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1. 发明授权

US4842814A Nuclear reactor fuel assembly 失效
标题翻译：核反应堆燃料组件
公开(公告)号：US4842814A
公开(公告)日：1989-06-27
申请号：US9477
申请日：1987-02-02
申请人： Iwao Takase , Masahisa Inagaki , Masayoshi Kanno , Toshimi Yoshida , Jiro Kuniya , Isao Masaoka , Tetsuo Yasuda , Hajime Umehara , Hideo Maki
发明人： Iwao Takase , Masahisa Inagaki , Masayoshi Kanno , Toshimi Yoshida , Jiro Kuniya , Isao Masaoka , Tetsuo Yasuda , Hajime Umehara , Hideo Maki
IPC分类号： G21C3/32 , G21C3/34
CPC分类号： G21C3/34 , G21C3/32 , Y02E30/40
摘要： A channel box and/or a spacer of a fuel assembly is a welded construction and made of a Zr-Nb-Sn alloy comprising 0.5-2.2 wt % Nb, 0.5-1.5 wt % Sn contained so as to satisfy the relation of Sn(wt %) 22.times.Nb(wt %)--3.0, and balance Zr or a Zr-Nb-Sn-Mo alloy comprising 0.5-2.2 wt % Nb, 0.5-1.5 wt % Sn contained so as to satisfy the relation of Sn(wt %).gtoreq.2.times.Nb(wt %)--0.3, 0.1-0.8 wt % Mo, and balance Zr. The welded portion, its heat affected zone and the unwelded portion of the channel box and/or the spacer have substantially the whole equilibrium phase structure.
摘要翻译：燃料组件的通道箱和/或间隔件是焊接结构，由包含0.5-2.2重量％Nb，0.5-1.5重量％Sn的Zr-Nb-Sn合金制成，以满足Sn（重量％）22×Nb（重量％）-3.0，余量包含0.5-2.2重量％Nb，0.5-1.5重量％Sn的Zr或Zr-Nb-Sn-Mo合金，以满足Sn（wt％）的关系，）> / = 2xNb（wt％）-0.3,0.1-0.8wt％Mo，余量为Zr。焊接部分，其热影响区和通道箱和/或间隔件的未焊接部分具有基本上全部的平衡相结构。

2. 发明授权

US4678521A Process for producing zirconium-based alloy and the product thereof 失效
标题翻译：锆系合金的制造方法及其制造方法
公开(公告)号：US4678521A
公开(公告)日：1987-07-07
申请号：US837557
申请日：1986-03-03
申请人： Toshimi Yoshida , Hideo Maki , Hajime Umehara , Tetsuo Yasuda , Isao Masaoka , Iwao Takase , Masahisa Inagaki , Ryutarou Jimbow , Keiichi Kuniya
发明人： Toshimi Yoshida , Hideo Maki , Hajime Umehara , Tetsuo Yasuda , Isao Masaoka , Iwao Takase , Masahisa Inagaki , Ryutarou Jimbow , Keiichi Kuniya
IPC分类号： C22F1/18 , C21D8/00 , C22C16/00
CPC分类号： C22F1/186 , Y10S376/90
摘要： In a process for producing a zirconium-based alloy in which after the zirconium-based alloy is subjected to hot plastic working, it is subjected to cold plastic working and then to annealing and these steps are repeated at least twice, the present invention provides a process for producing a zirconium-based alloy characterized in that after the alloy is subjected to solid solution treatment in which it is heated to a temperature within the range including the .alpha. phase and the .beta. phase of the alloy, or within the range of the .beta. phase and is then quenched, cold plastic working is effected at least twice.
摘要翻译：在锆系合金的制造方法中，在对锆系合金进行热塑性加工后，对其进行冷塑性加工，然后进行退火，将这些工序重复至少2次，本发明提供锆系合金的制造方法，其特征在于，在将合金进行固溶处理后，将其加热至包含合金的α相和β相的范围内的温度，或者在β 然后淬火，冷塑性加工至少进行两次。

3. 发明授权

US4689091A Process for producing zirconium-based alloy 失效
标题翻译：锆基合金的制造方法
公开(公告)号：US4689091A
公开(公告)日：1987-08-25
申请号：US704208
申请日：1985-02-22
申请人： Toshimi Yoshida , Hideo Maki , Hajime Umehara , Tetsuo Yasuda , Isao Masaoka , Iwao Takase , Masahisa Inagaki , Ryutarou Jimbow , Keiichi Kuniya
发明人： Toshimi Yoshida , Hideo Maki , Hajime Umehara , Tetsuo Yasuda , Isao Masaoka , Iwao Takase , Masahisa Inagaki , Ryutarou Jimbow , Keiichi Kuniya
IPC分类号： C22F1/18 , C21D8/00
CPC分类号： C22F1/186 , Y10S376/90
摘要： In a process for producing a zirconium-based alloy in which after the zirconium-based alloy is subjected to hot plastic working, it is subjected to cold plastic working and then to annealing and these steps are repeated at least twice, the present invention provides a process for producing a zirconium-based alloy characterized in that after the alloy is subjected to solid solution treatment in which it is heated to a temperature within the range including the .alpha. phase and the .beta. phase of the alloy, or within the range of the .beta. phase and is then quenched, cold plastic working is effected at least twice.

