Abstract: A breeder blanket for generating tritium using neutrons produced by nuclear fusion of deuterium and/or tritium within a plasma confined within a fusion reactor. The breeder blanket comprises: a plasma-facing first wall; a breeder layer comprising lithium containing material for generating tritium from the neutrons; and neutron moderator material comprising metal hydride and/or deuteride arranged between the first wall and the lithium-containing material.

Abstract: A method including depositing a first material on a first member by an additive manufacturing process in a pattern intended to aid in an assembly of the first member and at least a second member and inserting the first member at least partially into the second member, with the first material being guide for insertion.

Abstract: The invention relates to the field of thermonuclear fusion and can be used in devices for electrically connecting components situated inside a nuclear fusion reactor chamber to the vacuum vessel of the reactor. A device for electrically connecting components situated inside a nuclear fusion reactor chamber to the vacuum vessel of the reactor comprises two identical stacks of electrically conductive plates. The electrically conductive plates are in the shape of a symmetrical wave having at least one full period. The plates in a stack are nested one inside another and are connected to flanges for attachment to a component situated inside the chamber and to the vacuum vessel. The stacks of electrically conductive plates are mounted with mirror symmetry about a line that passes through the centers of symmetry of the flanges.

Abstract: Examples of a pressure wave generator configured to generate high energy pressure waves in a medium are disclosed. The pressure wave generator can include a sabot carrying a piston. The sabot can further comprise a locking means to lock the piston in a fixed position when the locking means are activated. When the locking means are in a deactivated position, the piston can be released and can move at least partially away from the sabot. The sabot carrying the piston can be disposed within an inner bore of a housing of the pressure wave generator and can move within the inner bore of the housing from its first end toward its second end along a longitudinal axis of the bore. A transducer can be accommodated in the second end of the housing. The transducer can be coupled to the medium and can convert a portion of the kinetic energy of the piston into a pressure wave in the medium upon impact of the piston with the transducer.

Abstract: Provided is a ferritic lightweight high-strength steel sheet having excellent stiffness and ductility and a method of manufacturing the same. The steel sheet including 0.02 wt % to 0.1 wt % of carbon (C), 4 wt % to 15 wt % of manganese (Mn), 4 wt % to 10 wt % of aluminum (Al), 2.0 wt % or less (excluding 0) of silicon (Si), 0.01 wt % to 0.3 wt % of titanium (Ti), 0.005 wt % to 0.2 wt % of antimony (Sb), and iron (Fe) as well as unavoidable impurities as a remainder, and having a value of 0.25×Ti/C ranging from 0.17 to 1.0 and a value of Mn/Al×Log(C×Ti×10000) ranging from 1.0 to 10.

Abstract: A method of monitoring a manufacturing process includes generating a measurement data by analyzing emission intensity of plasma emission light using a measurement device, the plasma emission light being generated when a plasma gas of a manufacturing process device is changed from an energy level corresponding to a high energy state to an energy level corresponding to a low energy state, generating a compensated value based on the measurement data, the compensated value being generated by offsetting a sensitivity change that is caused due to pollution of the manufacturing process device and the measurement device or measurement locations of the measurement device, and monitoring the manufacturing process based on the compensated value.

Abstract: An assembly and to a device for obtaining monochromatic neutron radiation is provided. In order to realize a nuclear synthesis reaction, a starting material is introduced into a pressure booster (gas multiplier) and compressed to the pressure at which the synthesis reaction begins. The resulting neutron radiation passes through the seals of the multiplier elements and an outlet channel in the plug of the pressure chamber (gasostat) vessel, then onto a monochromator and further onto the irradiated object.

Abstract: Embodiments of systems and methods for compressing plasma are disclosed in which plasma can be compressed by impact of a projectile on a magnetized plasma in a liquid metal cavity. The projectile can melt in the liquid metal cavity, and liquid metal may be recycled to form new projectiles.

Abstract: Nuclear transformation method and apparatus can produce thermal energy and hydrogen with a simple structure. A reaction cell, made of metal material like iron, from which oxygen is discharged is heated by a heater at a temperature above 500° C. Water is supplied into the reaction cell to be changed into steam which reacts on the inner wall of the reaction cell to produce hydrogen and thermal energy through a nuclear transformation. In the case that a reaction agent (NaOH, K2TiO3) which includes at least alkaline metal and oxygen is accommodated in the reaction cell, a nuclear reaction occurs without the supply of water.

