公开(公告)号：EP0523914A1

公开(公告)日：1993-01-20

申请号：EP92306301.0

申请日：1992-07-09

Applicant: HITACHI, LTD.

Inventor： Yamamoto, Nobukazu ,  Matsumoto, Kouichi ,  Nakajima, Junjiro ,  Maki, Hideo ,  Hirakawa, Hiromasa ,  Inagaki, Masahisa ,  Takase, Iwao ,  Okazaki, Nobuhiro ,  Ishizaki, Hideaki ,  Sakuma, Toraki

IPC: G21C3/324 ,  C23F1/02

CPC classification number: G21C3/324 ,  C23F1/02 ,  G21Y2002/103 ,  G21Y2002/302 ,  G21Y2004/201 ,  G21Y2004/40 ,  Y02E30/40

Abstract: In a method of fabricating a channel box (11) for use in a nuclear reactor, Zr-alloy sheet material (1) is formed into a tubular channel box. The method includes solution heat treatment (3,4,5) of the Zr-alloy sheet material including quenching from a temperature at which β-phase is present. After the solution heat treatment, portions of the Zr-alloy sheet are thinned relative to other portions by a non-stressing thinning process, such as chemical etching in a bath (24). The corrosion resistance imparted by heat treatment is retained, and the heat treatment itself is easily performed on material of uniform thickness.

Abstract translation: 在核反应堆中制造用于使用一个信道箱（11）的方法，Zr基合金片材（1）被形成为管状通道箱。 该方法包括将Zr的合金板材包括从淬火温度在哪个测试-PHASE存在的固溶热处理（3,4,5）。 在固溶热处理之后，Zr基合金板的部分相对于其它部分由非强调减薄过程，：如在一个浴（24）的化学蚀刻变薄。 通过热处理所赋予的耐蚀性得到保持，并在热处理本身容易进行上均匀的厚度的材料。

公开(公告)号：EP0353733A3

公开(公告)日：1990-03-07

申请号：EP89114266.3

申请日：1989-08-02

Applicant: HITACHI, LTD.

Inventor： Kanno, Masayoshi ,  Inagaki, Masahisa ,  Takase, Iwao ,  Kuniya, Jiro ,  Maru, Akira ,  Yasuda, Tetsuro ,  Maki, Hideo

IPC: G21C3/20

CPC classification number: G21C3/34 ,  G21C3/07 ,  G21C3/20 ,  G21Y2002/102 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2004/10 ,  G21Y2004/201 ,  G21Y2004/202 ,  G21Y2004/30 ,  Y02E30/40

Abstract: A fuel assembly for a nuclear reactor compris­ing a fuel cladding tube (11) of three-layer structure having an outer surface (16) in contact with reactor water of the nuclear reactor, an inner surface layer (14) in contact with the nuclear fuel, and an intermediate layer (15) interposed between the outer surface layer and the inner surface layer. the outer surface layer (16) is made of a Zr-based alloy containing Nb, Sn and Mo. The inner surface layer(14) is made of pure zirconium. The intermediate layer is made of a high ductility alloy which is higher in ductility than the outer surface layer (16) and is higher in strength than the inner surface layer(14).

公开(公告)号：EP0307268A1

公开(公告)日：1989-03-15

申请号：EP88402106.4

申请日：1988-08-12

Applicant: FRAMATOME ,  COGEMA: Société anonyme dite

Inventor： Bard, Josette

IPC: G21C3/34 ,  C22F1/18

CPC classification number: C22F1/186 ,  G21C3/3424 ,  G21Y2002/104 ,  G21Y2002/302 ,  G21Y2004/201 ,  G21Y2004/40 ,  Y02E30/40

Abstract: On refroidit à vitesse contrôlée un produit plat en alliage de zirconium contenant 2 à 3 % de niobium depuis l'état α + β, puis on découpe et on forme à froid des plaquettes (2, 2′) à partir de ce demi-produit. On réalise l'assemblage et la liaison entre les plaquettes (2, 2′) et la grille (1) dans son ensemble est soumise à un revenu en phase α à une température comprise entre 400 et 550°C, pendant une durée de dix à trente heures, de façon à obtenir par un traitement unique sur le produit fini, l'ensemble des caractéristiques nécessaires vis-à-vis des exigences fonctionnelles.

Abstract translation: 由含有2〜3％铌的锆合金制成的扁平制品以α+β状态的受控速率冷却，然后将小板（2,2'）从该半成品中切出并冷成型。 产生组件和小板（2,2'）之间的接合，并且格栅（1）作为整体在400-550℃的温度下作为α相进行回火10到30分钟 小时，以便通过对成品的单一处理获得所有功能要求所必需的特性。 ... ...

