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: Disclosed embodiments include methods of assembling a vented nuclear fission fuel module. Given by way of non-limiting example and not of limitation, an illustrative method of assembling a vented nuclear fission fuel module includes receiving a nuclear fission fuel element capable of generating a gaseous fission product. A valve body is coupled to the nuclear fission fuel element, and the valve body defines a plenum therein for receiving the gaseous fission product. A valve is disposed in communication with the plenum for controllably venting the gaseous fission product from the plenum. A flexible diaphragm is coupled to the valve for moving the valve. A cap is mounted on the valve, and a manipulator extendable to the cap for manipulating the cap is received.

Abstract: Illustrative embodiments provide a nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system.

Abstract: Illustrative embodiments provide a nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system.

Abstract: Illustrative embodiments provide a nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system.

Abstract: Illustrative embodiments provide a nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system.

Abstract: Illustrative embodiments provide a nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system.

Abstract: Illustrative embodiments provide a nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system.

Abstract: Illustrative embodiments provide a nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system.

Abstract: Illustrative embodiments provide a nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system.

Abstract: A nuclear fission reactor fuel assembly and system configured for controlled removal of a volatile fission product and heat released by a burn wave in a traveling wave nuclear fission reactor and method for same. The fuel assembly comprises an enclosure adapted to enclose a porous nuclear fuel body having the volatile fission product therein. A fluid control subassembly is coupled to the enclosure and adapted to control removal of at least a portion of the volatile fission product from the porous nuclear fuel body. In addition, the fluid control subassembly is capable of circulating a heat removal fluid through the porous nuclear fuel body in order to remove heat generated by the nuclear fuel body.

Abstract: The present invention relates to a fuel assembly for a light-water reactor with a substantially square cross section wherein the fuel assembly comprises a plurality of fuel rods (4). The fuel rods (4) extend between a bottom tie plate (5) and a top tie plate (6) and a coolant is adapted to flow upwards through the fuel assembly. At least one of the top tie plates (6) or the bottom tie plates (5) comprises flow openings (22, 22a, 22b) for the passage of the coolant and side supports (17) for supporting the fuel rods (4) in the lateral direction. The side supports (17) are designed in one and the same sheet-metal piece as the flow openings (22, 22a, 22b) and the side supports (17) are folded substantially 90° in relation to the other structure of the top tie plate (6) or the bottom tie plate (5).

Abstract: In order to avoid uncontrolled secondary damage to a fuel rod, in particular a fuel rod being formed of Zircaloy and having a liner on the inside, in which the secondary damage may be generated by coolant that enters the fuel rod in the event of primary damage, a nucleus is deliberately provided in a cladding tube. The nucleus, although passivated in an undamaged fuel rod and not impeding the serviceability of the fuel rod, is activated by coolant which enters the fuel rod in the event of primary damage or by hydrogen or other reaction products produced in reactions of the coolant in the interior of the fuel rod and results in a small-area perforation. This prevents an aggressive atmosphere, which may result in unintentional large-area secondary damage at other points, from accumulating in the cladding tube after primary damage.

Abstract: A diving bell type control rod of sodium bond type. The control rod including a plurality of control elements each comprising a pellet chamber for packing B.sub.4 C pellets and disposed in a cladding tube, an intermediate plug disposed above the pellet chamber, an upper chamber formed above the intermediate plug, a vent tube allowing the pellet chamber to communicate with the upper chamber while penetrating through the intermediate plug, upper and lower vent holes formed in upper and lower two stages in the cladding tube at the upper chamber, a sodium inflow port opening to the upper surface of the intermediate plug, and a sodium introduction tube extending from the sodium inflow port to a position below the lower end surface of the intermediate plug while penetrating through the intermediate plug.

Abstract: In a fuel bundle for a boiling water nuclear reactor comprising a plurality of fuel rods (20) secured within an array and extending between upper and lower tie plates (24, 22), and including at least one additional partial length fuel rod (20') extending from said lower tie plate (22) but terminating short of said upper tie plate (24), an improvement in the form of a removable extension rod (32) secured to said at least one additional fuel rod (20') and extending substantially to said upper tie plate (24). The removable extension rod (32) also permits variance in the reactivity of the partial length fuel rod (20') particularly in the two phase region of the bundle (10).

Abstract: A microporous plug is provided which serves to seal a vessel so as to prevent the bulk flow of gases through an outlet. The pores of said microporous plug are sized so as to permit the transport of gases to and from the vessel interior by Knudsen diffusion. In preferred embodiments, the pores of the plug are sized so as to release helium from the interior of a vessel and restrict the transport of carbon dioxide into the vessel from the surrounding atmosphere by Knudsen diffusion. Such embodiments are particularly useful on Mars where the helium is transported into an environment of higher pressure. In other embodiments, the microporous plug is used in conjunction with an absorber positioned within the vessel to react with atmospheric gases that pass through the plug, such as carbon dioxide. Also provided are radioisotope thermoelectric generators that incorporate a microporous plug and optionally an absorber.

Abstract: Disclosed is a method of installing a reversibly porous, air-diffusible, water-restrictive, polymer plug in a port that extends through the wall of a nuclear waste storage container. The plug is inserted a predetermined distance, for example, with the aid of a screwdriver applied to a slot in the plug's outer face. When inserted, the plug prevents the loss of nuclear waste through the port while the air-diffusible nature of the material allows gases to pass through the material. The resultant venting action of the plug prevents the creation of pressure differences between the interior of the container and the environment. Thus, the likelihood of the container becoming overpressurized and leaking is minimized. In addition, the water-restrictive nature of the plug material restricts the ingress and egress of water from the container, reducing the likelihood of groundwater contamination during storage.