Abstract: A method, system, and apparatus are disclosed for liquid lithium first walls for electromagnetic control of plasmas in fusion power reactor environments. In particular, the method involves installing at least one layer of at least one tile on the surface area of the internal walls of the reactor chamber. A portion of the tile(s) facing the interior of the reactor chamber includes a plurality of channels. The method further involves applying an electric charge to the liquid lithium. Further, the method involves circulating the liquid lithium throughout the interior network of the tile(s) to allow for the liquid lithium to flow into the channels and to reach the external surface of the tile(s) that faces the interior of the reactor chamber. In some embodiments, the method also involves installing at least one magnetic coil between the tile(s) and the surface area of the internal walls of the reactor chamber.

Abstract: A method, system, and apparatus are disclosed for a complex shape structure for liquid lithium first walls of fusion power reactor environments. In particular, the method involves installing at least one tile on the surface area of the internal walls of the reactor chamber. The tile(s) is manufactured from a high-temperature resistant, porous open-cell material. The method further involves flowing liquid lithium into the tile(s). Further, the method involves circulating the liquid lithium throughout the interior network of the tile(s) to allow for the liquid lithium to reach the external surface of the tile(s) that faces the interior of the reactor chamber. In addition, the method involves outputting the circulated liquid lithium from the tile(s). In one or more embodiments, the reactor chamber is employed in a fusion reactor. In some embodiments, the tile is manufactured from a ceramic material or a metallic foam.

Abstract: A cooling device component of monobloc design has a heat shield made from tungsten, a tungsten alloy, a graphitic material or a carbidic material provided with a through-hole. A cooling pipe for carrying coolant is joined in the through-hole. The heat shield is in turn joined or metallurgically joined to a structural part made from a material with a tensile strength at room temperature of >300 MPa and an electrical resistivity of >0.04 Ohm mm2m?1.

Abstract: A compressor assembly and the method of using the same which includes an elongated spiral passageway within which a compact toroid plasma, such as a compact toroid plasma structure, can be efficiently compressed to a high-energy state by compressing the compact toroid plasma structure by its own momentum against the wall of the spiral passageway in a manner to induce heating by conservation of energy. The compressor assembly also includes a burn chamber that is in communication with the spiral passageway and into which the compressed compact toroid plasma structure is introduced following its compression.

Abstract: A hohlraum for an inertial confinement fusion power plant is disclosed. The hohlraum includes a generally cylindrical exterior surface, and an interior rugby ball-shaped surface. Windows over laser entrance holes at each end of the hohlraum enclose inert gas. Infrared reflectors on opposite sides of the central point reflect fusion chamber heat away from the capsule. P2 shields disposed on the infrared reflectors help assure an enhanced and more uniform x-ray bath for the fusion fuel capsule.

Abstract: A generally concentric sealed reactor vessel defining a volume. A concentric target electrode 12 centered within a nonconductive vessel 24. This vessel is suspended in insulating and cooling medium 242 composed of transformer oil. Deuterium gas 235 is contained within the volume at a predetermined pressure. High voltage, high frequency potential 130 is connected between the target electrode and Earth ground 153, creating an alternating electrical field within the reaction chamber. This electric field is of sufficient intensity ionize the contained gases, and result in the alternately radial outward acceleration and alternately radial inward acceleration of these ionized gases. On inward acceleration the ions impact the target and with one another at fusion reactive velocities causing fusion reactions. In the second embodiment the reactor vessel is a conductive material connected to the power supply and the defined volume is free of tangible structure.

Abstract: A generally spherical sealed reactor vessel defining a volume. A target sphere shaped electrode 11 is centered within a nonconductive reactor vessel 21. The target sphere is insulated from and fixedly centered within the nonconductive reactor vessel by an insulated stalk 22. This vessel is suspended in an insulating and cooling medium 241 composed of transformer oil. Deuterium gas 235 is released into and contained within the volume at a predetermined pressure. A source of high voltage, high frequency potential 130 is connected to the target electrode by an electrical connection 13. The other terminal of the high voltage, high frequency potential source is connected to Earth ground 153. The applied alternating electrical potential creates an alternating electrical field within the reaction chamber. This an oscillating electric field is formed within the enclosed space of nonconductive reactor vessel 21, extending between target electrode 11 and heat absorbent container 238.

