor and fuel assembly
    • 轻水反应堆和燃料组件的核心
    • US08571166B2
    • 2013-10-29
    • US13411091
    • 2012-03-02
    • Renzo TakedaJunichi MiwaKumiaki Moriya
    • Renzo TakedaJunichi MiwaKumiaki Moriya
    • G21C3/00
    • G21C3/326G21C3/42G21C2003/3267Y02E30/38
    • A core of a light water reactor having a plurality of fuel assemblies, which are loaded in said core, having nuclear fuel material containing a plurality of isotopes of transuranium nuclides, an upper blanket zone, a lower blanket zone, and a fissile zone, in which the transuranium nuclides are contained, disposed between the upper blanket zone and the lower blanket zone, wherein a ratio of Pu-239 in all the transuranium nuclides contained in the loaded fuel assembly is in a range of 40 to 60% when burnup of the fuel assembly is 0, sum of a height of the lower blanket zone and a height of the upper blanket zone is in a range of 250 to 600 mm, and the height of said lower blanket zone is in a range of 1.6 to 12 times the height of the upper blanket zone.
    • 具有多个燃料组件的轻水反应堆的核心,其装载在所述芯体中,具有含有多个氮氧化物的多个同位素的核燃料材料,上覆层区域,下覆盖区域和裂变区域 其中包含超氧化物核素,其设置在上覆盖区域和下覆盖层区域之间,其中,当燃烧所述载体燃料组件时,包含在所述负载的燃料组件中的所有经核素核素中的Pu-239的比例在40至60%的范围内 燃料组件为0,下橡皮布区域的高度与上覆层区域的高度之和在250至600mm的范围内,并且所述下橡皮布区域的高度在1.6至12倍的范围内 上层毯的高度。
    • 5. 发明授权
    • Core of light water reactor and fuel assembly
    • 轻水反应堆和燃料组件的核心
    • US08422617B2
    • 2013-04-16
    • US12537452
    • 2009-08-07
    • Renzo TakedaJunichi MiwaKumiaki Moriya
    • Renzo TakedaJunichi MiwaKumiaki Moriya
    • G21C1/04
    • G21C3/326G21C3/42G21C2003/3267Y02E30/38
    • A core of a light water reactor having a plurality of fuel assemblies, which are loaded in said core, having nuclear fuel material containing a plurality of isotopes of transuranium nuclides, an upper blanket zone, a lower blanket zone, and a fissile zone, in which the transuranium nuclides are contained, disposed between the upper blanket zone and the lower blanket zone; wherein a ratio of Pu-239 in all the transuranium nuclides contained in the loaded fuel assembly is in a range of 40 to 60% when burnup of the fuel assembly is 0; sum of a height of the lower blanket zone and a height of the upper blanket zone is in a range of 250 to 600 mm; and the height of said lower blanket zone is in a range of 1.6 to 12 times the height of the upper blanket zone.
    • 具有多个燃料组件的轻水反应堆的核心,其装载在所述芯体中,具有含有多个氮氧化物的多个同位素的核燃料材料,上覆层区域,下覆盖区域和裂变区域 其中包含超氧化物核素,设置在上覆盖区域和下覆盖区域之间; 其中,当所述燃料组件的燃耗为0时,包含在所述装载的燃料组件中的所有超铀核素中的Pu-239的比率在40至60%的范围内; 下橡皮布区域的高度和上覆层区域的高度之和在250至600mm的范围内; 并且所述下覆盖带的高度在上毯区的高度的1.6至12倍的范围内。
    • 6. 发明授权
    • Core of light water reactor and fuel assembly
    • 轻水反应堆和燃料组件的核心
    • US09047994B2
    • 2015-06-02
    • US12978198
    • 2010-12-23
    • Renzo TakedaJunichi MiwaKumiaki Moriya
    • Renzo TakedaJunichi MiwaKumiaki Moriya
    • G21C1/04G21C19/44G21C3/328G21C5/00
    • G21C3/328G21C1/084G21C3/42G21C5/00G21C5/02G21C19/44Y02E30/38Y02W30/882
    • A core of a light water reactor has a plurality of fuel assemblies. The fuel assemblies include a plurality of fuel rods in which a lower end is supported by a lower tie-plate and an upper end is supported by an upper tie-plate. The fuel rods form plenums above a nuclear fuel material zone and have a neutron absorbing material filling zone under the nuclear fuel material zone. Neutron absorbing members attached to the upper tie-plate are disposed between mutual plenums of the neighboring fuel rods above the nuclear fuel material zone. The neutron absorbing members have a length of 500 mm and are positioned at a distance of 300 mm from the nuclear fuel material zone. Even if the overall core is assumed to become a state of 100% void, no positive reactivity is inserted to the core.