Abstract: A method and apparatus for extending the life of a core of a water moderated nuclear reactor by spectral shift comprising the displacement of a portion of the moderator in the core by a gas having a low neutron cross-section during the initial stage of the life of the core and displacing the gas and replacing it with moderator during the latter part of the life of the core.

Abstract: A segmented fuel and moderator rod and fuel assembly for a BWR. The segmented rod has a lower fuel region and an upper moderator region for passing coolant having a void fraction of between about 0-20% through the upper portion of the BWR core which is normally undermoderated. The segmented rod displaces one or more conventional fuel rods in the fuel bundle. A method of moderating a BWR core is also disclosed.

Abstract: A fuel assembly, particularly advantageous for use with a BWR, wherein the fuel bundle is adapted to be inserted into an envelope formed from a flow channel and a lower nozzle assembly. The fuel bundle is essentially axially symmetrical having identical top and bottom tie plates. Within the fuel bundle, alternate fission gas plenums are disposed at the top and bottom of the bundle respectively.During the refueling operation, the fuel bundle is removed from the reactor core, axially inverted and reinserted into the core for continued burn up. The invention takes advantage of the reactivity increase possible in a BWR when a partially burned fuel bundle is inverted.

Abstract: A nuclear fuel assembly, particularly advantageous for use in a pressurized water reactor, wherein each alternate fuel rod in the assembly is positioned with its fission gas plenum zone at the top of the assembly and the intervening alternate fuel rods are positioned with their fission gas plenum zones at the bottom of the assembly. All of the fuel rods are preferably axially coextensive. An axial blanket region may be formed by providing the fuel zone of each fuel rod with a small zone of natural or depleted uranium at a part of the fuel zone furthest from the fission gas plenum zone. A method of effectively lengthening the active length of a nuclear fuel assembly is also described.

Abstract: A tubular sheath for particulate nuclear fuel has microporous retaining elements formed by winding metal strip about a central pin and pushing the resulting spiral into the sheath ends. The metal strip has transverse grooves formed by a photo-etching process which form axial gas passages narrow enough to prevent passage of fuel particles. Suitable materials for the strip include molybdenum and tungsten. A stainless steel strip can be used if a molybdenum or tungsten disc is placed between it and the fuel.

Abstract: A nuclear fuel element comprises plutonium-containing fuel pellets filled in a cladding with both end sealed with end plugs. One end plug has a filter at the inside and a passage communicating with the space in the cladding through the filter. The passage is sealed at the surface part of the end plug by welding. The filter and the passage in the end plug are utilized for withdrawing a gas in the cladding filled with the fuel pellets in a process for fabricating the nuclear fuel element. The filter traps nuclear fissionable materials in the cladding to prevent its leakage to the outside. After the withdrawal of the gas, a helium gas is filled in the cladding through the passage in the end plug. After completion of these operations, the passage in the end plug is sealed as mentioned above.

Abstract: In the event of a breach in the cladding of a rod in an operating liquid metal fast breeder reactor, the rapid release of high-pressure gas from the fission gas plenum may result in a gas blanketing of the breached rod and rods adjacent thereto which impairs the heat transfer to the liquid metal coolant. In order to control the release rate of fission gas in the event of a breached rod, the substantial portion of the conventional fission gas plenum is formed as a gas bottle means which includes a gas pervious means in a small portion thereof. During normal reactor operation, as the fission gas pressure gradually increases, the gas pressure interiorly of and exteriorly of the gas bottle means equalizes.

Abstract: An improved end plug is provided for a nuclear fuel rod assembly. The end plug is of an integral construction having an upper shoulder portion which abuts the top edge of a fuel tube and a circular body portion adapted to be inserted into the end of the fuel tube in a force fitting relationship. A flat is provided on the lower body portion so as to define a gap between the lower body portion and the inner wall of the fuel tube upon partial insertion of the plug into the tube, the gap providing an orifice for introducing an inert-gas under pressure into the tube. Upon total insertion of the lower body portion of the plug into the tube, the gap is eliminated and metal-to-metal contact is made between the lower body portion of the plug and the end of the fuel tube for sealing the pressurized gas and a nuclear fuel within the fuel tube.

Abstract: This invention teaches an encapsulated fuel unit for a nuclear reactor, such as for an enriched uranium fuel plate of thin cross section of the order of 1/64 or 1/8 of an inch and otherwise of rectangular shape 1-2 inches wide and 2-4 inches long. The case is formed from (a) two similar channel-shaped half sections extended lengthwise of the elongated plate and having side edges butted and welded together to define an open ended tube-like structure and from (b) porous end caps welded across the open ends of the tube-like structure. The half sections are preferably of stainless steel between 0.002 and 0.01 of an inch thick, and are beam welded together over and within machined and hardened tool steel chill blocks. The porous end caps preferably are of T-316-L stainless steel having pores of approximately 3-10 microns size.

Abstract: Tungsten is placed in contact with either molybdenum, tantalum, niobium, vanadium, rhenium, or other metal of atoms having a different diffusion coefficient than tungsten. The metals are heated so that the atoms having the higher diffusion coefficient migrate to the metal having the lower diffusion rate, leaving voids in the higher diffusion coefficient metal. Heating is continued until the voids are interconnected.

Abstract: In a nuclear fuel reactor core, fuel elements are arranged in a closely packed hexagonal configuration, each fuel element having diametrically opposed vents permitting 180.degree. rotation of the fuel elements to counteract bowing. A grid plate engages the fuel elements and forms passages for communicating sets of three, four or six individual vents with respective monitor lines in order to communicate vented radioactive gases from the fuel elements to suitable monitor means in a manner readily permitting detection of leakage in individual fuel elements.