Abstract: A first-wall component for a fusion reactor contains at least one heat shield having a first region inclined toward the plasma and a second region lying opposite the first region and formed of a graphitic material. The heat shield has one or more slots that end in the first or second regions and are oriented generally in the direction of an axis of the cooling tube. The components suitably cope with the mechanical stresses resulting both from production and from thermal cycling.

Abstract: In FIG. 1 3CRC. A generally spherical sealed reactor vessel defining a volume. A target sphere shaped electrode 11 is centered within a nonconductive reactor vessel 21. The target sphere is insulated from and fixedly centered within the nonconductive reactor vessel by an insulated stalk 22. This vessel is suspended in an insulating and cooling medium 241 composed of transformer oil. Deuterium gas 235 is released into and contained within the volume at a predetermined pressure. A source of high voltage, high frequency potential 130 is connected to the target electrode by an electrical connection 13. The other terminal of the high voltage, high frequency potential source is connected to Earth ground 153. The applied alternating electrical potential creates an alternating electrical field within the reaction chamber. This an oscillating electric field is formed within the enclosed space of nonconductive reactor vessel 21, extending between target electrode 11 and heat absorbent container 238.

Abstract: The invention relates to a first-wall component of a fusion reactor, which comprises at least one heat shield of a graphitic material and a cooling tube of copper or a copper alloy. Arranged between the heat shield and the cooling tube is a tube segment, which is connected at least in certain regions to the heat shield and to the cooling tube via copper-containing layers.

Abstract: Systems and methods for bonding ceramic materials are disclosed herein. In various embodiments, a process is provided comprising the steps of disposing a bonding material at least partially adjacent to a surface of a first silicon carbide component and at least partially adjacent to a surface of a second silicon carbide component, and bonding said first silicon carbide component to said second silicon carbide component by heating, wherein said bonding material comprises vanadium or titanium.

Abstract: Disclosed are a blanket using lithium nanofluid and a fusion reactor including the same. The blanket multiplies a fuel of the fusion reactor using lithium nanofluid, and applies the lithium nanofluid to a cooling process of cooling the blanket. In this instance, the lithium nanofluid is preferably obtained by dispersing a metal or a metal oxide nano-particle in liquid lithium. Also, the fusion reactor includes a blanket to accommodate plasma to generate a thermal energy due to a reaction of the plasma, a fuel feeding unit to feed a fuel required for the reaction of the plasma, the fuel feeding unit being connected to the blanket, a coolant feeding unit to feed a coolant, and a coolant transfer unit to transfer the coolant by connecting the blanket with the coolant feeding unit.

Abstract: A first-wall component of a fusion reactor has a heat shield and a heat sink. The heat shield is formed of a material from the group of graphite material, carbidic material, tungsten and tungsten alloy. The heat sink is formed of a spray-compacted copper alloy.

Abstract: A thermonuclear fusion system having a treatment chamber in which gas isotopes are fused to initiate a thermonuclear fusion reaction is disclosed. Specifically, the treatment chamber has an elongate housing through which liquid and gas isotopes flow longitudinally from an inlet port to an outlet port thereof. An elongate ultrasonic waveguide assembly extends within the housing and is operable at a predetermined ultrasonic frequency and a predetermined electrode potential to ultrasonically enhance the concentration of dissolved hydrogen gas isotopes within the housing or energize and electrolyze the liquid and gas isotopes within the housing. An elongate ultrasonic horn of the waveguide assembly is disposed at least in part intermediate the inlet and outlet ports, and has a plurality of discrete agitating members in contact with and extending transversely outward from the horn intermediate the inlet and outlet ports in longitudinally spaced relationship with each other.

Abstract: The characteristic analysis of erosion of NB31 carbon-fiber composite enables the proposal of a novel carbon-fiber composite structure having a distinctly reduced erosion rate. Improvement only relates to the arrangement of the sewing and web fibers and to maintaining the structure of the pitch/carbon fibers, which consist of the main NB31 heat conducting components. The sewing and web fibers of the improved structure reinforce the rigidness/reinforce the thermal shield, compared to the NB31. The improved structure improves the erosion rate so it is 4-5 times lower compared to that of NB31.

Abstract: A plasma reactor including a plasma generating electrode which includes a plurality of unit electrodes hierarchically layered at specific intervals, a casing in which the plasma generating electrode is disposed, and a power supply which applies a voltage to the unit electrodes, generating plasma in a space formed between the unit electrodes by applying a pulse voltage between the unit electrodes from the power supply, and capable of processing exhaust gas introduced into the space through reaction, the plasma reactor further including a light-transmitting section formed in the casing for externally detecting light emitted by the plasma, light detection means capable of detecting light emitted by the plasma through the light-transmitting section, and control means for controlling electric energy applied to the unit electrodes depending on intensity of light detected by the light detection means.

