Abstract: The invention relates to a storage device (1) for storing and transporting nuclear fuel assemblies, the device comprising a plurality of adjacent compartments, each having a lateral wall and being capable of receiving a nuclear fuel assembly, the lateral walls being made using notched structural units (6a, 6b) that are stacked and crisscrossed. According to the invention, each unit (6a, 6b) comprises two spaced-apart flats (16, 18) made of a neutrophage material, as well as an intermediate structure (119) situated between the flats (16, 18) and in contact with them.

Abstract: In one characterization, the present invention relates to a radiation-shielding assembly for holding a container having a radioactive material disposed therein. The assembly may, at least in one regard, be referred to as an elution shield and/or a dispensing shield. The assembly includes a body at least partially defining a cavity. There is at least one opening through the body into the cavity. The assembly may include a cap that at least generally hinders escape of radiation from the assembly through the opening. The cap may be releasably attached to the body in one orientation and may establish non-attached engagement with the body in another orientation. The assembly may include an adjustable spacer system for adapting the assembly for use with containers having different heights.

Abstract: Embodiments of the present disclosure relate generally to transportation containers and assemblies, such as transportation containers and assemblies for containing and transporting radioactive material. A transportation assembly for transporting radioactive material generally includes an outer container defining an inner cavity, the outer container having an inner shell, wherein at least a portion of the inner shell includes a plurality of layers including at least one layer of chopped fiberglass mat and at least one layer of aramid fabric. The transportation assembly may further include an inner container disposed within the inner cavity of the outer container.

Abstract: A system, method and apparatus for providing additional radiation shielding to a ventilated cask for holding high level radioactive materials. The invention utilizes a tubular shell that is ancillary to the ventilated cask that circumscribes the ventilated cask to add radiation shielding protection while improving heat removal by natural convective air flow. Because the tubular shell and cask are non-unitary and slidably separable from one another, crane lifting capacity is not affected.

Abstract: A transport/storage cask for a radioactive material has an inner shell, an outer shell and a circular gamma ray shielding layer and a circular neutron shielding layer both of which are placed between the inner shell and the outer shell. The gamma ray shielding layer is formed by aligning a plurality of gamma ray shielding blocks composed of lead in a block shape in the circumferential direction. The entire gamma ray shielding block in the axial direction is covered with a copper tube having a higher elasticity limit than the gamma ray shielding block. In the above transport/storage cask, the gamma ray shielding layer composed of lead or a lead alloy is not easily deformed.

Abstract: The invention relates to a storage device (1) for the storing and/or transporting of nuclear fuel assemblies, including a plurality of adjacent housings each having a lateral wall and being able to receive a nuclear fuel assembly, the lateral walls being realized at least in part using stacking and intercrossing slotted structural assemblies (6a, 6b), each structural assembly including at least one plate (22) realized in a first material comprising aluminum. According to the invention, each structural assembly (6a, 6b) further includes a tubular cross-section element (20) inside of which is located said at least one plate (22), this tubular cross-section element (20) being realized in a second material selected from steels and titanium and alloys thereof.

Abstract: There is provided a method for selecting and configuring spent nuclear fuel bundles for casks so that the heat load for each of the casks is about the average heat load for all of the casks. The spent nuclear fuel bundles are disposed in the casks as low as reasonably achievable regarding the heat load.

Abstract: A system and method for storing high level waste. In one aspect, the invention is a system comprising: an outer shell having an open top end and a hermetically closed bottom end; an inner shell forming a cavity, the inner shell positioned inside the outer shell so as to form a space between the inner shell and the outer shell; at least one passageway connecting the space and a bottom portion of the cavity; at least one passageway connecting an ambient atmosphere and a top portion of the space; a lid positioned atop the inner shell, the lid having at least one passageway connecting the cavity and the ambient atmosphere; and a seal between the lid and the inner shell so at form a hermetic lid-to-inner shell interface.

