16 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "22 General Studies Of Nuclear Reactors"  
Results: 1 - 16
open access

Method for producing nuclear fuel

Description: Nuclear fuel is made by contacting an aqueous solution containing an actinide salt with an aqueous solution containing ammonium hydroxide, ammonium oxalate, or oxalic acid in an amount that will react with a fraction of the actinide salt to form a precipitate consisting of the hydroxide or oxalate of the actinide. A slurry consisting of the precipitate and solution containing the unreacted actinide salt is formed into drops which are gelled, calcined, and pressed to form pellets.
Date: April 24, 1981
Creator: Haas, P.A.
Partner: UNT Libraries Government Documents Department
open access

Passive decay heat removal system for water-cooled nuclear reactors

Description: This document describes passive decay-heat removal system for a water-cooled nuclear reactor which employs a closed heat transfer loop having heat-exchanging coils inside an open-topped, insulated evaporator located inside the reactor vessel, below its normal water level, in communication with a condenser located outside of containment and exposed to the atmosphere. The heat transfer loop is located such that the evaporator is in a position where, when the water level drops in the reactor, it w… more
Date: January 1, 1990
Creator: Forseberg, C.W.
Partner: UNT Libraries Government Documents Department
open access

Self-actuating reactor-shutdown system. [LMFBR]

Description: A control system for the automatic or self-actuated shutdown or scram of a nuclear reactor is described. The system is capable of initiating scram insertion by a signal from the plant protection system or by independent action directly sensing reactor conditions of low-flow or over-power. Self-actuation due to a loss of reactor coolant flow results from a decrease of pressure differential between the upper and lower ends of an absorber element. When the force due to this differential falls belo… more
Date: June 4, 1981
Creator: Barrus, D.M.; Brummond, W.A. & Peterson, L.F.
Partner: UNT Libraries Government Documents Department
open access

Nuclear reactor control apparatus. [FBR]

Description: Nuclear reactor safety rod release apparatus comprises a ring which carries detents normally positioned in an annular recess in outer side of the rod, the ring being held against the lower end of a drive shaft by magnetic force exerted by a solenoid carried by the drive shaft. When the solenoid is de-energized, the detent-carrying ring drops until the detents contact a cam surface associated with the lower end of the drive shaft, at which point the detents are cammed out of the recess in the sa… more
Date: April 16, 1981
Creator: Sridhar, B.N.
Partner: UNT Libraries Government Documents Department
open access

Nuclear reactor control apparatus

Description: Nuclear reactor core safety rod release apparatus comprises a control rod having a detent notch in the form of an annular peripheral recess at its upper end, a control rod support tube for raising and lowering the control rod under normal conditions, latches pivotally mounted on the control support tube with free ends thereof normally disposed in the recess in the control rod, and cam means for pivoting the latches out of the recess in the control rod when a scram condition occurs. One embodime… more
Date: August 28, 1981
Creator: Sridhar, B.N.
Partner: UNT Libraries Government Documents Department
open access

Shutdown system for a nuclear reactor

Description: An ultimate shutdown system is provided for termination of neutronic activity in a nuclear reactor. The shutdown system includes bead chains comprising spherical containers suspended on a flexible cable. The containers are comprised of mating hemispherical shells which provide a ruggedized enclosure for reactor poison material. The bead chains, normally suspended above the reactor core on storage spools, are released for downward travel upon command from an external reactor monitor. The chains … more
Date: January 20, 1982
Creator: Groh, E.F.; Olson, A.P.; Wade, D.C. & Robinson, B.W.
Partner: UNT Libraries Government Documents Department
open access

Fuel-rod-retention device for a nuclear reactor. [Patent application]

Description: A device is described for supporting a nuclear fuel rod in a fuel rod assembly which allows the rod to be removed without disturbing other rods in the assembly. A fuel rod cap connects the rod to a bolt which is supported in the assembly end fitting by means of a locking assembly. The device is designed so that the bolt is held securely during normal reactor operation yet may be easily disengaged and the fuel rod removed when desired.
Date: January 29, 1982
Creator: Hylton, C.L.
Partner: UNT Libraries Government Documents Department
open access

Robot arm apparatus

Description: A robot arm apparatus is provided for inspecting and/or maintaining an interior of a steam generator which has an outside wall and a port for accessing the interior of the steam generator. The robot arm apparatus includes a flexible movable conduit for conveying inspection and/or maintenance apparatus from outside the steam generator to the interior of the steam generator. The flexible conduit has a terminal working end which is translated into and around the interior of the steam generator. Th… more
Date: December 31, 1990
Creator: Nachbar, H. D.
Partner: UNT Libraries Government Documents Department
open access

