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1. 发明授权

US5398268A Nuclear power plant having a water chemistry control system for a primary cooling system thereof and an operation method thereof 失效
标题翻译：具有用于其一次冷却系统的水化学控制系统的核电站及其操作方法
公开(公告)号：US5398268A
公开(公告)日：1995-03-14
申请号：US960847
申请日：1992-10-14
申请人： Hidefumi Ibe , Masanori Takahashi , Yasuko Aoki , Yamato Asakura , Makoto Nagase , Noriyuki Ohnaka , Masanori Sakai , Takashi Saito , Katsumi Ohsumi , Kazuhiko Akamine , Makoto Hayashi , Kiyotomo Nakata
发明人： Hidefumi Ibe , Masanori Takahashi , Yasuko Aoki , Yamato Asakura , Makoto Nagase , Noriyuki Ohnaka , Masanori Sakai , Takashi Saito , Katsumi Ohsumi , Kazuhiko Akamine , Makoto Hayashi , Kiyotomo Nakata
IPC分类号： G21C17/02 , G21C17/022 , G21D1/00 , G21D3/08 , G21C9/00
CPC分类号： G21C17/0225 , G21C17/022 , G21Y2002/304 , G21Y2004/40
摘要： A water chemistry factor which is specific to a specific portion of a primary cooling system and universal is decided to be a standard target. The concentration of an agent for mitigating corrosion damage of structural material of the primary cooling system is controlled so that the target will be in a desirable range. All sensor groups provided in the primary cooling system are separated into sensor groups in different lines, of which a specific sensor group are connected to an arithmetic unit and a data base and are for always monitoring a plant process. For example, concentration distribution agreed with measured value oxidation component in the reactor water at the measurement points is selected from the data base, and it is used to estimate the standard target.
摘要翻译：特定于主冷却系统和通用特定部分的水化学因子决定为标准目标。减轻主冷却系统结构材料的腐蚀损伤的试剂的浓度被控制，使得靶在期望的范围内。主冷却系统中提供的所有传感器组分为不同的传感器组，其中特定传感器组连接到算术单元和数据库，并用于始终监测工厂过程。例如，从数据库中选择测量点的反应堆水中测量值氧化成分的浓度分布，并用于估计标准目标。

2. 发明授权

US5116569A Austenitic steel excellent in resistance to neutron irradiation embrittlement and members made of the steel 失效
标题翻译：奥氏体耐腐蚀性能优良的耐中性辐照刺激和钢铁成员
公开(公告)号：US5116569A
公开(公告)日：1992-05-26
申请号：US563697
申请日：1990-08-07
申请人： Shigeki Kasahara , Kiyotomo Nakata , Jiro Kuniya , Shigeo Hattori
发明人： Shigeki Kasahara , Kiyotomo Nakata , Jiro Kuniya , Shigeo Hattori
IPC分类号： G21C3/07 , C22C38/00 , C22C38/40 , C22C38/58 , G21B1/11 , G21B1/17 , G21C3/30 , G21C7/12 , G21C13/08
CPC分类号： C22C38/58 , Y10S376/90
摘要： An austenitic steel excellent in resistance to neutron irradiation embrittlement which contains, by weight, not more than 0.03% carbon, not more than 1% silicon, 5 to 25% manganese, 15 to 26% chromium, and 10 to 20% nickel, the ratio of atomic volume of chromium to the average atomic volume of matrix of the steel being from 0.900 to 1.030. It is possible to add to the austenitic steel, besides the above-mentioned alloying elements, at least one element selected from the group consisting of niobium, titanium, zirconium, tantalum and vanadium which are effective in corrosion resistance and irradiation embrittlement under neutron irradiation in total amounts of not more than 1.0%. At least one of components composing the inside of a nuclear reactor or nuclear fusion reactor is made of the austenitic steel.

