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1. 发明申请

US20190172595A1 STICKY NEUTRON MODERATOR CORE PELLETS 审中-公开
公开(公告)号：US20190172595A1
公开(公告)日：2019-06-06
申请号：US15920740
申请日：2018-03-14
申请人： US Department of Energy
发明人： Donald R. Lambert
IPC分类号： G21C7/24 , G21C21/18
摘要： Exemplary embodiments of the present invention comprise pellets comprised of neutron moderating or absorbing materials with a polymer coating. The neutron core moderator pellet 100 comprises a core matrix of neutron absorbing material 102 and a polymer coating 104 that can also serve as a binder for the core 102. The neutron moderating/absorbing material 102 can be selected from a variety of chemical element materials that have been proven to have established neutron capture/absorbing capabilities.

2. 发明授权

US09914986B2 Method for producing, from a preform made of austenitic stainless steel with a low carbon content, a wear-resistant and corrosion-resistant cladding for a nuclear reactor, corresponding cladding and corresponding control cluster 有权
公开(公告)号：US09914986B2
公开(公告)日：2018-03-13
申请号：US14348378
申请日：2012-09-28
申请人： AREVA NP
发明人： Dominique Hertz
IPC分类号： G21C3/06 , G21C7/10 , C21D1/72 , C21D6/00 , C21D9/08 , C21D9/14 , C23C8/02 , C23C8/32 , C23C8/80 , G21C21/18 , C23C8/22 , C23C8/38 , G21C7/06 , C21D8/10
CPC分类号： C21D1/72 , C21D6/004 , C21D8/10 , C21D8/105 , C21D9/08 , C21D9/085 , C21D9/14 , C23C8/02 , C23C8/22 , C23C8/32 , C23C8/38 , C23C8/80 , G21C7/06 , G21C7/10 , G21C21/18 , Y02E30/39
摘要： A method for producing a wear-resistant and corrosion-resistant stainless steel part for a nuclear reactor is provided. This method includes steps of providing a tubular blank in austenitic stainless steel whose carbon content is equal to or lower than 0.03% by weight; shaping the blank; finishing the blank to form the cladding; hardening the outer surface of the cladding by diffusing one or more atomic species; the blank, before the providing step or during the shaping or finishing step, being subjected to at least one hyper quenching with sub-steps of: heating the blank to a sufficient temperature and for a sufficient time to solubilize any precipitates present; quenching the blank at a rate allowing the austenitic structure to be maintained in a metastable state at ambient temperature and free of precipitates.

3. 发明申请

US20170330642A1 Operational Neutron Source 审中-公开
公开(公告)号：US20170330642A1
公开(公告)日：2017-11-16
申请号：US15537460
申请日：2015-12-01
申请人： JOINT STOCK COMPANY "AKME-ENGINEERING"
发明人： Aleksandr Evgen'evich RUSANOV , Viktor Viktorovich LITVINOV , Vyacheslav Vasil'evich POPOV , Lyudmila Vasil'evna SKURIKHINA , Aleksandr Dmitrievich KARPIN
IPC分类号： G21G4/02 , G21C7/10 , G21C21/18 , G21F5/015
CPC分类号： G21G4/02 , G21C7/10 , G21C21/18 , G21F5/015 , Y02E30/38 , Y02E30/39
摘要： The invention relates generally to nuclear engineering and more particularly to controlled reactor start-up. The invention improves reliability of an operational neutron source by creating additional safety barriers between the coolant and the source active part materials. The operational neutron source is designed as a steel enclosure housing an ampule containing antimony and beryllium with separate antimony and beryllium cavities positioned coaxially. The antimony is contained in the central enclosure made of a niobium-based alloy unreactive with antimony. A beryllium powder bed is located between the antimony enclosure and the ampule enclosure. The ampule enclosure is made of martensite-ferrite steel poorly reacting with beryllium. An upper gas collector is located above the ampule, which serves as a compensation volume collecting gaseous fission products. At the bottom, the ampule is supported by a reflector and a bottom gas collector. The gas collectors, reflector and washers are made of martensite-ferrite grade steel.

