公开(公告)号：EP1556869B1

公开(公告)日：2011-12-07

申请号：EP03809908.1

申请日：2003-10-30

Applicant: Westinghouse Electric Sweden AB

Inventor： DAHLBÄCK, Mats ,  HALLSTADIUS, Lars

IPC: G21C3/07 ,  G21C21/02 ,  C22F1/18

CPC classification number: C22C16/00 ,  C22F1/186 ,  G21C3/07 ,  G21Y2002/103 ,  G21Y2002/104 ,  G21Y2004/10 ,  G21Y2004/201 ,  G21Y2004/40 ,  Y02E30/40 ,  Y10T29/49391

Abstract: The invention concerns a method of producing a cladding tube for nuclear fuel for a nuclear pressure water reactor. According to the method, a tube is formed which at least principally consists of a cylindrical tube component (1) of a Zr-based alloy, with a Nb content between 0.5 and 2.4 weight percent. The cladding tube is finally annealed at a temperature and during a time such that said tube component (1) is partly recrystallized but not completely recrystallized. The invention also concerns a cladding tube, a fuel assembly for a pressure water reactor and the use of a cladding tube.

公开(公告)号：EP1329905B1

公开(公告)日：2010-09-08

申请号：EP02015569.3

申请日：2002-07-12

Applicant: MITSUBISHI HEAVY INDUSTRIES, LTD.

Inventor： Monaka, Kazuki, c/o Kobe Shipyard & Machinery Works ,  Shimizu, Juntaro, c/o Kobe Shipyard & Machinery Works ,  Yamaguchi, Yoichiro, c/o Takasago Research & Development Center,

IPC: G21C3/07 ,  G21C3/12

CPC classification number: G21C3/07 ,  G21C3/12 ,  G21Y2002/103 ,  G21Y2004/201 ,  G21Y2004/202 ,  Y02E30/40 ,  Y10S148/908 ,  Y10S376/90

公开(公告)号：EP1927997B1

公开(公告)日：2009-07-29

申请号：EP07254656.7

申请日：2007-11-30

Applicant: Studsvik, Inc.

Inventor： Mason, J.Bradley

IPC: G21F9/28 ,  G21F9/32

CPC classification number: G21F9/28 ,  G21F9/32 ,  G21Y2002/20 ,  G21Y2002/50 ,  G21Y2002/501 ,  G21Y2004/201 ,  G21Y2004/40

公开(公告)号：EP1329905A2

公开(公告)日：2003-07-23

申请号：EP02015569.3

申请日：2002-07-12

Applicant: Mitsubishi Heavy Industries, Ltd.

Inventor： Monaka, Kazuki, Kobe Shipyard & Machinery Works ,  Shimizu, Juntaro, Kobe Shipyard & Machinery Works ,  Yamaguchi, Yoichiro, Takasago Research & Develop.

IPC: G21C3/07 ,  G21C3/12

CPC classification number: G21C3/07 ,  G21C3/12 ,  G21Y2002/103 ,  G21Y2004/201 ,  G21Y2004/202 ,  Y02E30/40 ,  Y10S148/908 ,  Y10S376/90

Abstract: A method of surface-treating a reactor member for effectively removing a Cr-deficient layer and a work-hardened layer considered to be a cause of stress-corrosion cracking (SCC) under low-stress conditions. The method of surface-treating a reactor member which is worked by bending (step 1) and then processed by a heat treatment (step 2), in which a work-hardened layer is formed by the bending, and in which a Cr-deficient layer is formed due to an oxide film attached by the heat treatment, uses at least one of: acid wash; grinding; electrolytic polishing; electro-discharge machining; surface cutting; surface deoxidation and softening; wet blasting; laser machining; or surface plating (step 3) to remove the work-hardened layer and the Cr-deficient layer from the reactor member or to prevent contact of the work-hardened layer and the Cr-deficient layer of the reactor member with a primary coolant.

