摘要:
The invention relates in particular to a solid metallic component. This component (1) is particularly notable in that it comprises a core (5) and an external shell (3) which surrounds said core (5) in all directions, this core (5) and this shell (3) being made of different grades of steel, the steel of said core (5) having martensite and bainite critical cooling rates lower than those of the steel or steels of said shell (3).
摘要:
A nuclear island includes a nuclear reactor, a lateral seismic restraint, and a reactor core retention cooling system. The lateral seismic restraint includes a vertically oriented pin attached to one of the bottom of the lower vessel head and the floor underneath the nuclear reactor, and a mating pin socket is attached to the other of the bottom of the lower vessel head and the floor. The reactor core retention cooling system includes one or more baffles, optionally thermally insulating material, disposed alongside the exterior surface of a lower portion of the reactor pressure vessel including at least the lower vessel head. A plenum is defined between the one or more baffles and the exterior surface of a lower portion of the reactor pressure vessel. The one or more baffles may define a lower plenum inlet surrounding the lateral seismic restraint.
摘要:
Provided is a method for manufacturing a cylindrical member which includes end bending of respective end portions of a plate material in a longitudinal direction, primary grooving of respective end surfaces of the plate material subjected to end bending, bending of the plate material to a ring shape, secondary grooving of respective end surfaces of the plate material subjected to bending in a ring shape, and joining of respective end surfaces of the plate material. Therefore, it is possible to manufacture a high-quality cylindrical member.
摘要:
A suspended basket includes a plurality of plates, tie rods, and adjustable length threaded tie rod couplings connecting threaded ends of the tie rods with threaded features of the plates. Control rod drive mechanisms (CRDMs) with CRDM motors are mounted in the suspended basket, which is suspended in a pressure vessel above a nuclear reactor core to control insertion of control rods into the reactor core. In one embodiment each adjustable length threaded tie rod coupling is a turnbuckle coupling that includes a sleeve threaded onto the threaded end of the tie rod and onto the threaded feature of the plate, and the sleeve is rotatable to adjust the position of the tie rod respective to the plate. Guide frames may be mounted in the suspended basket between the CRDMs and the nuclear reactor core to guide portions of the control rods withdrawn from the nuclear reactor core.
摘要:
This disclosure describes various configurations and components of a molten fuel fast or thermal nuclear reactor in which one or more primary heat exchangers are located above the reactor core of the nuclear reactor.
摘要:
A nuclear reactor is supported by a primary support anchored to a civil structure and defining a reactor support plane located below the center of gravity of the nuclear reactor. A lateral seismic support engages the nuclear reactor below the reactor support plane to prevent lateral motion of the nuclear reactor. In one approach a flange, protrusion, or ledge of the reactor pressure vessel rests on a support engagement surface, a seismic rotational restraint assembly prevents the nuclear reactor from rotating during a seismic event, and a liftoff prevention assembly prevents vertical liftoff of the flange, protrusion, or ledge of the reactor pressure vessel from the support engagement surface. The lateral seismic support may comprise a pin connected with the bottom of the reactor pressure vessel engaging a pin socket connected with or formed in a floor of the civil structure of the radiological containment containing the nuclear reactor.
摘要:
An inspection system for inspecting a core shroud includes a remotely operated vehicle with a profile, scanning ability, and reliability that contribute to expanded inspection coverage and reduced inspection times.
摘要:
In order to provide an austenitic single crystal stainless steel having preferable stress corrosion cracking resistance, strength, and irradiation induced embrittlement resistance so as to extend the life of a nuclear reactor core structure, which is used under a high radiation dose environment, a method is employed, which comprises the steps of homogeneously dispersing carbides into a parent phase of the austenitic single crystal stainless steel by a two step solution heat treatment, and subsequently effecting an ageing heat treatment after rapid cooling for precipitating fine carbides. Austenitic single crystal stainless steel having preferable stress corrosion cracking resistance, strength, and irradiation induced embrittlement resistance can be provided, and the life of nuclear reactor core structure, which is used under a high radiation dose environment, can be extended.
摘要:
An apparatus for repairing a shroud in which one or more seam welds are cracked. The repair involves the attachment of a splice bracket to the shroud so that the bracket bridges the cracked weld seam and is applicable to both vertical and horizontal weld seams. The bracket is intended to structurally replace the shroud seam weld which is cracked. Multiple splice brackets can be placed along the length of a crack. Each splice bracket is attached to the shroud by a plurality of tapered fastener assemblies. Each tapered fastener assembly includes a first fastener element having a threaded surface and a conical surface coaxial with the threaded surface; a slotted sleeve having an internal surface which matches the conical surface of the first fastener element and an external surface which matches a circular cylindrical surface, and a flange which extends radially outward beyond the external surface; and a second fastener element having a threaded surface threadably engaged with the threaded surface of the first fastener element. The sleeve fits inside aligned holes in the splice bracket and shroud.
摘要:
An apparatus for repairing a shroud in which one or more seam welds are cracked. The repair involves the attachment of a splice bracket to the shroud so that the bracket bridges the cracked weld seam and is applicable to both vertical and horizontal weld seams. The bracket is intended to structurally replace the shroud seam weld which is cracked. Multiple splice brackets can be placed along the length of a crack. Each splice bracket is attached to the shroud by a plurality of tapered fastener assemblies. Each tapered fastener assembly includes a first fastener element having a threaded surface and a conical surface coaxial with the threaded surface; a slotted sleeve having an internal surface which matches the conical surface of the first fastener element and an external surface which matches a circular cylindrical surface, and a flange which extends radially outward beyond the external surface; and a second fastener element having a threaded surface threadably engaged with the threaded surface of the first fastener element. The sleeve fits inside aligned holes in the splice bracket and shroud.