4. 发明申请

US20160351281A1 Neutron Irradiated Material Repair 审中-公开
标题翻译：中子照射材料修复
公开(公告)号：US20160351281A1
公开(公告)日：2016-12-01
申请号：US14721834
申请日：2015-05-26
申请人： AREVA Inc.
发明人： Jeffrey A. Enneking , Brian W. Ring
IPC分类号： G21C21/18 , B23K26/144 , B23K26/36 , B23P6/00 , B23K26/342
CPC分类号： B23K26/144 , B23K26/0884 , B23K26/1224 , B23K26/127 , B23K26/32 , B23K26/34 , B23K26/361 , B23K2101/12 , B23K2103/04 , B23K2103/26 , B23P6/00 , G21C13/087 , G21C19/02 , G21C19/20 , G21C21/00 , Y02E30/40
摘要： The invention is a process of repairing cracked or microstructurally damaged portions of irradiated materials, such as nuclear reactor pressure vessels and shrouds. A damaged portion of the irradiated substrate is first removed, such as by electrical discharge machining (EDM). After removing the damaged portion, the recast layer inherent in the EDM process is then removed. Once the repair area substrate material has been removed to a calculated depth, the created cavity is then filled without releasing transmutated elements within the irradiated material. A chamber may be placed on the irradiated material surrounding the repair area to create an isolated work space.
摘要翻译：本发明是修复受辐射材料（例如核反应堆压力容器和护罩）的裂纹或微结构损坏部分的方法。照射的基板的损坏部分首先被去除，例如通过放电加工（EDM）。在去除损坏的部分之后，然后去除EDM工艺中固有的重铸层。一旦修复区域基底材料已被去除到计算的深度，则所形成的空腔然后被填充而不释放被照射材料内的变形元素。腔室可以被放置在围绕修复区域的辐射材料上以产生隔离的工作空间。

5. 发明授权

US4744922A Neutron-absorbing material and method of making same 失效
标题翻译：中子吸收材料及其制造方法
公开(公告)号：US4744922A
公开(公告)日：1988-05-17
申请号：US884046
申请日：1986-07-10
申请人： Keith A. Blakely , Peter T. B. Shaffer
发明人： Keith A. Blakely , Peter T. B. Shaffer
IPC分类号： C04B35/573 , G21C7/107 , G21C7/24 , G21C21/18 , C04B35/68 , G21C11/06 , G21F1/06
CPC分类号： C04B35/573 , G21C21/18 , G21C7/107 , G21C7/24 , G21Y2002/104 , G21Y2004/10 , Y02E30/39
摘要： A neutron-absorbing material is formed by a process which includes the steps of: mixing an absorptive material having a high thermal neutron capture cross-section (e.g., B.sub.4 C), a neutron-moderating material (e.g., graphite) and a binder (e.g., a phenol formaldehyde resin); shaping such mixture; curing such shaped mixture (e.g., to complete polymerization of the resin and to have only a carbon residue); and siliconizing such shaped and cured mixture. The resulting product has been formed to be denser and stronger, and more oxidation- and abrasion-resistant than prior art compositions.
摘要翻译：通过包括以下步骤的方法形成中子吸收材料：将具有高热中子捕获截面（例如，B4C）的吸收材料，中子调节材料（例如石墨）和粘合剂（例如，，苯酚甲醛树脂）; 塑造这种混合物; 固化这种成形混合物（例如，完成树脂的聚合并且仅具有碳残余物）; 并将这种成型和固化的混合物硅化。所形成的产品已经形成为比现有技术的组合物更致密，更坚固，更耐氧化和耐磨。

