公开(公告)号：US4927468A

公开(公告)日：1990-05-22

申请号：US278068

申请日：1988-11-30

Applicant: Gerald D. Johnson ,  Ralph J. Lobsinger ,  Margaret L. Hamilton ,  David S. Gelles

Inventor： Gerald D. Johnson ,  Ralph J. Lobsinger ,  Margaret L. Hamilton ,  David S. Gelles

IPC: G21C3/06 ,  C21D6/00 ,  C22C38/00 ,  C22C38/22 ,  C22C38/24 ,  C22C38/26 ,  C22C38/32 ,  C22C38/54 ,  G21C3/07

CPC classification number: C22C38/32 ,  C22C38/22 ,  C22C38/24 ,  C22C38/26 ,  G21C3/07 ,  G21Y2002/104 ,  G21Y2004/10 ,  G21Y2004/201 ,  Y02E30/40

Abstract: This is a very narrowly defined martensitic steel alloy fuel cladding material for liquid metal cooled reactors, and a process for making such a martensitic steel alloy material. The alloy contains about 10.6 wt. % chromium, about 1.5 wt. % molybdenum, about 0.85 wt. % manganese, about 0.2 wt. % niobium, about 0.37 wt. % silicon, about 0.2 wt. % carbon, about 0.2 wt. % vanadium, 0.05 maximum wt. % nickel, about 0.015 wt. % nitrogen, about 0.015 wt. % sulfur, about 0.05 wt. % copper, about 0.007 wt. % boron, about 0.007 wt. % phosphorous, and with the remainder being essentially iron. The process utilizes preparing such an alloy and homogenizing said alloy at about 1000.degree. C. for 16 hours; annealing said homogenized alloy at 1150.degree. C. for 15 minutes; and tempering said annealed alloy at 700.degree. C. for 2 hours. The material exhibits good high temperature strength (especially long stress rupture life) at elevated temperature (500.degree.-760.degree. C.).

公开(公告)号：US4918710A

公开(公告)日：1990-04-17

申请号：US235593

申请日：1988-08-24

Applicant: Josette Bard

Inventor： Josette Bard

IPC: C22F1/18 ,  G21C3/34

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

Abstract: A zirconium alloy sheet containing 2 to 3% of niobium is cooled at a controlled and moderate rate to the .alpha.+.beta. state. Plates (2, 2') are cut from the cooled sheet and cold-formed. The grid (1) is assembled from the plates (2, 2') which are welded together and the completed grid is then returned to the .alpha. phase by heating at a temperature of between 400.degree. and 550.degree. C. for a period of ten to thirty hours.

Abstract translation: 将含有2〜3％铌的锆合金板以受控和适度的速率冷却至α+β状态。 从冷却片切割板（2,2'）并冷成型。 格栅（1）从焊接在一起的板（2,2'）组装，然后通过在400-550℃的温度下加热完成的格子返回到α相，持续十分钟 至三十小时。

公开(公告)号：US4863679A

公开(公告)日：1989-09-05

申请号：US59175

申请日：1987-06-12

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

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

IPC: G21C3/20

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

Abstract: 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 and an outer zirconium alloy layer. 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 is greater than 1.0, (II) the zirconium liner layer 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 and/or the outer surface of the zirconium alloy layer have been removed substantially. Owing to these features, undesirable stress corrosion cracking and local corrosion are remarkably suppressed in the cladding tube and the nuclear fuel element of the invention.

Abstract translation: 公开了一种用于核燃料的包覆管和结合有包层管的核燃料元件。 包层管由内锆衬层和外锆合金层组成。 包壳管具有以下特征中的至少一个：（I）锆衬层中氧含量a与铁含量b的比a / b大于1.0，（II）锆衬层由 锆溶解在其中溶解有杂质的基质中，并且（III）已经除去了具有微观尺寸并分散在锆衬层的内表面和/或锆合金层的外表面的第二相颗粒。 由于这些特征，在本发明的包层管和核燃料元件中，显着地抑制了不期望的应力腐蚀开裂和局部腐蚀。

公开(公告)号：US4762675A

公开(公告)日：1988-08-09

申请号：US50177

申请日：1987-05-15

Applicant: Alexander L. Feild, Jr.

Inventor： Alexander L. Feild, Jr.

IPC: C23C16/04 ,  C23C16/18 ,  C23C16/28 ,  G21C3/18 ,  G21C3/06

CPC classification number: C23C16/18 ,  C23C16/045 ,  C23C16/28 ,  G21C3/18 ,  G21Y2002/104 ,  G21Y2002/303 ,  G21Y2004/10 ,  G21Y2004/20 ,  G21Y2004/201 ,  G21Y2004/40

Abstract: A process for forming a boron-containing coating on the internal surface of a zirconium or zirconium alloy hollow tube by heating the internal surface to a temperature of between 200.degree.-450.degree. C. and passing through the tube a mixture of a volatilized boron compound in helium or argon, such that the boron compound decomposes to form an integral boron containing coating on the internal surface.