4. 发明授权

US4810461A Zirconium-based alloy with high corrosion resistance 失效
标题翻译：锆基合金具有高耐腐蚀性
公开(公告)号：US4810461A
公开(公告)日：1989-03-07
申请号：US940723
申请日：1986-12-09
申请人： Masahisa Inagaki , Iwao Takase , Masayoshi Kanno , Jiro Kuniya , Kimihiko Akahori , Isao Masaoka , Hideo Maki , Junjiro Nakajima
发明人： Masahisa Inagaki , Iwao Takase , Masayoshi Kanno , Jiro Kuniya , Kimihiko Akahori , Isao Masaoka , Hideo Maki , Junjiro Nakajima
IPC分类号： G21C3/07 , C22C16/00 , C22F1/00 , C22F1/18 , G21C3/06
CPC分类号： C22F1/186 , C22C16/00
摘要： A zirconium-based alloy with a high corrosion resistance, consisting essentially of 1 to 2 wt % Sn, 0.20 to 0.35 wt % Fe, 0.03 to 0.16 wt % Ni and the balance substantially Zr. The Fe/Ni content ratio of the alloy ranges between 1.4 and 8. The structure of the alloy has fine intermetallic compound of Sn and Ni is precipitated within the zirconium crystal grain of .alpha.-phase. The alloy may further contain 0.05 to 0.15 wt % Cr. This alloy exhibits reduced hydrogen absorption rate and suffers from no nodular corrosion, so that it can suitably be used as a material of nuclear fuel cladding tubes. The nuclear fuel cladding tube made of this alloys exhibits extended service life when used in a nuclear reactor of high degree of burn-up.
摘要翻译：具有高耐腐蚀性的锆基合金基本上由Sn组成为1〜2重量％，Fe为0.20〜0.35重量％，Ni为0.03〜0.16重量％，余量基本为Zr。合金的Fe / Ni含量比在1.4和8之间。合金的结构具有细小的Sn的金属间化合物，Ni在α相的锆晶粒内析出。该合金还可以含有0.05〜0.15重量％的Cr。该合金显示出降低的氢吸收率，并且没有结节腐蚀，因此它可以适当地用作核燃料包覆管的材料。由这种合金制成的核燃料包层管在高度燃烧的核反应堆中使用时，寿命延长。

5. 发明授权

US4348041A Butt welded tubular structure of austenite stainless steel 失效
标题翻译：对接焊管状奥氏体不锈钢结构
公开(公告)号：US4348041A
公开(公告)日：1982-09-07
申请号：US6216
申请日：1979-01-24
申请人： Katsuyuki Imai , Isao Masaoka , Yochiteru Chiba , Masayoshi Kanno , Jiro Kuniya , Hisao Itow
发明人： Katsuyuki Imai , Isao Masaoka , Yochiteru Chiba , Masayoshi Kanno , Jiro Kuniya , Hisao Itow
IPC分类号： B23K33/00 , B23K9/23 , F16L13/02 , F16L13/04
CPC分类号： B23K9/23 , F16L13/0236
摘要： A butt welded tubular structure composed of tubular members of austenite stainless steel including a restraining member providing a cover to the entire outer circumferential surfaces of a welded joint and heat affected zones of the tubular members, the restraining member being formed of a metal or alloy of lower stress corrosion cracking sensitivity than the material of the tubular members and joined at the entire surfaces of opposite end portions thereof to the tubular members by welding, although the restraining member is not joined to the tubular members at portions of the restraining member corresponding to the welded joint and heat affected zones of the tubular members. The butt welded tubular structure is produced by joining tubular members of austenite stainless steel by butt welding, covering the entire outer circumferential surfaces of the welded joint and heat affected zones of the tubular members with a restraining member formed of a metal or alloy of lower stress corrosion cracking sensitivity than the material of the tubular members, and joining by welding the entire surfaces of opposite end portions of the restraining member to the tubular members while avoiding the joining of the restraining member to the welded joint and heat affected zones of the tubular members at portions of the restraining member corresponding to the welded joint and heat affected zones.
摘要翻译：一种对接焊管状结构，由奥氏体不锈钢管状构件构成，其包括对焊接接头的整个外周面提供盖的限制构件和管状构件的受热影响区域，所述约束构件由金属或合金比管状部件的材料低的应力腐蚀开裂敏感性，并且通过焊接在其相对端部的整个表面上与管状部件接合，尽管限制部件在与限制部件对应的部分处未连接到管状部件管状构件的焊接接头和热影响区域。对接焊管状结构是通过对接焊接奥氏体不锈钢的管状部件，通过用低应力的金属或合金形成的限制部件覆盖焊接接头的整个外周面和管状部件的热影响区域而制造的腐蚀开裂敏感性比管状构件的材料，并且通过将约束构件的相对端部的整个表面焊接到管状构件上而接合，同时避免限制构件与焊接接头的接合和管状构件的热影响区域在对应于焊接接头和受热影响区域的限制构件的部分。