Abstract: A system for forming a thick flowing liquid metal, in this case lithium, layer on the inside wall of a toroid containing the plasma of a deuterium-tritium fusion reactor. The presence of the liquid metal layer or first wall serves to prevent neutron damage to the walls of the toroid. A poloidal current in the liquid metal layer is oriented so that it flows in the same direction as the current in a series of external magnets used to confine the plasma. This current alignment results in the liquid metal being forced against the wall of the toroid. After the liquid metal exits the toroid it is pumped to a heat extraction and power conversion device prior to being reentering the toroid.

Abstract: A plasma processing chamber having a chamber liner and a liner support, the liner support including a flexible wall configured to surround an external surface of the chamber liner, the flexible wall being spaced apart from the wall of the chamber liner. The apparatus can include a heater thermally connected to the liner support so as to thermally conduct heat from the liner support to the chamber liner. The liner support can be made from flexible aluminum material and the chamber liner comprises a ceramic material. The flexible wall can include slots which divide the liner support into a plurality of fingers which enable the flexible wall to absorb thermal stresses.

Abstract: A double-wall structure consisting of an inner wall, an outer wall surrounding said inner wall and reinforcing ribs that connect said outer and inner walls is produced by a piercing welding method in which an electron beam is externally applied at right angles to the outer wall, such that the welded structure of the outer wall and each rib is composed of at least two piercing weld beads that are spaced apart by an unwelded area, with the sum of the widths of the weld beads being at least 25% of the rib width and the length of the unwelded area exterior to the root of each bead being no more than 20% of plate thickness. The distortion in welding is sufficiently reduced to enable precise assembling of the double-wall structure that can be fabricated efficiently and which can reasonably withstand the large electromagnetic force caused by plasma disruption.

Abstract: A sealed passage is formed in a part of refractory composite material by inserting a tubular metal lining in a hole in the part, brazing material being interposed between the lining and the hole, and by heating to braze the metal lining to the wall of the hole, so that the metal lining defines a sealed passage (38). The metal lining (39) is plastically deformable under the conditions of use of the part such that differential expansion of thermal origin between the refractory composite material and the metal lining can be compensated by plastic deformation of the lining.

Abstract: A sealed passage is formed in a part of refractory composite material by inserting a tubular metal lining in a hole in the part, brazing material being interposed between the lining and the hole, and by heating to braze the metal lining to the wall of the hole, so that the metal lining defines a sealed passage (38). The metal lining (39) is plastically deformable under the conditions of use of the part such that differential expansion of thermal origin between the refractory composite material and the metal lining can be compensated by plastic deformation of the lining.

Abstract: A carbon fiber-reinforced carbon composite material, wherein carbon fibers are oriented substantially in the thickness direction, the ratio of the thermal conductivity in the thickness direction to the thermal conductivity in a direction perpendicular to the thickness direction is at least 2, and the thermal conductivity in the thickness direction is at least 3 W/cm..degree. C.

Abstract: A sealed passage is formed in a part of refractory composite material by inserting a tubular metal lining in a hole in the part, brazing material being interposed between the lining and the hole, and by heating to braze the metal lining to the wall of the hole, so that the metal lining defines a sealed passage (38). The metal lining (39) is plastically deformable under the conditions of use of the part such that differential expansion of thermal origin between the refractory composite material and the metal lining can be compensated by plastic deformation of the lining.

Abstract: A fusion reactor has an internal component in which an internal structure assembly is housed in a toric vacuum vessel in an arrangement along a circumferential direction thereof and in which a high-temperature plasma in which hydrogen and hydrogen isotopes are maintained in a plasma state is confined in a toric internal space defined in the internal structure assembly. The internal component includes a cooling structure of a multi-wall structure having multiple walls formed to the internal structure assembly and a flow channel formed in the cooling structure for a cooling fluid for extracting heat caused by plasma and a nuclear reaction.

Abstract: A carbon fiber-reinforced carbon composite material, wherein carbon fibers are oriented substantially in the thickness direction, the ratio of the thermal conductivity in the thickness direction to the thermal conductivity in a direction perpendicular to the thickness direction is at least 2, and the thermal conductivity in the thickness direction is at least 3 W/cm.multidot..degree.C.

