Pipe connector

Pipe joints or couplings – With casing – lining or protector – Insulated

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Details

176 65, 176 87, 285268, 176 40, G21C 900

Patent

active

040873234

ABSTRACT:
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.

REFERENCES:
patent: 1469528 (1923-10-01), Owens
patent: 2242604 (1941-05-01), Wells
patent: 2774618 (1956-12-01), Alderson
patent: 3793143 (1974-02-01), Muller
patent: 3807772 (1974-04-01), Delisle et al.
patent: 3823065 (1974-09-01), Jones
patent: 3977940 (1976-08-01), Frisch et al.
Fast Reactor Technology: Plant Design, M.I.T. Press, (1966), Yevick et al. pp. 187-188.

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