6. 发明授权

US4718949A Method of producing a cladding tube for reactor fuel 失效
标题翻译：生产反应堆燃料包层管的方法
公开(公告)号：US4718949A
公开(公告)日：1988-01-12
申请号：US915555
申请日：1986-10-06
申请人： Iwao Takase , Toshimi Yoshida , Shinzo Ikeda , Isao Masaoka , Junjiro Nakajima
发明人： Iwao Takase , Toshimi Yoshida , Shinzo Ikeda , Isao Masaoka , Junjiro Nakajima
IPC分类号： C22C16/00 , C22F1/18 , G21C3/06 , G21C3/07
CPC分类号： G21C3/07 , Y02E30/40 , Y10S376/90
摘要： A method of producing cladding tube comprises a step of temperature-gradient annealing in which the inner surface of the tube is heated to a temperature higher than the recrystallization temperature thereof, while the outer surface of the tube is cooled, after the tube has been hot-extruded. The temperature-gradient annealing is effected while a temperature gradient is maintained between the inner surface and the outer surface of the cladding tube. While keeping the inner surface at a temperature higher than the recrystallization temperature, and the outer surface at a temperature lower than the recrystallization temperature. The cladding tube is obtained with the outer surface which has an excellent resistance to nodular corrosion and a soft inner surface which has an excellent resistance to stress corrosion cracking.
摘要翻译：制造包层管的方法包括将管的内表面加热到高于其再结晶温度的温度的温度梯度退火步骤，同时管的外表面被冷却后，管被热 - 挤压。在包覆管的内表面和外表面之间保持温度梯度的同时进行温度梯度退火。同时将内表面保持在比再结晶温度高的温度，而外表面在低于再结晶温度的温度下。获得具有优异的抗结块腐蚀性的外表面和具有优异的耐应力腐蚀开裂性的软内表面的包覆管。

7. 发明授权

US4664727A Zirconium alloy having superior corrosion resistance 失效
标题翻译：锆合金具有优良的耐腐蚀性
公开(公告)号：US4664727A
公开(公告)日：1987-05-12
申请号：US506393
申请日：1983-06-21
申请人： Masahisa Inagaki , Ryutaro Jinbo , Keiichi Kuniya , Isao Masaoka , Hideo Maki
发明人： Masahisa Inagaki , Ryutaro Jinbo , Keiichi Kuniya , Isao Masaoka , Hideo Maki
IPC分类号： C22C16/00 , C22F1/18
CPC分类号： C22F1/186
摘要： A zirconium alloy having superior corrosion resistance, containing Sn of a small amount not less than the amount of Sn existing in the solid-solution of the zirconium alloy at a room temperature, and at least one kind of Fe and Cr each of a small amount not less than the amount of each of Fe and Cr existing in the solid-solution of the zirconium alloy at a room temperature,the zirconium alloy being annealed after the solution heat treatment at a temperature at which both the .alpha. phase and .beta. phase thereof are included in the zirconium alloy,the total amount of said at least one kind of Fe and Cr existing in the solid-solution of the zirconium alloy being not less than 0.26%.
摘要翻译：具有优异的耐腐蚀性的锆合金，其含有少量不小于室温下的锆合金的固溶体中的Sn的量的Sn和至少一种少量的Fe和Cr 不少于在室温下锆合金固溶体中存在的Fe和Cr中的每一种，锆合金在固溶热处理后在其α相和β相均为包含在锆合金中，锆合金固溶体中存在的所述至少一种Fe和Cr的总量不小于0.26％。