Abstract translation: 表面处理的反应器部件，用于有效地除去的Cr缺乏层，被认为是的应力腐蚀低应力条件下开裂（SCC）的原因的加工硬化层的方法。 的表面处理的反应器部件的所有其由弯曲加工（步骤1），然后处理进行热处理（步骤2），在该加工硬化层通过弯曲而形成，并且其中所述的Cr-缺陷的方法 层被形成由于膜附着通过热处理，使用中的至少一种氧化物：酸洗; 磨; 电解抛光; 电火花加工; 切割表面; 表面脱氧和软化; 湿法喷砂; 激光加工; 或表面镀敷（步骤3），以除去加工硬化层并从反应器构件在Cr缺乏层，或防止加工硬化层和反应器部件的与一次冷却材料在Cr缺乏层的接触。

公开(公告)号：EP1046174A1

公开(公告)日：2000-10-25

申请号：EP99906113.8

申请日：1999-01-11

Applicant: FORSCHUNGSZENTRUM JÜLICH GMBH

Inventor： BRÖCKERHOFF, Peter ,  VON LENSA, Werner ,  REINECKE, Ernst-Arndt ,  VOSWINKEL, Moritz

IPC: G21C9/06 ,  G21C19/317

CPC classification number: G21C19/317 ,  G21C9/06 ,  G21Y2002/201 ,  G21Y2002/207 ,  G21Y2002/50 ,  G21Y2004/201 ,  G21Y2004/30 ,  Y02E30/40

Abstract: The invention relates to a device for the catalytic conversion of hydrogen. The device is used for eliminating hydrogen which has been produced as a result of an incident. Said hydrogen is eliminated effectively and without producing a backfire. The aim of the invention is to improve the effect of the recombiner and to prevent the containment atmosphere from heating up. To this end, a recombiner (8) with a plurality of catalytically effective catalyst elements (8a) is arranged in the containment containing the gas mixture, a cooling device (10) is placed downstream from the recombiner (8) and a further cooling device (4) is placed upstream of the recombiner (8).

公开(公告)号：EP0760017A1

公开(公告)日：1997-03-05

申请号：EP95923640.0

申请日：1995-06-20

Applicant: SANDVIK AKTIEBOLAG

Inventor： ANDERSSON, Thomas

IPC: G21C3 ,  C22C16 ,  C22F1

CPC classification number: G21C3/07 ,  C22F1/186 ,  G21Y2002/103 ,  G21Y2002/206 ,  G21Y2004/201 ,  Y02E30/40

Abstract: The present invention relates to a method of manufacturing tubes of zirconium based alloys for usage in nuclear reactors. According to the invention one can achieve good resistance towards general corrosion, improved transversal creep strength and reduced irradiation induced growth by subjecting a β-quenched tube a vacuum anneal in the α-phase range at a temperature and a time sufficient to obtain an annealing parameter value A in the range 3.4 x 10-16 to 3.4 x 10-13.

公开(公告)号：EP0745258A1

公开(公告)日：1996-12-04

申请号：EP94919956.0

申请日：1994-06-22

Applicant: ABB ATOM AB

Inventor： RUDLING, Peter

IPC: C22F1 ,  G21C3

CPC classification number: G21C3/07 ,  C22F1/186 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/201 ,  Y02E30/40

Abstract: The present invention relates to a nuclear fuel element for a pressurized-water reactor, PWR. The fuel element comprises cladding tubes or cladding tubes and guide tubes, whose composition and manufacture are so adapted that the cladding or the cladding and the guide tubes during reactor operation show a good resistance to general corrosion and a low hydrogen contents. This can be achieved by allowing the cladding or the cladding and the guide tubes, when being manufactured, to undergo heat treatments which are of such a nature that the cumulative annealing parameter ⊤A = ⊤ti exp (-Q/RTi) is at most 1.25 x 10-14, at Q/R = 31726 K.

公开(公告)号：EP0725155A2

公开(公告)日：1996-08-07

申请号：EP96100999.0

申请日：1996-01-24

Applicant: HITACHI, LTD.

