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1. 发明授权

US4820359A Process for thermally stress-relieving a tube 失效
标题翻译：热应力释放管的工艺
公开(公告)号：US4820359A
公开(公告)日：1989-04-11
申请号：US24941
申请日：1987-03-12
申请人： Bruce W. Bevilacqua , Wenche W. Cheng , Donald R. Stoner , Fredric W. Pement , Robert D. Burack , Joseph M. Gilkison
发明人： Bruce W. Bevilacqua , Wenche W. Cheng , Donald R. Stoner , Fredric W. Pement , Robert D. Burack , Joseph M. Gilkison
IPC分类号： C21D9/08 , C22F1/00 , C22F1/10 , H05B3/06 , B23K1/02
CPC分类号： C21D9/08 , C22F1/10
摘要： A process for thermally stress-relieving a stressed portion of a metallic tube is disclosed herein. The process generally comprises the steps of inserting a small diameter radiant heater into the open end of the metallic conduit and then positioning it adjacent to the portion to be stress relieved, and heating this portion to a temperature between about 1150.degree. F. to 1500.degree. F. for a time period of between about four and twelve minutes, depending upon wall thickness. In order to determine the proper amount of electrical power to apply to the radiant heater, the emissivity of the stressed portion of the conduit is first measured by heating a portion of the section to incandescence at a known power level, and then determining the temperature of the incandescent tube by means of a pyrometer which compares the intensity of two selected colors or wavelengths of the transmitted light. This process is particularly useful in thermally stress-relieving the U-bends of heat exchanger tubes formed from Inconel.RTM. 600 that are used in nuclear steam engines. It may also be used to stress-relieve such heat exchanger tubes in regions where the reinforcing sleeves have been welded into their interiors. Such thermal stress relieving renders the tubes less susceptible to intragranular stress corrosion cracking.

2. 发明授权

US5108697A Inhibiting stress corrosion cracking in the primary coolant circuit of a nuclear reactor 失效
标题翻译：抑制核反应堆主冷却回路中的应力腐蚀开裂
公开(公告)号：US5108697A
公开(公告)日：1992-04-28
申请号：US600465
申请日：1990-10-19
申请人： John N. Esposito , Judith B. Esposito , Fredric W. Pement
发明人： John N. Esposito , Judith B. Esposito , Fredric W. Pement
IPC分类号： G21C15/28 , C23F11/18 , G21C19/28 , G21D1/00 , G21D3/08
CPC分类号： G21C19/28 , C23F11/18
摘要： A primary coolant circuit for cooling a nuclear reactor has wetted mechanically stressed nickel base alloy components such as Alloy 600 tubes in steam generators having oxidized surfaces comprising 1-10 w/o zinc, which tubes are inhibited against primary water stress corrosion cracking. The crack initiation times may be delayed by a factor of two in pressurized water nuclear reactors.
摘要翻译：用于冷却核反应堆的主要冷却剂回路具有润湿机械应力的镍基合金部件，例如具有包含1-10w / o锌的氧化表面的蒸汽发生器中的合金600管，该管防止初级水应力腐蚀开裂。在加压水核反应堆中，裂纹开始时间可能会延迟2倍。

3. 发明授权

US5034190A Apparatus for conducting accelerated corrosion testing of nickel alloys 失效
标题翻译：镍合金加速腐蚀试验装置
公开(公告)号：US5034190A
公开(公告)日：1991-07-23
申请号：US183260
申请日：1988-04-08
申请人： George Economy , Richard J. Jacko , Fredric W. Pement , Alfred W. Klein
发明人： George Economy , Richard J. Jacko , Fredric W. Pement , Alfred W. Klein
IPC分类号： G01N17/00
CPC分类号： G01N17/00
摘要： Both an improved method and apparatus for determining, on an accelerated basis, the susceptibility of a nickel-based alloy to suffer stress corrosion cracking within a steam generator environment is disclosed herein. The method generally comprises the steps of subjecting a mechanically stressed specimen of the alloy to a mixture of steam and hydrogen at a temperature of between about 365.degree. C. to 435.degree. C., wherein the partial steam pressure is between about 10.4 MPa to 30.4 MPa, and the partial hydrogen pressure is between about 32 kPa to 500 kPa. The improved testing apparatus of the invention generally comprises a vessel for containing a stressed specimen and a pressurized atmosphere formed of steam and hydrogen, and an inlet cell for injecting a selected amount of hydrogen into the pressurized atmosphere of the vessel which includes a diffusion membrane which is permeable to hydrogen but impermeable to the remainder of the pressurized atmosphere. The inlet cell has a tubular housing having a wall formed from a thin layer of hydrogen permeable palladium-silver alloy. The tubular housing contains a gas permeable sponge formed by sintered particles of stainless steel to prevent the thin layer of palladium-silver alloy used in the hydrogen diffusion membrane from imploding in response to the pressure within the vessel.
摘要翻译：本文公开了一种用于在加速的基础上确定镍基合金在蒸汽发生器环境内遭受应力腐蚀开裂的敏感性的改进的方法和装置。该方法通常包括以下步骤：在约365℃至435℃的温度下使合金的机械应力样品经受蒸汽和氢气的混合物，其中部分蒸汽压力为约10.4MPa至30.4 MPa，部分氢压为约32kPa至500kPa。本发明的改进的测试装置通常包括用于容纳应力样品和由蒸汽和氢气形成的加压气氛的容器，以及用于将选定量的氢气注入到容器的加压气氛中的入口单元，该容器包括扩散膜，对氢气是可渗透的，但对其余的加压气氛是不可渗透的。入口单元具有管状壳体，其具有由可透氢钯 - 银合金薄层形成的壁。管状壳体包含由不锈钢烧结颗粒形成的透气海绵，以防止氢扩散膜中使用的钯 - 银合金薄层响应于容器内的压力而侵入。

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