Inflatable containment diaphragm for sealing and removing stacks

Description: A diaphragm with an inflatable torus-shaped perimeter is used to seal at least one end of a stack so that debris that might be hazardous will not be released during removal of the stack. A diaphragm is inserted and inflated in the lower portion of a stack just above where the stack is to be cut such that the perimeter of the diaphragm expands and forms a seal against the interior surface of the stack.
Date: December 31, 1991
Creator: Meskanick, G. R. & Rosso, D. T.
Partner: UNT Libraries Government Documents Department
open access

Passive decay heat removal system for water-cooled nuclear reactors

Description: This document describes passive decay-heat removal system for a water-cooled nuclear reactor which employs a closed heat transfer loop having heat-exchanging coils inside an open-topped, insulated evaporator located inside the reactor vessel, below its normal water level, in communication with a condenser located outside of containment and exposed to the atmosphere. The heat transfer loop is located such that the evaporator is in a position where, when the water level drops in the reactor, it w… more
Date: December 31, 1990
Creator: Forseberg, C. W.
Partner: UNT Libraries Government Documents Department
open access

Heater element design for electrically powered heater assemblies

Description: This invention is comprised of an apparatus for electrically simulating a nuclear reactor fuel assembly. It includes a heater assembly having a top end and a bottom end and a plurality of concentric heater tubes having electrical circuitry connected to a power source, and radially spaced from each other. An outer target tube and an inner target tube is concentric with the heater tubes and with each other, and the outer target tube surrounds and is radially spaced from the heater tubes. The inne… more
Date: December 31, 1992
Creator: Berta, V. T.
Partner: UNT Libraries Government Documents Department
open access

Duplex sampling apparatus and method

Description: An improved apparatus is provided for sampling a gaseous mixture and for measuring mixture components. The apparatus includes two sampling containers connected in series serving as a independently determine the amounts of condensable and noncondensable gases in admixture from a single sample. More specifically, a first container includes a first port capable of selectively connecting to and disconnecting from a sample source and a second port capable of selectively connecting to and disconnecti… more
Date: January 30, 1991
Creator: Brown, P. E. & Lloyd, R.
Partner: UNT Libraries Government Documents Department
open access

High flexibility, noncollapsing light weight hose

Description: This invention relates generally to a high-flexibility, light weight, noncollapsing hose and more particularly to such a hose having a large size and particularly useful as equipment draining a radioactively contaminated fluid through a noncontaiminated, isolated and restricted space with high confidence against kinking, collapse, or leaking even with large relative motion between the inlet and outlet ends of the hose. In the operation of nuclear facilities, such as nuclear reactors, processing… more
Date: February 1, 1991
Creator: Williams, D. A.
Partner: UNT Libraries Government Documents Department
open access

A unique method of neutron flux determination from experimental data

Description: A method is provided for determining the fission heat flux of a prime specimen inserted into a specimen of a test reactor. A pair of thermocouple test specimens are positioned at the same level in the holder and a determination is made of various experimental data including the temperature of the thermocouple test specimens, the temperature of bulk water channels located in the test holder, the gamma scan count ratios for the thermocouple test specimens and the prime specimen, and the thickness… more
Date: December 1, 1998
Creator: Paxton, Frank A.
Partner: UNT Libraries Government Documents Department
open access

Multilayered nuclear fuel element

Description: A nuclear fuel element is described which is suitable for high temperature applications comprised of a kernel of fissile material overlaid with concentric layers of impervious graphite, vitreous carbon, pyrolytic carbon and metal carbide. The kernel of fissile material is surrounded by a layer of impervious graphite. The layer of impervious graphite is then surrounded by a layer of vitreous carbon. Finally, an outer shell which includes alternating layers of pyrolytic carbon and metal carbide s… more
Date: December 1, 1996
Creator: Schweitzer, Donald G. & Sastre, Cesar
Partner: UNT Libraries Government Documents Department
open access

Thermionic switched self-actuating reactor shutdown system

Description: A self-actuating reactor shutdown system is described which has a thermionic switched electromagnetic latch arrangement which is responsive to reactor neutron flux changes and to reactor coolant temperature changes. The system is self-actuating in that the sensing thermionic device acts directly to release (scram) the control rod (absorber) without reference or signal from the main reactor plant protective and control systems. To be responsive to both temperature and neutron flux effects, two d… more
Date: June 4, 1981
Creator: Barrus, Donald M.; Shires, Charles D. & Brummond, William A.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen