-
公开(公告)号：CN1032258A
公开(公告)日：1989-04-05
申请号：CN88106836
申请日：1988-08-23
Inventor： 巴德·约瑟特
IPC: G21C3/34
CPC classification number: C22F1/186 , G21C3/3424 , G21Y2002/104 , G21Y2002/302 , G21Y2004/201 , G21Y2004/40 , Y02E30/40
Abstract: 一种含铌为2—3％的锆合金板按一种有规律的、缓慢的速率冷却剂α+β相，板(2，2′)是由冷却后的板材切割和冷却加工而成的。板材(2，2′)通过焊接组装成栅格(1)，然后整个栅格加热到400—550℃之间的α相维持10—30小时。
-
公开(公告)号：CN1030261A
公开(公告)日：1989-01-11
申请号：CN88103765
申请日：1988-06-23
Applicant: 弗拉马托姆联合股份公司 , 皮西尼和弗拉马托姆铀合股公司
CPC classification number: G21C3/07 , C22C16/00 , C22F1/186 , G21Y2002/103 , G21Y2002/104 , G21Y2004/10 , G21Y2004/20 , G21Y2004/201 , Y02E30/40
Abstract: 本发明涉及用于反应堆并由锆基合金制成的燃料元件包壳管的制造方法，它包括多道连续轧制和退火过程，本发明还涉及该方法对具体合金的应用。其特征在于该方法的最终步骤是通过加热到温度为950℃和1250℃之间使整个元件在β相中均质的热处理之后，进行快速冷却到室温。
-
公开(公告)号：WO1993001319A1
公开(公告)日：1993-01-21
申请号：PCT/DE1991000566
申请日：1991-07-10
Applicant: SIEMENS AKTIENGESELLSCHAFT
Inventor： SIEMENS AKTIENGESELLSCHAFT , ALTER, Dietrich , DEWES, Peter , GARZAROLLI, Friedrich , HAHN, Roland
IPC: C21D06/02
CPC classification number: C22C38/38 , C21D6/004 , C21D6/02 , C21D2211/001 , C21D2211/004 , C22C38/48 , G21C3/07 , G21C7/00 , G21C21/18 , G21Y2002/103 , G21Y2002/104 , G21Y2004/10 , G21Y2004/201 , Y02E30/39
Abstract: Austenitic steel for nuclear reactor components is largely resistant to radiation-induced stress cracking corrosion if the silicon, phosphorus and sulphur content is reduced by comparison with commercial grades of steel and its grain structure has finely dispersed and distributed carbide deposits, especially niobium carbide. The finely dispersed distribution can be obtained if larger niobium deposits are first disagregated by annealing at 1100 to 1150 DEG C and the carbide is deposited by subsequent annealing at temperatures of about 750 DEG C.