Abstract: A pharmaceutical pig is used to transport a syringe containing a liquid radiopharmaceutical from a radiopharmacy to a medical facility for administration to a patient. The pharmaceutical pig includes an elongate polymer cap that is removably attached to an elongate polymer base. The elongate polymer cap includes a cap shell that completely encloses a cap shielding element and the elongate polymer base includes a base shell that completely encloses a base shielding element. Preferably the polymer utilized for the cap shell and the base shell is polycarbonate resin, e.g., LEXAN®. An inner liner is not utilized and the cap shielding element and the base shielding element, which are preferably, but not necessarily, made of lead, are completely sealed and unexposed.

Abstract: A pharmaceutical pig is used to transport a syringe containing a liquid radiopharmaceutical from a radiopharmacy to a medical facility for administration to a patient. The pharmaceutical pig includes an elongate polymer cap that is removably attached to an elongate polymer base. The elongate polymer cap includes a cap shell that completely encloses a cap shielding element and the elongate polymer base includes a base shell that completely encloses a base shielding element. Preferably the polymer utilized for the cap shell and the base shell is polycarbonate resin, e.g., LEXAN®. An inner liner is not utilized and the cap shielding element and the base shielding element, which are preferably, but not necessarily, made of lead, are completely sealed and unexposed.

Abstract: An improved method and apparatus for radiopharmaceutical purification, the apparatus including a chromatographic separating device, a UV-absorption detector, a radioactivity detector and a collection container having a collection inlet valve located at a collection location. Propagation times of eluent between the UV-absorption detector and the radiation detector, as well as between one or both of the detectors and the collection inlet valve, are determined. UV-absorption and radiation data from the detectors are monitored, and an appropriate time period during which the collection valve should be opened is established. Preferably, monitoring and operation of the apparatus is under control of a computer. A user interface display may be provided to enable an operator to monitor the purification process, and to intervene as required and/or appropriate.

Abstract: The invention relates to a device for the sealed docking (14) of mobile containers (42) equipped with plugs (44) of various diameters on a containment box (10). The device includes a center disk (22) and at least one docking flange (20a, 20b, 20c) that are concentric to each other, normally plugging the access opening (18) of the containment box. A locking/unlocking mechanism (24) makes it possible to only unlock the center disk (22) alone or the center disk and one or more of the docking flanges (20a, 20b, 20c), according to the diameter of the plug (44). This arrangement makes it possible, in particular, to clean the plug (44) of a mobile container (42) serving to transport contaminated nuclear equipment.

Abstract: A container for a vial of radiopharmaceutical, made of polymethyl methacrylate consists of a receptacle, with a cavity capable of containing the vial of radiopharmaceutical, and of a lid screwed onto the receptacle for closing the container, said lid presenting a central through-hole. A set, in combination with this container with the vial of radiopharmaceutical, consisting of a bottle of saline solution and two infusion catheters, enhances the radioprotection during the infusion of a radiopharmaceutical in an infusion operation.

Abstract: A collimator that formed from a plurality of metal layers that are shaped by use of lithographic techniques in specific shapes. The formed metal layers are stacked and aligned together and then connected together to form the collimator.

Abstract: The invention, in one characterization, may be said to be directed to a radiopharmaceutical system. In some embodiments, the system may include a radioisotope elution component and a radio-frequency identification (RFID) tag coupled to the radioisotope elution component. Other embodiments may include a radiation shielded enclosure having an interior, an exterior, and a radio-frequency identification (RFID) communication transmission passage extending between the interior and the exterior.

Abstract: A process for cleaning containers (pigs) in which radioactive drugs are shipped to health care providers, after than are returned to a pharmacy and may contain residual radioactive material, blood, microorganisms and other contaminants. Those pigs that are contaminated with radioactive material are removed from the cleaning process until they have decayed to the background radiation level. The upper and lower portions of each blood contaminated pig is disinfected. Each pig is washed at a temperature of at least 180° Fahrenheit for a least one minute to kill bacteria and viruses. The combination of a disinfectant and high washing temperature water provides an optimum level of sterilization.