公开(公告)号：EP0155167B1

公开(公告)日：1989-03-15

申请号：EP85301661.6

申请日：1985-03-11

Applicant: WESTINGHOUSE ELECTRIC CORPORATION

Inventor： Ferrari, Harry Max ,  Boyle, Raymond Francis ,  Kingsbury, Fred Dewey Jr.

IPC: G21C3/20 ,  C22C16/00 ,  C22F1/18

CPC classification number: G21C3/20 ,  C22C16/00 ,  C22F1/186 ,  G21Y2002/104 ,  G21Y2002/206 ,  G21Y2002/303 ,  G21Y2004/10 ,  G21Y2004/201 ,  G21Y2004/202 ,  Y02E30/40

公开(公告)号：EP0196286A1

公开(公告)日：1986-10-01

申请号：EP86850081.0

申请日：1986-03-06

Applicant: Santrade Ltd.

Inventor： Andersson, Erik Thomas ,  Wilson, Sten Anders ,  Schemel, John H.

IPC: C22F1/18 ,  G21C3/20

CPC classification number: G21C3/07 ,  C22F1/186 ,  G21Y2002/103 ,  G21Y2004/201 ,  G21Y2004/202 ,  Y02E30/40

Abstract: The invention relates to a method of making tubes of Zirconium alloys containing 1 -5 percent by weight of alloying elements such as Sn, Fe, Cr and Ni. According to the invention an improved corrosion resistance can be reached by means of annealing after extrusion and between cold rollings within a well defined temperature range in the a-phase zone during considerably longer times than standardized for the purpose of reaching equilibrium between secondary phase particles and Zirconium matrix and in that way a minimum content of Fe in solid solution.

公开(公告)号：EP0155603A1

公开(公告)日：1985-09-25

申请号：EP85102649.2

申请日：1985-03-08

Applicant: NIPPON NUCLEAR FUEL DEVELOPMENT CO., LTD.

Inventor： Imahashi, Hiromichi ,  Kubo, Toshio ,  Asahi, Kazumi ,  Mukai, Hideyuki ,  Ogata, Keizo

IPC: G21C3/20

CPC classification number: G21C3/20 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/201 ,  G21Y2004/30 ,  Y02E30/40

Abstract: 57 Disclosed are a cladding tube for a nuclear fuel and a nuclear fuel element incorporating the cladding tube. The cladding tube consists of an inner zirconium liner layer (6;34) and an outer zirconium alloy layer (1). The cladding tube has at least one of the following features. (I) the ratio a/b of the oxygen content a to iron content b in the zirconium liner layer (6; 34) is greater than 1.0, (II) the zirconium liner layer (34) is made of a zirconium into the matrix of which impurities are dissolved, and (III) the second phase particles having microscopic sizes and dispersed in the inner surface of the zirconium liner layer (6) and/or the outer surface of the zirconium alloy layer (1) have been removed substantially. Owing to these features, undesirable stress corrosion cracking and local corrosion are remarkably suppressed in the cladding tube (6, 1; 34, 1) and the nuclear fuel element of the invention.

公开(公告)号：EP0155167A2

公开(公告)日：1985-09-18

申请号：EP85301661.6

申请日：1985-03-11

Applicant: WESTINGHOUSE ELECTRIC CORPORATION

Inventor： Ferrari, Harry Max ,  Boyle, Raymond Francis ,  Kingsbury, Fred Dewey Jr.

IPC: G21C3/20 ,  C22C16/00 ,  C22F1/18

CPC classification number: G21C3/20 ,  C22C16/00 ,  C22F1/186 ,  G21Y2002/104 ,  G21Y2002/206 ,  G21Y2002/303 ,  G21Y2004/10 ,  G21Y2004/201 ,  G21Y2004/202 ,  Y02E30/40

Abstract: Cladding tubes for containing nuclear fuel material utilizing zirconium base alloys containing from 0.1 to 0.6 weight per cent tin; from 0.07 to 0.24 weight per cent iron; about 0.05 to 0.15 weight per cent chromium; and up to 0.05 weight per cent nickel. The balance of the alloy is zirconium with incidental impurities. The levels of the incidental impurity, oxygen, is controlled to a level of less than 350 ppm. These alloys have been designed to minimize the adverse effects of pellet-clad interaction, when they are used as a liner bonded to the inside surface of water reactor nuclear fuel cladding.

