发明名称 Pipe connector
摘要 A safety test facility for testing sodium-cooled nuclear reactor components includes a reactor vessel and a heat exchanger submerged in sodium in the tank. The reactor vessel and heat exchanger are connected by an expansion/deflection pipe coupling comprising a pair of coaxially and slidably engaged tubular elements having radially enlarged opposed end portions of which at least a part is of spherical contour adapted to engage conical sockets in the ends of pipes leading out of the reactor vessel and in to the heat exchanger. A spring surrounding the pipe coupling urges the end portions apart and into engagement with the spherical sockets. Since the pipe coupling is submerged in liquid a limited amount of leakage of sodium from the pipe can be tolerated.
申请公布号 US4087323(A) 申请公布日期 1978.05.02
申请号 US19760749206 申请日期 1976.12.09
申请人 THE UNITED STATES OF AMERICA AS REPRESENTED BY THE UNITED STATES DEPARTMENT OF ENERGY 发明人 SULLIVAN, THOMAS E.;PARDINI, JOHN A.
分类号 F16L11/18;F16L27/04;F16L27/12;G21C1/02;(IPC1-7):G21C9/00 主分类号 F16L11/18
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