3. 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。

4. 发明授权

US5583900A Structural member having superior resistance to neutron irradiation embrittlement, austenitic steel for use in same, and use thereof 失效
标题翻译：具有优异的耐中子照射脆性的结构件，用于其的奥氏体钢及其用途
公开(公告)号：US5583900A
公开(公告)日：1996-12-10
申请号：US214297
申请日：1994-03-17
申请人： Shigeki Kasahara , Kiyotomo Nakata , Shizuka Shimanuki , Shinzo Ikeda , Masayoshi Kanno
发明人： Shigeki Kasahara , Kiyotomo Nakata , Shizuka Shimanuki , Shinzo Ikeda , Masayoshi Kanno
IPC分类号： C22C38/00 , C22C38/50 , C22C38/58 , G21B1/11 , G21B1/17 , G21C3/07 , G21C5/00 , G21C11/00
CPC分类号： C22C38/58 , G21C3/07 , G21Y2002/102 , G21Y2004/10 , Y02E30/40 , Y10S376/90
摘要： This invention provides austenitic steel having a superior resistance to neutron irradiation, a nuclear reactor and a nuclear fission reactor using such steel.In the present invention, austenitic steel containing at least one of Pd and Pt is used for a member which undergoes neutron irradiation in high-temperature water. More specifically, the steel consists essentially of not more than 0.02% C, not more than 1% Si, 0.5-15% Mn, 9-26% Cr, 8-20% Ni, 0.5-3% Mo, at least one kind of 0.1-16% selected from the group consisting of Pd and Pt, and not less than 50% Fe, and may further contain not more than 1.0% of at least one kind selected from the group consisting of Nb, Ti, Zr, Hf and V, and this is used for structural members in a core of a nuclear reactor and a nuclear fission reactor.
摘要翻译：本发明提供了具有优异的耐中子辐射性的奥氏体钢，核反应堆和使用这种钢的核裂变反应堆。在本发明中，将含有Pd和Pt中的至少一种的奥氏体钢用于在高温水中进行中子照射的构件。更具体地说，钢基本上由不超过0.02％C，不超过1％Si，0.5-15％Mn，9-26％Cr，8-20％Ni，0.5-3％Mo，至少一种选自Pd和Pt中的0.1-16％，Fe不小于50％，并且还可以含有不超过1.0％的选自Nb，Ti，Zr，Hf中的至少一种和V，这用于核反应堆和核裂变反应堆核心的结构件。

5. 发明授权

US5307385A Method of and apparatus for estimating remaining service life of material being exposed to radiant ray irradiation 失效
标题翻译：用于估计暴露于辐射线照射的材料的剩余使用寿命的方法和装置
公开(公告)号：US5307385A
公开(公告)日：1994-04-26
申请号：US895049
申请日：1992-06-08
申请人： Shizuka Shimanuki , Kiyotomo Nakata , Shizuo Matushita , Shigeki Kasahara , Michiyoshi Yamamoto , Hideya Anzai
发明人： Shizuka Shimanuki , Kiyotomo Nakata , Shizuo Matushita , Shigeki Kasahara , Michiyoshi Yamamoto , Hideya Anzai
IPC分类号： G01N17/00 , G21C17/00
CPC分类号： G21D3/001 , G01N17/00 , G21C17/00 , Y02E30/40
摘要： A method and an apparatus for estimating the remaining service life of an object by measuring the physical quantity of a sample and which are applicable to a nuclear reactor. A plurality of model samples are experimentally prepared by preliminarily disposing a material having substantially the same composition as the object to be subjected to the estimation in an environment substantially the same as the object and measuring the physical quantities of the model samples in relation with exposure times. From this experiment, a relationship between the exposure time and the physical quantity under such an environment is obtained. Further, a critical exposure time which will cause an unstable fracture of a material of an actual sample, which is made of a material substantially the same as the object and placed in substantially the same environment as the object, is preliminarily obtained from the relationship between the exposure time and the physical quantity for the model samples. The physical quantity of the actual sample is then measured. Subsequently, an actual exposure time corresponding to the physical quantity of the actual sample is obtained by using the relationship between the physical quantity and the exposure time. Thereafter, a difference between the critical exposure time and the actual exposure time is calculated to obtain a remaining service life of the object.
摘要翻译：一种用于通过测量样品的物理量并且适用于核反应堆来估计物体的剩余使用寿命的方法和装置。通过在与目标基本相同的环境中预先设置与要进行估计的物体基本相同的组成的材料并且测量与曝光时间相关的模型样品的物理量来实验地制备多个模型样本。从该实验可以看出，在这种环境下曝光时间与物理量之间的关系。此外，由与目标基本上相同的材料制成的实际样品的材料的不稳定断裂的临界暴露时间预先从对象的相互关系中获得，模型样本的曝光时间和物理量。然后测量实际样品的物理量。随后，通过使用物理量和曝光时间之间的关系来获得与实际样品的物理量相对应的实际曝光时间。此后，计算临界曝光时间和实际曝光时间之间的差以获得对象的剩余使用寿命。