Inventor： Aono, Yasuhisa ,  Yoshinari, Akira ,  Kondo, Yasuo ,  Kaneda, Junya ,  Kodama, Hideyo ,  Kato, Takahiko ,  Hattori, Shigeo ,  Arai, Masahiko

IPC: C22C38/40 ,  C30B11/00 ,  C30B29/52 ,  G21C3/07 ,  G21C17/01

CPC classification number: G21C21/00 ,  C21D6/004 ,  C21D6/02 ,  C21D2201/04 ,  C21D2211/001 ,  C22C38/40 ,  C30B29/52 ,  C30B33/00 ,  G21C3/07 ,  G21C5/10 ,  G21C13/087 ,  G21Y2002/101 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/201 ,  G21Y2004/504 ,  Y02E30/40 ,  Y10S376/90

Abstract: In order to provide austenitic single crystal stainless steel having preferable stress corrosion cracking resistance, strength, and irradiation induced embrittlement resistance so as to extend life of nuclear reactor core structure which is used under a high radiation dose environment, a method is disclosed, which comprises the steps of homogeneously dispersing carbides into a parent phase of the austenitic single crystal stainless steel by a two step solution heat treatment, and subsequent an ageing heat treatment after rapid cooling for precipitating fine carbides.

Abstract translation: 为了提供具有优良的耐应力腐蚀开裂性，强度和抗辐照引起的抗脆性的奥氏体单晶不锈钢，以延长在高辐射剂量环境下使用的核反应堆芯结构的寿命，公开了一种方法，其包括 通过两步固溶热处理将碳化物均匀分散到奥氏体单晶不锈钢的母相中，然后在快速冷却后进行时效热处理以沉淀细碳化物的步骤。

公开(公告)号：EP0706706A1

公开(公告)日：1996-04-17

申请号：EP94920626.0

申请日：1994-06-29

Applicant: ABB ATOM AB

Inventor： VESTERLUND, Gunnar ,  DAHLBÄCK, Mats

IPC: G21C3 ,  C22C16 ,  C22F1 ,  G21C21 ,  G21D1

CPC classification number: C22F1/186 ,  G21C3/06 ,  G21C21/00 ,  G21Y2002/103 ,  G21Y2004/201 ,  Y02E30/40

Abstract: The invention relates to a fuel element for a pressurized-water reactor comprising a number of fuel rods arranged in a square lattice and wherein certain positions in the lattice contain guide tubes for receiving control rods, wherein the fuel element can be used for higher burnup by manufacturing the guide tubes of the element such that their irradiation-induced growth is reduced and their corrosion resistance is increased compared with conventionally manufactured guide tubes. This is achieved by finally heat-treating the guide tubes in two steps, the first step being a beta quenching and the second step a heat treatment in the alpha-phase region.

公开(公告)号：EP0651396A1

公开(公告)日：1995-05-03

申请号：EP94307316.3

申请日：1994-10-05

Applicant: GENERAL ELECTRIC COMPANY

Inventor： Adamson, Ronald Bert ,  Lutz, Daniel Reese

IPC: G21C3/20

CPC classification number: G21C3/20 ,  G21Y2002/103 ,  G21Y2004/201 ,  Y02E30/40 ,  Y10T428/12458 ,  Y10T428/12806

Abstract: A method for fabricating a composite cladding comprised of a moderate-purity metal barrier of zirconium metallurgically bonded on the inside surface of a zirconium alloy tube which improves corrosion resistance. The improved corrosion resistance of the liner is accomplished by suitable heat treatment of the Zircaloy-zirconium composite cladding to allow diffusion of alloying elements, notably Fe and Ni, from the Zircaloy into the zirconium, in particular, to the inner surface of the zirconium liner. This diffusion anneal reduces the undesirable tendency of zirconium liner to oxidize rapidly.

Abstract translation: 一种用于制造由锆的中等纯度的金属阻挡冶金结合锆合金管从而提高耐腐蚀性的内表面上的复合物覆层的方法。 衬套的改进的耐腐蚀性由锆锡合金锆复合包层的适当的热处理来实现，以允许的合金元素，特别是Fe和Ni的扩散，从Zircaloy合金成锆，特别地，所述锆衬的内表面 ， 这种扩散退火降低锆衬里的不良现象迅速氧化。