Abstract: A storage-transport system includes a storage container and a transport container for respectively storing and transporting weak to intermediate level active nuclear waste. The storage-transport system has different containers for the functions of storage and transport, namely the storage container and the transport container. The storage container only meets the requirements for temporary storage which are less strict than the requirements for the transport container, thereby allowing for a simple and therefore less expensive construction of the storage container. A method for storing and for transporting radioactive waste is also provided.

Abstract: A concrete material is disclosed according to one embodiment. The concrete material may include a mixture of cement, granular rubber and boron in various forms and ratios. The boron may include boron carbide. The rubber may be recovered rubber from used automobile and/or truck tires. Various other components may be added to the cement, such as, for example, binders, water, sand, rock, or other aggregates. Embodiments described herein may be used in radiation shielding applications, such as, for example, nuclear waste facilities, nuclear storage and/or transportation casks, nuclear power plants, medical waste facilities, illicit drug detection facilities, linear accelerator facilities, etc.

Abstract: The invention relates to the handling of radioactive material. For instance, a radiation shield of the invention may include a body having a cavity therein for receiving radioactive material. An opening to the cavity may be defined in the body. A base may be releasably attachable to the body (generally toward the opening) to at least partially enclose the radioactive material in the cavity. In the case that the radiation shield includes a plurality of interchangeable bases, one of the bases may have at least one of a shorter length and a lighter weight than another of the bases. The base(s) may be designed to enclose more than one size and/or shape of container in the cavity. The base(s) may include a hand grip to facilitate manual gripping of the radiation shield. The base(s) may include a guard to reduce exposure to radiation from manual handling of the radiation shield.

Abstract: Spherical storage containers for radioactive materials, such as plutonium oxides and salts, are comprised of coupled hemispheres joined by helical threads or bayonet connections. The spherical storage containers are supported in a barrel by a vertical strut and laterally extending straps or are supported in cylindrically configured frames.

Abstract: The invention relates to the confinement of an alloy formed of actinide transuranic radioactive wastes and beryllium metal within a neutron moderating and reflecting apparatus to cause accelerated destruction (burning) of the actinide wastes. Waste actinides, including plutonium, neptunium, americium, and curium, emit alpha particles by radioactive decay. The alpha particles are converted into neutrons by the beryllium through an alpha-neutron (alpha, n) reaction. The neutrons developed by the alpha, n reaction are moderated by a surrounding layer of graphite, which allows the slowed neutrons to cause additional fission or decay events within the waste actinide alloy. This process is passive because the alpha particles that initiate the actinide burning are an intrinsic physical property of the actinides.

Abstract: A radioactive substance storage container 1 includes a trunk body 2, a neutron shielding container 3, and a neutron shielding body 8. The trunk body 2 is a bottomed container including a trunk 2A, a bottom 2B provided at one end of the trunk 2A, and an opening 2H opened to the side opposite from the bottom 2B, and storing therein recycled fuel, and is, for example, manufactured by casting. The neutron shielding container 3 includes a cylindrical inner tube 4 attached to the trunk body 2 by being fitted thereto, a cylindrical outer casing 5 disposed outside the inner tube 4, and heat transfer fins 7 that connect the inner tube 4 and the outer casing 5. The neutron shielding body 8 is disposed in a space surrounded by the inner tube 4, the heat transfer fins 7 and 7 adjacent to each other, and the outer casing 5.

Abstract: The present disclosure includes an electron beam emitter, a roller for a web, circumferential radiation shielding, a reaction chamber, movement between open and closes positions, a depositor, baffles, inert gas dispenser, and other features. One example in the present disclosure is a web carrying roller for electron beam irradiation of the web on one side of that roller within a baffle-containing shielded area, while another side of that roller is outside of the shielded area, and near the two ends of the roller are arcuate tongue and groove barriers to x-radiation leakage from the shielded area. The baffle-containing shielded area has a series of voids separated by walls, rather than having the shielded area positioned close to the circumference of the cylinder along its length.