6. 发明授权

US5316597A A nuclear reactor comprising a reactor vessel and structural members made of an austenitic stainless steel having superior resistance to irradiation-induced segregation 失效
标题翻译：一种包括反应器容器和由奥氏体不锈钢制成的结构构件的核反应堆具有优异的抗辐照诱导偏析性
公开(公告)号：US5316597A
公开(公告)日：1994-05-31
申请号：US936647
申请日：1992-08-28
申请人： Takahiko Kato , Shinzo Ikeda , Yasuhisa Aono , Masakiyo Izumiya , Kiyotomo Nakata , Isao Masaoka , Heishichiro Takahashi
发明人： Takahiko Kato , Shinzo Ikeda , Yasuhisa Aono , Masakiyo Izumiya , Kiyotomo Nakata , Isao Masaoka , Heishichiro Takahashi
IPC分类号： C22C38/00 , C22C38/40 , C22C38/46 , C22C38/48 , C22C38/50 , G21B1/11 , G21B1/17 , G21C5/00
CPC分类号： C22C38/50 , C22C38/40 , C22C38/46 , C22C38/48 , Y10S376/90
摘要： A nuclear reactor having structural members made of austenitic stainless steel which is corrosion-resistant in an environment of neutron irradiation, and can suppress stress corrosion cracking and embrittlement. At least one additive selected from the group consisting of Ti more than 0.2% by weight but not more than 0.6%, Zr more than 0.2% but not more than 1.14%, Hf more than 0.2% but not more than 2.24%, V more than 0.2% but not more than 0.64%, Nb more than 0.5% but not more than 1.17% and Ta more than 0.5% but not more than 2.27% is added to austenitic stainless steel containing Cr, Ni and so on, and said at least one exists in a solid-solution state. In addition, the steel has a wholly austenitic structure substantially free of carbide. In order to maintain the irradiation-induced segregation prevention effected by the addition element, the C content is limited to 0.01 to 0.008%, and the N content is limited to 0.001 to 0.0%. The irradiation-induced segregation, of the constituent elements, such as Cr and Ni, occurring in a grain boundary under irradiation, can be prevented, and the deterioration of the corrosion resistance of the material, as well as the embrittlement, can be prevented.
摘要翻译：具有由奥氏体不锈钢制成的结构构件的核反应堆，其在中子照射环境中耐腐蚀，并且可以抑制应力腐蚀开裂和脆化。至少一种添加剂选自Ti大于0.2重量％但不大于0.6重量％，Zr大于0.2重量％但不大于1.14重量％，Hf大于0.2重量％但不大于2.24重量％，V多超过0.2％但不超过0.64％，Nb超过0.5％但不超过1.17％，Ta含量超过0.5％但不超过2.27％，则含有Cr，Ni等奥氏体不锈钢，在固溶状态下最少存在。此外，钢具有基本上不含碳化物的完全奥氏体结构。为了保持由添加元素进行的照射诱导的偏析防止，C含量限于0.01〜0.008％，N含量限定在0.001〜0.0％。可以防止在照射下的晶界中发生的诸如Cr和Ni的组成元素的照射诱导的偏析，并且可以防止材料的耐腐蚀性劣化以及脆化。

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