Abstract translation: 如果与商业级别的钢相比，硅，磷和硫含量降低，其核反应堆组分的奥氏体钢大部分抵抗辐射诱发的应力开裂腐蚀，其晶粒结构具有细分散和分布的碳化物沉积物，特别是碳化铌。 如果较大的铌沉积物首先通过1100至1150℃的退火而脱落，并且碳化物通过随后在约750℃的温度退火而沉积，则可以获得细分散的分布。
-
14.发明申请FUEL ROD CLADDING TUBE FOR A BOILING WATER REACTOR FUEL ROD AND THE PRODUCTION THEREOF 审中-公开包层的燃料棒的管FOR A沸水反应堆燃料元件及其制造
公开(公告)号：WO98040893A1
公开(公告)日：1998-09-17
申请号：PCT/EP1998/001105
申请日：1998-02-26
CPC classification number: G21C3/07 , C21D9/085 , C22F1/186 , G21Y2002/103 , G21Y2002/104 , G21Y2002/202 , G21Y2004/201 , G21Y2004/403 , Y02E30/40
Abstract: The invention relates to a cladding tube (1) which is practically homogenous as far as chemical composition and particle structure is concerned and is made of zircalloy components, exhibiting an elongation at rupture of at least 20 % with a ductility parameter gamma = (a)
Abstract translation: 包壳管（1）在化学组成和从锆锡合金的成分的晶粒结构几乎均匀的方面被构造和包含Duktilitätsparameter伽马=（A）<3.5（伽玛=Duktilitätsparameter，KD =平均粒径; FR =基恩斯因子）一 伸长率的至少20％的断裂由低温处理的挤出管坯的设定。 于挤压，一个起始体使用具有被β-淬火在各区域中沉淀的二次粒子的定义的不同的分布形成为从所述内表面（6）和外表面（7）挤压管。 在所述内表面（6），所述颗粒（8）具有较大的直径和平均距离，所述分配是由“间距”（粒子的平均距离披= 1微米内更大克（内表面6）至少在所描述 20微米，颗粒（9）为至多200微米的外表面上更大的外面披克= 1.8微米）。
-
15.发明申请ZIRCONIUM ALLOY TUBE FOR A NUCLEAR REACTOR FUEL ASSEMBLY, AND METHOD FOR MAKING SAME 审中-公开用于核反应堆燃料组件的ZIRCONIUM合金管及其制造方法
公开(公告)号：WO1996024140A1
公开(公告)日：1996-08-08
申请号：PCT/FR1996000137
申请日：1996-01-26
Applicant: FRAMATOME , COMPAGNIE GENERALE DES MATIERES NUCLEAIRES , MARDON, Jean-Paul , SEVENAT, Jean , CHARQUET, Daniel
Inventor： FRAMATOME , COMPAGNIE GENERALE DES MATIERES NUCLEAIRES
IPC: G21C03/07
CPC classification number: G21C3/07 , G21Y2002/103 , G21Y2004/10 , G21Y2004/201 , Y02E30/40
Abstract: A tube for forming a nuclear fuel assembly guide tube or sheath. The tube is made of an alloy containing 1.0-1.7 wt % of tin, 0.55-0.8 wt % of iron, 0.20-0.60 wt % total of chromium and/or vanadium, and 0.10-0.18 wt % of oxygen, carbon and silicon being present in amounts of 100-180 ppm and 50-120 ppm respectively, while the only other components of the alloy are zirconium and the unavoidable impurities.
Abstract translation: 一种用于形成核燃料组件引导管或护套的管。 该管由含有1.0-1.7重量％的锡，0.55-0.8重量％的铁，0.20-0.60重量％的铬和/或钒的总量和0.10-0.18重量％的氧，碳和硅的合金制成 分别以100-180ppm和50-120ppm的量存在，而合金中唯一的其它组分是锆和不可避免的杂质。
-
Patent Agency Ranking
公开(公告)号：WO1993001318A1
公开(公告)日：1993-01-21
申请号：PCT/DE1991000565
申请日：1991-07-10
Applicant: SIEMENS AKTIENGESELLSCHAFT
Inventor： SIEMENS AKTIENGESELLSCHAFT , ALTER, Dietrich , DEWES, Peter , GARZAROLLI, Friedrich , HAHN, Roland
IPC: C21D06/00
CPC classification number: C22C38/38 , C21D6/004 , C22C38/40 , C22C38/48 , G21C3/07 , G21C7/00 , G21C21/18 , G21Y2002/103 , G21Y2002/104 , G21Y2004/10 , G21Y2004/201 , Y02E30/39
Abstract: Austenitic steel for nuclear reactor components is largely resistant to radiation-induced stress cracking corrosion if the silicon, phosphorus and sulphur content is reduced by comparison with commercial grades of steel and its grain structure has a mean grain diameter of under some 20 mu m. This grain structure is obtained if annealing processes above some 950 DEG C are avoided. Finely dispersed carbide deposits in the grains also provide increased resistance to radiation-induced stress cracking corrosion if the annealing temperatures are increased to about 1075 DEG C.