    • 轻水反应堆的核心具有多个燃料组件。 燃料组件包括多个燃料棒,其中下端由下连接板支撑,上端由上连接板支撑。 燃料棒在核燃料材料区之上形成集气室,并在核燃料材料区下方具有中子吸收材料填充区。 附接到上连接板的中子吸收构件设置在核燃料材料区域上方的相邻燃料棒的相互增压室之间。 中子吸收构件具有500mm的长度并且位于与核燃料材料区300mm的距离处。 即使假设整个核心成为100%空白的状态,也不会向核心插入积极的反应性。
    • 8. 发明授权
    • Light water reactor core and fuel assembly
    • 轻水反应堆核心和燃料组件
    • US06512805B1
    • 2003-01-28
    • US09660356
    • 2000-09-12
    • Renzo TakedaMotoo AoyamaJunichi MiwaMotohiko Ikegawa
    • Renzo TakedaMotoo AoyamaJunichi MiwaMotohiko Ikegawa
    • G21C104
    • G21C3/32G21C1/08G21C3/326G21C5/02G21C7/117Y02E30/31Y02E30/38
    • There are provided a light water reactor core which has the same levels in cost efficiency and degree of safety as those of an existing BWR under operation now, that is, which is oriented to plutonium multi-recycle having a breeding ratio near 1.0 or slightly larger and having a negative void coefficient with minimizing modification of the reactor core structure of the existing BWR under operation now, and to fuel assemblies used for the boiling water reactor. The light water reactor core having an effective water-to-fuel volume ratio of 0.1 to 0.6 is formed by combining closed compact lattice fuel assemblies each composed of fuel rods having fuel which is enriched by adding plutonium or plutonium and an actinide to a uranium containing at least one of a depleted uranium, natural uranium, a degraded uranium and a low enriched uranium; high void fraction coolant of 45% to 70%; and large-diameter control rods to be inserted into the fuel assemblies, the large-diameter control rod comprising at least one absorption rod having a transverse cross-sectional area larger than a cross-sectional area of a unit lattice cell of the fuel rod.
    • 提供了一种轻水反应堆核心,其成本效益和安全程度与目前运行的现有BWR相同,即面向钚多循环的育种率接近1.0或稍大 并且具有负空隙系数,同时使现有的BWR的反应堆堆芯结构的现有修改最小化,以及用于沸水反应器的燃料组件。 具有有效的水与燃料体积比为0.1至0.6的轻水反应堆核心是通过组合封闭的紧凑格子燃料组合而形成的,每个燃料组合物由具有通过将钚或钚加入的铀和锕系元素富集的燃料的燃料棒组成, 铀,天然铀,退化铀和低浓铀中的至少一种; 45%至70%的高空隙率冷却液; 和大直径控制杆插入到燃料组件中,所述大直径控制杆包括至少一个吸收杆,所述至少一个吸收杆的横截面面积大于所述燃料棒的单元晶格单元的横截面面积。
    • 10. 发明授权
    • System and method for controlling operation of boiling water reactor
    • 沸水反应堆运行控制系统及方法
    • US4400343A
    • 1983-08-23
    • US085686
    • 1979-10-17
    • Masayuki IzumiRenzo Takeda
    • Masayuki IzumiRenzo Takeda
    • G21D3/14G21C7/32
    • G21D3/14Y02E30/40
    • The pressure P.sub.R in the reactor pressure vessel, the flow rate W.sub.c of the cooling water flowing through the core in the reactor pressure vessel, and the flow rate W.sub.STM of the steam supplied from the reactor pressure vessel to the turbine are detected. The enthalpy H.sub.f of the saturated cooling water is determined on the basis of the pressure P.sub.R. The values of the cooling water flow rate W.sub.c, the steam flow rate W.sub.STM, the enthalpy H.sub.f of the saturated cooling water and a predetermined enthalpy H.sub.IN of the cooling water at the core inlet are substituted into the equation below thereby to obtain the enthalpy H.sub.fw of the feed water. ##EQU1## An error is determined between the feed-water enthalpy H.sub.fw thus obtained and the enthalpy T.sub.fw of the feed water actually supplied into the reactor pressure vessel, and on the basis of this error, the opening of the flow rate control valve on the turbine bleeding pipe is adjusted, so that the flow rate of the steam bled from the turbine for heating the feed water is adjusted according to the error.
    • 检测反应堆压力容器中的压力PR,流过反应堆压力容器中的芯的冷却水的流量Wc以及从反应堆压力容器供给到涡轮的蒸汽的流量WSTM。 基于压力PR确定饱和冷却水的焓Hf。 将冷却水流量Wc,蒸汽流量WSTM,饱和冷却水的焓Hf和核心入口处的冷却水的预定焓HIN的值代入下面的等式,由此获得焓Hfw 给水。 在这样获得的给水焓Hfw与实际供应到反应堆压力容器中的进料水的焓Tfw之间确定误差,并且基于该误差,流量控制阀在 涡轮排气管被调节,从而根据误差调节从涡轮机排出的用于加热给水的蒸汽的流量。