Abstract translation: 在锆或锆合金中空管的内表面上形成含硼涂层的方法是将内表面加热至200-450℃的温度，并通过管将挥发的硼化合物 在氦气或氩气中，使得硼化合物在内表面上分解形成一体的含硼涂层。

公开(公告)号：US4584030A

公开(公告)日：1986-04-22

申请号：US571122

申请日：1984-01-13

Applicant: Samuel G. McDonald ,  George P. Sabol

Inventor： Samuel G. McDonald ,  George P. Sabol

IPC: C22F1/18 ,  G21C3/07 ,  G21C3/06

CPC classification number: G21C3/07 ,  C22F1/186 ,  G21Y2002/103 ,  G21Y2004/201 ,  Y02E30/40 ,  Y10S376/90

Abstract: It has been found that 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: 已经发现，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，导致具有优异的耐高温蒸汽腐蚀性的Zircaloy合金产品。

公开(公告)号：US4576654A

公开(公告)日：1986-03-18

申请号：US438515

申请日：1982-11-01

Applicant: Fletcher C. Eddens ,  David W. White ,  John L. Harmon

Inventor： Fletcher C. Eddens ,  David W. White ,  John L. Harmon

IPC: C22F1/18 ,  G21C21/02

CPC classification number: C22F1/186 ,  G21C21/02 ,  G21Y2002/103 ,  G21Y2004/10 ,  G21Y2004/201

Abstract: There is provided a nuclear fuel element having a zirconium alloy cladding tube with improved corrosion resistance. The cladding tube comprises a metallurgical gradient across the width of the tube wall wherein the tube has a more corrosion-resistant metallurgical condition at the outer circumference and a less corrosion-resistant metallurgical condition at the inner circumference. The metallurgical gradient can be generated by heating an outer circumferential portion of the tube to the high alpha or mixed alpha plus beta range while maintaining the inner surface at a lower temperature, followed by cooling of the tube.

Abstract translation: 提供了具有耐腐蚀性提高的锆合金包覆管的核燃料元件。 包层管包括横跨管壁的宽度的冶金梯度，其中管在外周具有更耐蚀的冶金条件，在内圆周处具有较少的耐腐蚀冶金条件。 可以通过将管的外周部分加热到高α或混合α+β范围同时将内表面保持在较低温度，随后冷却管而产生冶金梯度。

公开(公告)号：US3510545A

公开(公告)日：1970-05-05

申请号：US3510545D

申请日：1967-12-08

Applicant: SUMITOMO ELECTRIC INDUSTRIES

Inventor： NISHIYAMA ATSUSHI ,  KASAMATSU TOSHIO

IPC: G21C3/62 ,  G21C7/04 ,  G21C21/04 ,  G21C21/08 ,  G21C3/04

CPC classification number: G21C3/623 ,  G21C7/04 ,  G21C21/04 ,  G21Y2002/104 ,  G21Y2004/10 ,  G21Y2004/201 ,  G21Y2004/40 ,  Y02E30/38 ,  Y02E30/39

公开(公告)号：US3427222A

公开(公告)日：1969-02-11

申请号：US3427222D

申请日：1965-10-15

Applicant: WESTINGHOUSE ELECTRIC CORP

Inventor： BIANCHERIA AMILCARE ,  ALLIO ROBERT J

IPC: G21C3/18 ,  G21C3/20 ,  G21C3/62 ,  G21C7/04 ,  G21C3/02 ,  G21C3/06 ,  G21C3/30

CPC classification number: G21C3/62 ,  G21C3/18 ,  G21C3/20 ,  G21C7/04 ,  G21Y2002/104 ,  G21Y2002/303 ,  G21Y2002/304 ,  G21Y2004/10 ,  G21Y2004/201 ,  G21Y2004/40 ,  Y02E30/38 ,  Y02E30/39

公开(公告)号：US3325363A

公开(公告)日：1967-06-13

申请号：US27219963

申请日：1963-04-11

Applicant: GEN DYNAMICS CORP

Inventor： GOEDDEL WALTER V ,  LUBY CHARLES S

IPC: C23C16/26 ,  G21C3/62 ,  G21C7/04

CPC classification number: G21C7/04 ,  C23C16/26 ,  G21C3/626 ,  G21Y2002/104 ,  G21Y2004/10 ,  G21Y2004/201 ,  G21Y2004/40 ,  Y02E30/38 ,  Y02E30/39

公开(公告)号：US07459037B2

公开(公告)日：2008-12-02

申请号：US11041305

申请日：2005-01-25

Applicant: Kazuki Monaka ,  Juntaro Shimizu ,  Yoichiro Yamaguchi

Inventor： Kazuki Monaka ,  Juntaro Shimizu ,  Yoichiro Yamaguchi

IPC: C21D9/02 ,  C21D7/06 ,  C21D7/08

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: 在低应力条件下，有效地除去被认为是应力腐蚀开裂原因（SCC）的Cr缺陷层和加固硬化层的反应器构件的表面处理方法。 表面处理通过弯曲（步骤1）进行加工，然后通过热处理（步骤2）进行加工的反应器构件的表面处理方法，其中通过弯曲形成加工硬化层，并且其中Cr缺陷 由于通过热处理而附着的氧化膜形成层，使用以下中的至少一种：酸洗; 研磨 电解抛光; 放电加工; 表面切割; 表面脱氧和软化; 湿喷 激光加工; 或表面电镀（步骤3）以从反应器构件去除加固硬化层和Cr缺陷层，或者防止加固硬化层和反应器构件的Cr缺陷层与初级冷却剂接触。