The Babcock & Wilcox Company

Donald C Schluderberg

Felix S Jabsen

Arnold E Paulson

Bertrand N McDonald

Gerald T Edwards

Steam generation and reheat apparatus and method. After flowing in series through a superheater and an evaporator, a heat supply fluid is flowed through both an economizer and a reheater in parallel flow to improve the Rankine Cycle thermal efficiency in plants such as nuclear power plants where the heat supply fluid temperatures are limited.

Steam generation and reheat apparatus

An heat exchanger including a shell for flow of a first fluid and a plurality of tubes for flow of a second fluid in heat exchange relation therewith. A tubular member is concentric with at least a portion of a tube to define a space between the tube and tubular member. The tubular member includes at least one radially outwardly longitudinally extending projection portion for effecting flexing of the tubular member radially outwardly so that a minimum clearance between the tube and tubular member may be provided, and so that the tube may be inserted in and removed from the tubular member to provide greater accessibility for welding tubular members to tube sheets during assembly. Oxygen may be introduced into the space between the tubular member and tube to combine with tritium which may diffuse through the tubular member wall to prevent diffusion of the tritium through the tube wall.

Heat exchanger having tubular members concentric with fluid carrying

Apparatus for superheating steam. In accordance with one aspect of the invention, the apparatus is provided with two banks of inclined tubes extending upwardly from an outlet header to respective inlet headers. The banks of tubes are disposed in the flow path of main steam through the apparatus and provide a flow of vapor for adding superheat to the main steam. In accordance with another aspect of the invention, the tubes extend upwardly to closed ends whereby a lower header acts as both a vapor inlet and condensate outlet. In accordance with another aspect of the invention, the vapor is provided by a fossil fuel-fired vapor generator to superheat main steam which has been provided by a nuclear steam generator.

Apparatus for superheating steam

An integral nuclear fuel element assembly utilizes longitudinally finned fuel pins. The continuous or interrupted fins of the fuel pins are brazed to fins of juxtaposed fuel pins or directly to the juxtaposed fuel pins or both. The integrally brazed fuel assembly is designed to satisfy the thermal and hydraulic requirements of a fuel assembly lattice having moderator to fuel atom ratios required to achieve high conversion and breeding ratios.

Integral nuclear fuel element assembly

An energy storage and recovery system designed for storing excess over demand energy generated by a steam cycle electrical generating plant during slack electricity demand periods and for recovering the stored energy to provide supplemental electricity during peak demand periods. The system utilizes one or more moving bed heat exchangers for transferring heat between the steam cycle of the power plant and a moving bed of refractory particles. Pipes and valves establish fluid communication between the heat exchangers and the steam cycle to supply fluid to selectively heat the moving bed of refractory particles or to cool them as the case may be. One or more insulated silos are provided for storing the refractory particles and means are provided for transporting the particles between the silos and the heat exchangers.

Moving bed heat storage and recovery system

A technique is provided for engaging and disengaging burnable poison rods from the spider in a fuel assembly. The cap on the end of each of the burnable poison rods is provided with a shank that is received in the respective bore formed in the spider. A frangible flange secures the shank and rod to the spider. Pressing the shank in the direction of the bore axis ruptures the frangible flange to release the rod from the spider.

Method of assembling and disassembling a control component structure

A nuclear fuel assembly of the type having a plurality of nuclear fuel elements disposed in parallel, and forming a plurality of longitudinal flow channels, in a closely packed array is disclosed. Axially spaced longitudinal fins formed integrally on at least some of the fuel elements, at an angle with the fuel element axis, serve to divert coolant flowing longitudinally past the fuel elements between adjacent flow channels to promote mixing and even heating of the coolant. Each fin traverses the clearance between adjacent fuel elements, tangentially contacts the body of an adjacent fuel element, and is fixedly connected thereto. Sets of the axially spaced fins are fixedly connected to adjacent fuel elements, as described, in substantially the same transverse plane relative to the longitudinal axis of the fuel assembly. At the leading end of the fins, the relative flow rate diverted from adjacent flow channels alternates; and at the trailing end of the fins, the relative flow rate conveyed to adjacent flow channels also alternates; moreover, in a given flow channel the number of flow streams diverted and converged, at the leading and trailing fin edges, also alternates.

Fuel element assembly

Industrial technique

This invention relates to a group of modular heat exchangers of the type having a steam chamber, a feedwater chamber, and a feedwater tube passing through the steam chamber to establish fluid communication with the feed chamber.

Modular heat exchangers for consolidated nuclear steam generator

A method of operating a vapor generating system, including a once-through vapor generator, wherein wet vapor is generated in the upper portion of the load range and superheated vapor is generated in the lower portion of the load range is disclosed. Generated vapor is passed through an external and remote moisture separator. Superheated vapor is desuperheated by liquid injection as it passes from the vapor generator to the moisture separator.

Vapor generating technique

This invention relates to an improved system of providing power having a unique generating means of the nuclear reactor variety adapted with a plurality of steam generators in the form of replaceable modular units of the expendable type for the attainment of the optimum in effective and efficient vaporization of fluid during the process of generating power.

Vessel penetration apparatus

Consolidated nuclear steam generator

A typical embodiment of an integral pressurized water nuclear reactor and straight-tube steam generator combination in accordance with the invention includes a generally cylindrical pressure vessel that is assembled from three segments which are bolted together at transverse joints to form a fluid and pressure tight unit that encloses the steam generator and the reactor. This novel construction permits primary to secondary coolant heat exchange and improved control rod drive mechanisms which can be exposed for full service access during reactor core refueling, maintenance and inspection.

Growing community of inventors

Lynchburg, VA, United States of America

Donald C Schluderberg