Abstract: An electric generator using imploding plasma dynamics for generating electric energy from fuel energy, which includes a substantially cylindrical vortex chamber bounded by a cylindrical chamber wall having an axis, an inward curved fuel inlet end wall, and an opposite inward curved exhaust end wall; a shroud surrounding the vortex chamber forming an air space between the chamber wall and the shroud; at least one air inlet entering the air space at an angle tangential to the air space; air compressor means fluidly communicating with the air inlet for injecting air into the air space; fuel-air mixture injection means disposed in the fuel inlet end wall; a mixing chamber in the fuel-air mixture injection means for mixing fuel with the air fluidly communicatng with the air space; a plasma expansion cone having an inlet fluidly communicating with the mixing chamber for receiving fuel-air mixture from the mixing chamber; ignition means in the plasma expansion cone for igniting the fuel-air mixture, and forming at l

Abstract: An Fe-Cr-Mn alloy is disclosed which has the following composition by wt% and corrosion resistance of which is improved and deterioration in its strength is prevented at grain boundaries due to irradiation of high-energy particles such as neutrons: 5 to 40% of Mn, 5 to 18% of Cr, 2.0 to 12% of Al and the balance of Fe except for unavoidable impurities. In the alloy according to the present invention, Al is added to an Fe-Cr-Mn alloy by a restricted quantity as a main component element. As a result of the addition of Al, an alloy can be obtained in which lowering of concentration of Cr at grain boundaries due to irradiation of high-energy particles such as neutrons can be prevented or concentration of the solutes can be raised.

Abstract: The heat shield according to the invention makes it possible to protect a structure from a very high thermal flux. It is mainly constituted by tiles (2) fixed to a support structure (4) by means of a spring (8) fixed in translation with respect to a tile (2) and on which bears a locking arm (10). The latter can be fixed to the support structure (4) by means of locking screws (30), which are accessible from the outside through locking orifices (12) in the tile (2). The compression of the spring (8) allows locking to take place and also a satisfactory heat exchange from the tile (2) to the support structure (4), which can be cooled by cooling medium flow ducts (14).

Abstract: A structure of a nuclear fusion reactor having a vacuum vessel in which hydrogen isotope plasma is enclosed and a confining magnetic field generating coil for confining said plasma at a predetermined position in said vacuum vessel. It comprises a low tritium-permeable layer having lower tritium-permeability than that of a cooling metal base for forming a refrigerant passage for cooling the vacuum vessel on at least the surface adjacent to said plasma enclosed and a heat resistant and insulating fire member of the level higher than that of said cooling metal base for thermally shielding said low tritium-permeable layer from said plasma or corpuscular rays is formed on the low tritium-permeable layer. The similar processings are applied to the cooling metal base for forming the refrigerant passage for cooling a divertor disposed in the vacuum vessel and for neutralizing ionized corpuscles so as to exhaust them.

Abstract: A muon detector system including central and end air-core superconducting toroids and muon detectors enclosing a central calorimeter/detector. Muon detectors are positioned outside of toroids and all muon trajectory measurements are made in a nonmagnetic environment. Internal support for each magnet structure is provided by sheets, located at frequent and regularly spaced azimuthal planes, which interconnect the structural walls of the toroidal magnets. In a preferred embodiment, the shape of the toroidal magnet volume is adjusted to provide constant resolution over a wide range of rapidity.

Abstract: An actively cooled device, such as a heat shield for a fusion reactor, includes elements (10) of a heat-resistant material, particularly graphite, each being provided with at least one recess having a circular cross section, particularly a groove (14), into which a cooling pipe (16) conducting a coolant is brazed directly and with surface contact. This produces an effective dissipation of heat from the elements and a more durable connection of the elements with the cooling pipe or pipes.

Abstract: In a heat protective shield with solid protective element bodies (16), wh consist of highly heat-resistant material such as graphite, each containing a groove-like recess (20), and comprising cooling pipes (12) arranged in the recess (20), the wall portion forming the recess (20) surrounds the respective cooling pipe (12) in tongs-like manner and the protective element bodies (16) are connected to the associated cooling pipe solely in radially form-locking and axially force-locking manner.