Abstract translation: 包含含有0.1至0.6重量％锡的锆基合金的核燃料材料的包覆管; 从0.07到0.24重量铁; 约0.05至0.15重量％的铬; 和高达0.05重量％的镍。 合金的余量为锆，附有杂质。 附带杂质，氧气的含量被控制在小于350ppm的水平。 这些合金被设计成当它们用作结合到水反应堆核燃料包层的内表面的衬里时，最小化颗粒包覆相互作用的不利影响。

公开(公告)号：EP0130840A3

公开(公告)日：1985-05-29

申请号：EP84304534

申请日：1984-07-02

Applicant: Quadrex Corporation

Inventor： Spalaris, Constantine N. ,  Vollmer, Regis

IPC: G21C03/32 ,  F16B35/00

CPC classification number: G21C3/334 ,  F16B35/00 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2004/201 ,  G21Y2004/30 ,  Y02E30/40

Abstract: @ Guide tube alignment pins are secured to a flange at the lower end of a guide tube of a nuclear power plant reactor vessel. They extend downwardly from the flange and enter openings in an upper core plate of a guide tube assembly as the guide tube is lowered into place to align the center of the guide tube with the center of the fuel bundle or fuel element so that the cluster control rod in the guide tube can enter the fuel bundle with the least amount of drag and in the proper time. The guide tube alignment pins include guide fingers at the lower portions thereof which enter the openings in the upper core plate for positioning the center of the guide tube over the center of the associated fuel bundle or fuel element. Intermediate the ends thereof, the guide tube alignment pins are formed with a Morse taper to increase the width of the shanks at the areas subject to frequent fractures. A locking device at the top of the guide tube alignment pins, which is integrally formed with a locking cup, is crimped for securement of the upper ends of the guide tube alignment pins to the flange at the lower end of the guide tube. Guide tube alignment pins have been made of Ni-Cr-Fe alloy X-750. To reduce stress corrosion cracking of the guide tube alignment pins, the guide tube alignment pins are heat treated by solution annealing at 2000°F ± 50°F for a minimum of one hour and then cooling to ambient temperature. This procedure is followed by heating the guide tube alignment pins at 1300°F ± 50°F for approximately twenty hours and then cooling to ambient temperature.

Abstract translation: 引导管对准销固定在核电站反应堆容器的导管下端的法兰上。 它们从凸缘向下延伸，并且当引导管下降到适当的位置以将引导管的中心与燃料束或燃料元件的中心对准时，在导管组件的上部芯板中进入开口，使得集束控制 引导管中的杆可以以最小量的阻力并在适当的时间内进入燃料束。 引导管对准销包括在其下部的引导指针，其进入上芯板中的开口，用于将引导管的中心定位在相关联的燃料束或燃料元件的中心上方。 在其端部中间，引导管对准销以莫尔斯锥形形成，以增加在频繁断裂的区域处的柄的宽度。 引导管对准销顶部的与锁定杯一体形成的锁定装置被压接，用于将引导管对准销的上端固定到导管下端的凸缘。 导管对准销已由Ni-Cr-Fe合金X-750制成。 为了减少引导管对准销的应力腐蚀开裂，引导管对准销通过2000°F +/- 50°F的固溶退火进行热处理至少1小时，然后冷却至环境温度。 此过程之后，将引导管对准销在1300°F +/- 50°F下加热约20小时，然后冷却至环境温度。

公开(公告)号：EP0085553A2

公开(公告)日：1983-08-10

申请号：EP83300455.9

申请日：1983-01-28

Applicant: WESTINGHOUSE ELECTRIC CORPORATION

Inventor： McDonald, Samuel Gilbert ,  Sabol, George Paul

IPC: C22F1/18

CPC classification number: C22F1/186 ,  G21C3/07 ,  G21Y2002/103 ,  G21Y2004/201 ,  Y02E30/40

Abstract: Modifying standard Zircaloy alloy processing techniques by limiting the working and annealing temperatures utilized after conventional beta treatment results in Zircaloy alloy product having superior high temperature steam corrosion resistance.

Abstract translation: 通过限制常规β处理后使用的工作和退火温度来修改标准Zircaloy合金加工技术，可以获得具有优异耐高温蒸汽腐蚀性能的Zircaloy合金产品。

公开(公告)号：EP3352175A1

公开(公告)日：2018-07-25

申请号：EP18151876.2

申请日：2018-01-16

Applicant: Sgargi, Andrea

Inventor： Sgargi, Andrea

IPC: G21F9/02 ,  G21F9/32 ,  B01D53/68

CPC classification number: G21F9/32 ,  B01D53/14 ,  B01D2252/103 ,  G21F9/02 ,  G21Y2002/60 ,  G21Y2004/20 ,  G21Y2004/201

Abstract: There is provided a method (1) for disposing of waste (2), in which the waste (2) is radioactive waste and the method (1) comprises a first step (1a) in which pre-treatment waste (2a) is placed inside a pyrolytic reactor (3), a second step (1b), in which the pre-treatment waste (2a) is thermally disintegrated by pyrolysis into treated waste (4), the treated waste (4) comprising a solid phase (40) and a gaseous phase (41), and the method (1) further comprising a third step (1c) in which the solid phase (40) is stored according to known radioactive waste storage procedures and a fourth step (1d) in which the gaseous phase (41) is expelled into the outside environment.