8. 发明授权

US4223197A Method of cooling weld in steel piping and apparatus therefor 失效
标题翻译：钢管道焊接冷却方法及其设备
公开(公告)号：US4223197A
公开(公告)日：1980-09-16
申请号：US897403
申请日：1978-04-18
申请人： Katsuyuki Imai , Isao Masaoka , Yositeru Chiba , Jiro Kuniya
发明人： Katsuyuki Imai , Isao Masaoka , Yositeru Chiba , Jiro Kuniya
IPC分类号： B23K9/028 , B23K37/00 , B23K31/06
CPC分类号： B23K9/0282 , B23K37/003
摘要： A method for cooling a weld in steel piping during butt welding with cooling of the inside comprises, after joining of pipe ends by a root pass on the inside, cooling the junction being welded by subsequent passes with injection of a liquid medium at room temperature from the center of the pipe against the surrounding wall, in a direction between radial and tangential directions relative to the inner pipe surface. An apparatus for practicing the cooling method comprises a rotatable multi-nozzle assembly having a radius of rotation corresponding to the inside diameter of the pipe and is capable of injecting the cooling medium against the inner surface of the pipe, a duct for conducting the cooling medium to the nozzles, and a pumping device for forcing the cooling medium under pressure into the nozzles.
摘要翻译：在内部冷却的对接焊接期间冷却钢管道中的焊接的方法包括：在管端部通过内侧的根部接合之后，通过随后的通过在室温下注入液体介质来冷却被焊接的接合部管道的中心相对于内管表面在径向和切向之间的方向上相对于周围壁。用于实施冷却方法的装置包括具有与管的内径相对应的旋转半径的可旋转多喷嘴组件，并且能够将冷却介质喷射到管的内表面上，用于传导冷却介质以及用于迫使冷却介质在压力下进入喷嘴的泵送装置。

9. 发明授权

US5203984A Monitoring system for plant operation condition and its in-situ electrochemical electrode 失效
标题翻译：植物营养条件监测系统及其现场电化学电极
公开(公告)号：US5203984A
公开(公告)日：1993-04-20
申请号：US573780
申请日：1990-08-28
申请人： Masanori Sakai , Katsumi Mabuchi , Toshiaki Arato , Takuya Takahashi , Masakiyo Izumiya , Isao Masaoka , Yoshitaka Kojima , Masahisa Inagaki , Katsumi Ohsumi , Makoto Hayashi , Fumio Sato , Masateru Suwa , Kimihiko Akahori
发明人： Masanori Sakai , Katsumi Mabuchi , Toshiaki Arato , Takuya Takahashi , Masakiyo Izumiya , Isao Masaoka , Yoshitaka Kojima , Masahisa Inagaki , Katsumi Ohsumi , Makoto Hayashi , Fumio Sato , Masateru Suwa , Kimihiko Akahori
IPC分类号： G01N17/02 , G01N27/26 , G01N27/27 , G01N27/30 , G01N27/333 , G01N27/401 , G01N27/403 , G01N27/416 , G01N27/48 , G01N33/18 , G21C17/02 , G21C17/022
CPC分类号： G01N27/30 , G01N33/18 , G21C17/022 , Y10S706/906
摘要： A plant operational status monitoring supervisory system comprising; means for extracting information directly relating to water quality of an objective portion consecutively for a period of time by means of an electrochemical water quality sensor installed in an objective portion to monitor in-situ in a plant; means for evaluating water quality based on thus extracted information; means for comparing an obtained water quality evaluation result with a reference value for a predetermined plant operation procedure; and means for displaying or storing necessary portion out of said comparison results; is disclosed.An electrochemical reference electrode used in this system being provided with an electrolyte layer containing ion of the electrode member; a porous ceramic layer surrounding the same without permeating liquid; and electrode member electrochemically contacting with said elec-trolyte layer; and a terminal electrically contacting with said electrode member; and further having a long life in high temperature water, various status of high temperature water in objective portions and that of nearby constituent members in a plant are possible to be monitored online by means of this reference electrode.Further, because monitored data are processed by means of a neural network, the higher precision level of monitoring has been achieved.

10. 发明授权

US4560407A Alloy for use in a radioactive ray environment and reactor core members 失效
标题翻译：用于放射线环境和反应堆核心部件的合金
公开(公告)号：US4560407A
公开(公告)日：1985-12-24
申请号：US358211
申请日：1982-03-15
申请人： Toshimi Yoshida , Kiyotomo Nakata , Isao Masaoka , Hisawo Itow
发明人： Toshimi Yoshida , Kiyotomo Nakata , Isao Masaoka , Hisawo Itow
IPC分类号： C22C38/00 , C22C38/40
CPC分类号： C22C38/001 , C22C38/40 , Y10S376/90
摘要： An alloy for use in an environment exposed to neutron rays consists principally of Cr-Ni austenite stainless steel containing nitrogen in an amount exceeding the amount of an impurity and having principally an austenite structure. The alloy is used for reactor core members such as a core shroud, core supporters, control rods, etc. which are exposed to the neutron radiation but prevented from being embrittled by the radiation.
摘要翻译：用于暴露于中子射线的环境中的合金主要由Cr-Ni奥氏体不锈钢组成，其中氮含量超过杂质量，主要是奥氏体结构。该合金用于暴露于中子辐射但防止被辐射脆化的反应堆核心构件，例如芯护罩，芯支撑件，控制杆等。

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