Abstract translation: 如果与商业级别的钢相比，硅，磷和硫含量降低，核反应堆组分的奥氏体钢大部分抵抗辐射诱发的应力开裂腐蚀，其晶粒结构的平均粒径在20微米左右。 如果避免高于950℃的退火过程，则获得这种晶粒结构。 如果将退火温度提高到约1075℃，则细粒分散的碳化物沉积物也提供了对辐射诱发的应力开裂腐蚀的增加的抗性。
-
公开(公告)号：WO99036923A1
公开(公告)日：1999-07-22
申请号：PCT/EP1999/000107
申请日：1999-01-11
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).
Abstract translation: 本发明涉及一种用于氢气的催化转化被有效地消除，并与事故引起所产生的氢再起弧，并由此解决了技术问题，以提高再化合的效果并抑制壳气氛的加热，即一个复合器（ 8）设置有多个（在该冷却装置（10）的下游设置在所述复合器（8）的含气体混合物遏制催化作用的催化剂元件8a），并且进一步的冷却器（4）流（再化合8的上游） 布置。
-
18.发明申请METHOD FOR THE MANUFACTURE OF TUBES OF A ZIRCONIUM BASED ALLOY FOR NUCLEAR REACTORS AND THEIR USAGE 审中-公开制造用于核反应堆的基于锆的合金管的方法及其用途
公开(公告)号：WO1995035395A1
公开(公告)日：1995-12-28
申请号：PCT/SE1995000749
申请日：1995-06-20
Applicant: SANDVIK AB , ANDERSSON, Thomas
Inventor： SANDVIK AB
IPC: C22C16/00
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 beta -quenched tube a vacuum anneal in the alpha -phase range at a temperature and a time sufficient to obtain an annealing parameter value A in the range 3.4 x 10 to 3.4 x 10 .
Abstract translation: 本发明涉及一种用于核反应堆的锆基合金管的制造方法。 根据本发明，可以在足以获得退火参数的温度和时间下使β淬灭管在α相范围内进行真空退火，从而可以获得对一般腐蚀的良好抵抗，改进的横向蠕变强度和减少的辐射诱导生长 范围3.4×10 < - 16>至3.4×10 <-13>的值A。
-
19.发明申请A NUCLEAR FUEL ELEMENT FOR A PRESSURIZED WATER REACTOR AND A METHOD FOR MANUFACTURING THE SAME 审中-公开一种用于增压水反应器的核燃料元件及其制造方法
公开(公告)号：WO1995000955A1
公开(公告)日：1995-01-05
申请号：PCT/SE1994000619
申请日：1994-06-22
Applicant: ABB ATOM AB , RUDLING, Peter
Inventor： ABB ATOM AB
IPC: G21C03/07
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 SIGMA A = SIGMA ti exp (-Q/RTi) is at most 1.25 x 10 , at Q/R = 31726 K.
Abstract translation: 本发明涉及一种用于加压水反应堆的核燃料元件，PWR。 燃料元件包括包层管或包覆管和导管，其组成和制造适于在反应器操作期间使包层或包层和导管显示出良好的抗一般腐蚀性和低氢含量。 这可以通过允许包层或包层和导管在制造时进行热处理来实现，这些热处理的性质使得累积退火参数SIGMA A = SIGMA ti exp（-Q / RTi）至多为 1.25×10 14，在Q / R = 31726K。
-
公开(公告)号：JP3955097B2
公开(公告)日：2007-08-08
申请号：JP53879497
申请日：1997-04-21
Applicant: ウエスチングハウス エレクトリック スウェーデン アクチボラグ
Inventor： ダールバック，マッツ
CPC classification number: G21C3/324 , G21Y2002/104 , G21Y2004/201 , Y02E30/40
-
-
-
-
-
-
-
-
-
Search Results
255
records
(took 0.067 seconds)