6. 发明授权

US4474728A Neutron absorber pellets with modified microstructure 失效
标题翻译：具有改性微结构的中子吸收剂颗粒
公开(公告)号：US4474728A
公开(公告)日：1984-10-02
申请号：US334720
申请日：1981-12-28
申请人： Kenneth C. Radford
发明人： Kenneth C. Radford
IPC分类号： G21C3/62 , G21C7/04 , G21C21/18 , G21C11/00
CPC分类号： G21C21/18 , G21C7/04 , G21Y2002/104 , G21Y2002/40 , G21Y2004/10 , G21Y2004/40 , Y02E30/39
摘要： An improved annular burnable poison pellet of aluminum oxide-boron carbide (Al.sub.2 O.sub.3 --B.sub.4 C) adapted for positioning in the annular space of concentrically disposed zircaloy tubes. Each tubular pellet is fabricated from Al.sub.2 O.sub.3 powders of moderate sintering activity which serves as a matrix for B.sub.4 C medium size particle distrbution. Special pellet moisture controls are incorporated in the pellet for moisture stability and the pellet is sintered in the temperature range of 1630.degree.-1650.degree. C. This method of fabrication produces a pellet about 2 inch long with a wall thickness of about 0.020 inch to 0.040 inch. Fabricating each pellet to about 70% theoretical density gives an optimum compromise between fabricability, microstructure, strength and moisture absorption.
摘要翻译：一种改进的氧化铝 - 碳化硼（Al2O3-B4C）的环形可燃毒丸，适用于定位在同心设置的锆石管的环形空间中。每个管状丸粒由具有中等烧结活性的Al 2 O 3粉末制成，其用作B4C中等粒度分布的基质。将特殊颗粒水分控制物并入颗粒中用于水分稳定性，并将颗粒在1630°-1650℃的温度范围内烧结。该制造方法产生约2英寸长的颗粒，壁厚约0.020英寸至0.040 英寸。将每个颗粒制造成约70％的理论密度，使得在可制造性，显微结构，强度和吸湿性之间达到最佳的折中。

7. 发明授权

US3955972A Method of producing sheets and article to practice such method 失效
标题翻译：生产纸张和制品的方法来实施这种方法
公开(公告)号：US3955972A
公开(公告)日：1976-05-11
申请号：US468971
申请日：1974-05-13
申请人： Gary E. Miller
发明人： Gary E. Miller
IPC分类号： B21B3/02 , C21D1/68 , C21D8/02 , G21C21/18 , C22C33/00 , C22B9/10
CPC分类号： C21D8/0205 , B21B3/02 , C21D1/68 , G21C21/18
摘要： This invention relates to the art of reducing metallic bodies from a greater thickness to a substantially smaller thickness and has particular relationship to such reduction of stainless steel containing substantial quantities of boron, typically in the fabrication of sheets for nuclear reactor control rods.
摘要翻译：本发明涉及将金属体从更大厚度还原成较小厚度的技术，并且与通常用于制造核反应堆控制棒的片材的含有大量硼的不锈钢的这种减少具有特别的关系。

8. 发明授权

US3827264A Method of producing sheets and article to practice such method 失效
标题翻译：生产纸张的方法和实践方法
公开(公告)号：US3827264A
公开(公告)日：1974-08-06
申请号：US56660366
申请日：1966-07-20
申请人： ARCO NUCLEAR CO
发明人： MILLER G
IPC分类号： B21B3/02 , C21D1/68 , C21D8/02 , G21C21/18 , B21B45/00 , B23P17/00
CPC分类号： G21C21/18 , B21B3/02 , C21D1/68 , C21D8/0205 , Y10T29/49812
摘要： There is disclosed a method of reducing a billet of stainless steel containing about 2% of boron without edge cracking of the billet and without loss of the boron from the billet. The billet is coated with zirconia and enclosed in a jacket of mild steel and heated to about 1100*C. and rolled to the desired thickness. The zirconia prevents the billet from adhering to the jacket. The stainless steel is produced by melting rods of a standard stainless steel, for example AISI 304L, with a mild-steel can containing an appropriate quantity of boron powder.
摘要翻译：公开了一种减少含有约2％硼的不锈钢坯料的方法，而不会使坯料发生边缘裂纹，并且不会从坯料中损失硼。坯料用氧化锆涂覆并封闭在软钢外壳中并加热至约1100℃并轧制至所需厚度。氧化锆防止坯料粘附到夹套上。不锈钢是通过用标准不锈钢（例如AISI 304L）的熔化棒与含有适量硼粉的软钢罐制成的。

9. 发明授权

US3245782A Metal dispersions 失效
公开(公告)号：US3245782A
公开(公告)日：1966-04-12
申请号：US18565662
申请日：1962-04-06
申请人： DRESSER PRODUCTS INC
发明人： RAY WILLIAM E
IPC分类号： C22C1/10 , G21C21/18
CPC分类号： G21C21/18 , C22C1/10

10. 发明授权

US3103478A Goooo 失效
公开(公告)号：US3103478A
公开(公告)日：1963-09-10
申请号：US3103478D
IPC分类号： G21C7/113 , G21C21/18
CPC分类号： G21C21/18 , G21C7/113 , Y02E30/39 , Y10T29/4981 , Y10T428/12375 , Y10T428/12486

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