Abstract: A neutron generating system comprising a hermetically sealed housing containing an ionizable gas and a ring anode and target cathode of a Penning ion source. The housing is provided with a recess axially oriented relative to the ring anode and target cathode and adapted to accept a removable samarium/cobalt magnet such that degassing and sealing of the housing can be performed in the absence of the permanent magnet. The cathode target is an OHFC copper rod of substantially the same cross-sectional area as the target with one polished end of the rod containing a titanium film within the housing to serve as the target and the other end of the rod extending out of the housing such as to remove thermal energy from the target during operation. An ion screen between the anode ring and cathode target containing an axially positioned gridded aperture provides a broad ion beam of reduced power per unit area.

Abstract: Nuclear devices are detonated periodically inside an underground cavity in which a working fluid absorbs most of the thermal energy released by the device detonation. The kinetic energy contained in the shock wave created within the working fluid is absorbed by shock absorbers located outside the inner wall of the cavity. This wall consists of adjacent plate segments that separate and recoil outwardly as do pieces of shells of fragmentation grenades. The shock wave kinetic energy is transferred to the segments that are constrained in their outwardly-directed flight by shock absorbers. The shock-absorbing system is solidly attached to the rock structure surrounding the cavity. The loading transmitted to the rock is of a much lower intensity than that which the plate segments sense, though of a much longer duration. The momentum trapped in the shock wave is thus absorbed by the rocks but in a manner such that the rock structure is not affected.

Abstract: A reversed field pinch apparatus is equipped with a first OH coil and a second OH coil which are inductively coupled with a plasma. The first OH coil is supplied a low-level alternating current for performing F-.THETA. pumping, while the second OH coil is supplied a high-level direct current for forming a plasma current.

Abstract: Method for extending service life of nuclear reactor components prepared from ductile, high strength crystalline alloys obtained by devitrification of metallic glasses. Two variations of the method are described: (1) cycling the temperature of the nuclear reactor between the operating temperature which leads to irradiation damage and a lThe U.S. Government has rights in this invention by virtue of Department of Energy, Office of Fusion Energy, Grant No. DE-AC02-78ER-10107.

Abstract: U-shaped limiter tiles placed end-to-end over a pair of parallel runners secured to a wall have two rods which engage L-shaped slots in the runners. The short receiving legs of the L-shaped slots are perpendicular to the wall and open away from the wall, while long retaining legs are parallel to and adjacent the wall. A sliding bar between the runners has grooves with clips to retain the rods pressed into receiving legs of the L-shaped slots in the runners. Sliding the bar in the direction of retaining legs of the L-shaped slots latches the tiles in place over the runners. Resilient contact strips between the parallel arms of the U-shaped tiles and the wall assure thermal and electrical contact with the wall.

Abstract: An array of connected plates mounted on the inside wall of the vacuum vessel of a magnetic confinement reactor in order to provide a protective surface for energy deposition inside the vessel. All fasteners are concealed and protected beneath the plates, while the plates themselves share common mounting points. The entire array is installed with torqued nuts on threaded studs; provision also exists for thermal expansion by mounting each plate with two of its four mounts captured in an oversize grooved spool. A spool-washer mounting hardware allows one edge of a protective plate to be torqued while the other side remains loose, by simply inverting the spool-washer hardware.

Abstract: A first wall construction for a tokamak reactor is disclosed, comprising a series of hollow lobes, each having a pair of side wall portions with a curved end wall portion extending therebetween. Each lobe is adapted to withstand substantial pressure on the concave side of the curved end wall portion while withstanding substantial heat flux on the convex side. The curved end wall portion has a shape which is approximately cylindrical in curvature but differs from being circular in curvature by a substantial deviation, in that such curved end wall portion is flatter in curvature than a truly circular curvature by the amount of such deviation, such that the thermal stresses generated in the curved end wall portion by such heat flux are at least approximately balance or neutralized by the bending stresses generated in such curved end wall portion by such pressure. The curvature may correspond generally in shape to the flatter half of an ellipse.

Abstract: An apparatus and method for simulating a fusion environment on a first wall or blanket structure. A material test specimen is contained in a capsule made of a material having a low hydrogen solubility and permeability. The capsule is partially filled with a lithium solution, such that the test specimen is encapsulated by the lithium. The capsule is irradiated by a fast fission neutron source.

Abstract: Apparatus for removing the helium ash from a fusion reactor having a D-T plasma comprises a helium trapping site within the reactor plasma confinement device, said trapping site being formed of a trapping material having negligible helium solubility and relatively high hydrogen solubility; and means for depositing said trapping material on said site at a rate sufficient to prevent saturation of helium trapping.