Abstract:
Use in a nuclear fission reactor of a sacrificial metal in a molten salt fuel containing actinide halides in order to maintain a predefined ratio of actinide trihalide to actinide tetrahalide without reducing actinide trihalide to actinide metal. A method of maintaining oxidation state of a molten salt containing actinide halides. The method comprises contacting the molten salt continuously with a sacrificial metal, the sacrificial metal being selected in order to maintain a predefined ratio of actinide trihalide to actinide tetrahalide without reducing actinide trihalide to actinide metal. A fuel tube containing a sacrificial metal is also described.
Abstract:
Disclosed embodiments include a vented nuclear fission fuel module system. Given by way of non-limiting example and not of limitation, an illustrative vented nuclear fission fuel module system includes a nuclear fission fuel element capable of generating a gaseous fission product. A valve body is associated with the nuclear fission fuel element, and the valve body defines a plenum therein for receiving the gaseous fission product. A reclosable valve is in operative communication with the plenum for controllably venting the gaseous fission product from the plenum, and the valve body includes a flexible diaphragm coupled to the valve for moving the valve to a closed position.
Abstract:
A vent structure for reliable long term operation at high temperatures is fabricated by annealing a tubing of predetermined length and size, filling the tubing with fine alumina particles, flattening and coiling and pressing an upper portion of the tubing at predetermined pressures, annealing the formed tubing, and installing a particulate filter in the undeformed lower portion of the tubing. For use in venting helium generating reactor control pins located under hot molten sodium, a vent assembly including the vent structure and providing an air lock between the outer molten sodium and the vent is affixed to the upper end of each control pin.
Abstract:
A fuel element for a gas-cooled nuclear reactor having a housing surrounding a plurality of fuel pins through which coolant flows over the fuel pins. The housing has a portion of varying cross section and a plug disposed within the housing adjacent the portion. The plug and housing form a generally annular orifice through which the gas coolant flows, the size of which orifice is variable in accordance with the axial position of the plug, which can be varied from exterior of the reactor pressure vessel.
Abstract:
Tracer gases are contained in a capsule which is closed-off by a fusible seal and placed within the interior of each fuel-pin can. The capsule is formed of material having a melting point above the operating temperature of the fuel pins within a nuclear reactor. The fusible seal is formed of material having a melting point below said temperature, with the result that the tracer gases are released into the interior of each fuel pin at that temperature.
Abstract:
A vent structure for reliable long term operation at high temperatures is fabricated by annealing a tubing of predetermined length and size, placing a predetermined number of strands of stabilized zirconium oxide yarn of predetermined diameter longitudinally into one end of the tubing a predetermined distance therein, flattening and coiling and pressing the end portion of the tubing containing the yarn at predetermined pressures, annealing the formed tubing, and installing a particulate filter in the undeformed (normally lower) portion of the tubing. For use in venting helium generating reactor control pins located under hot molten sodium, a vent assembly including the vent structure and providing an air lock between the outer molten sodium and the vent is affixed to the upper end of each control pin.
Abstract:
A VENTING SYSTEN IS DESCRIBED FOR A GLASS COOLED NUCLEAR REACTOR HAVING A PLURLAITY OF CONTAINERS FOR FISSIONABLE MATERIAL. A VENT PASSAGE SYSTEM IS PROVIDED FOR CONDUCTING FISSION PRODUCTS FROM THE CONTAINERS TO A FISSION PRODUCT RECEIVING SYSTEM. THE RECEIVING SYSTEM AND THE VENT PASSAGE SYSTEM ARE AT A LOWER PRESSURE THAN THE AMBIENT PRESSURE OF THE COOLANT GAS. AT LEAST ONE BLEED PASSAGE IS PROVIDED ADJACENT THE CONTAINERS COMMUNICATING FROM THE COOLING SYSTEM OF THE REACTOR TO THE VENT PASSAGE SYSTEM FOR BLEEDING COOLANT GAS INTO THE VENT PASSAGE SYSTEM, THEREBY SPEEDING THE TRANSPORTATION OF FISSION PRODUCTS TO THE RECEIVING SYSTEM, AND SO REDUCING THE DEPOSITION OF SOLIDS DECAYING THEREFROM IN THE CONNECTING DUCTING,
ALSO DESCRIBED IS A FUEL ELEMENT FOR USE IN SUCH A REACTOR, SUCH FUEL ELEMENTS HAVING A SELF-CONTAINING VARIABLE POSITION PLUG AND ORIFICE ARRANGEMENT FOR VARYING THE FLOW OF COOLANT THROUGH THE FUEL ELEMENT.