Abstract: A radiation source container comprising: a radiation source capsule (1); a radiation source holder (4) having an aperture (B) that emits unidirectionally radiation emitted from a radiation port A of the radiation source capsule, that provides screening such that no leakage of radiation takes place except from this aperture, and that fixes this radiation source capsule (1) in a manner that is difficult to attach or detach; a container (7) that accommodates the radiation source holder (4) and that has an irradiation window (C) that transmits radiation emitted from the aperture; an attenuation plate (3) provided between the radiation port of the radiation source capsule and the irradiation window, that attenuates beforehand the amount of radiation emitted; a shutter (6) provided between the attenuation plate (3) and the irradiation window (C) and that screens the radiation emitted from the irradiation window; and a capsule cover whereby, when the recommended use period in respect of the sealing performance of th

Abstract: An improved photodiode detector shielding apparatus and method are provided which shield a photodiode detector from electromagnetic interference and ambient light, without affecting the wavelengths of light that reach the photodiode. The improved photodiode detector shield has two layers. A bottom layer is substantially made from an electrically conducting material and is fixed over a photodiode in order to shield it from EMI and ambient light. A top layer is substantially made from a lustrous, shiny, reflective material that reflects an equal amount of light across a band of wavelengths. Both layers have areas with optically transmissive openings, which are aligned to allow for the unobstructed passage of light of a band of wavelengths to the photodiode. Light within a band of wavelengths is evenly reflected off the top of the first surface and also reaches the photodiode.

Abstract: A system, method and apparatus for providing additional radiation shielding to a container holding radioactive materials. The invention utilizes a sleeve-like structure that is slid over a container holding high level radioactive materials to add radiation shielding protection. Because the sleeve-like structure and container are non-unitary and slidably separable from one another, crane lifting capacity is not affected.

Abstract: Transport and storage of nuclear fuel assemblies may require double confinement depending on the circumstances. A device and a method are described to perform this double conditioning without the need of a hot containment, and in which the loading and pre-positioning steps can take place in a pool. The device (10) includes a metallic inner leak tight conditioning receptacle (20) and a metallic outer leak tight receptacle (30). When the inner receptacle (20) is located in the outer receptacle (30), a passage (15, 25) remains free between the two receptacles, from the open end to the bottom of the outer receptacle. The outer receptacle (30) can be drained through this passage, particularly by a dip tube (33).

Abstract: The present disclosure relates to a thermo formed tray having an upper half and a lower half. The upper half and the lower half define a closed configuration when the upper half and the lower half are substantially adjacent one another and an open configuration when the upper half and the lower half are substantially apart from one another. A predetermined area is provided in at least one of the upper half and the lower half for containing a product in the closed configuration, the product having at least one radioactive seed held in a predetermined seed configuration. At least one cutter guide is contained in the thermoformed tray.

Abstract: A radiation-shielding assembly can contain any of multiple containers of different sizes in a predetermined, fixed location within the assembly. A clamping system in of the assembly is able to clamp any of the containers so that they are held in the same fixed location within the assembly. The containers, regardless of size, are always located in the desired position within the shield. The positive location is achieved with out the use of separate components not attached to the assembly.

Abstract: A cover for a syringe includes an elongated flexible envelope and an absorbent material. The elongated flexible envelope includes a body portion and a needle-receiving portion. The body portion has a first end that defines an opening and an opposite second end. The needle-receiving portion extends from the second end of the body portion and terminates in a distal end. The body portion and the needle-receiving portion define a cavity of sufficient size to allow the syringe to be placed therein. The cavity is in communication with the opening. The envelope is made of a material that is impervious to liquid. The absorbent material is disposed in the distal end of the needle-receiving portion.

Abstract: Systems, devices, and methods for filling containers with radioactive materials are described. In certain embodiments, the systems comprise a shielding material that substantially defines a chamber and, preferably, substantially blocks radioactivity, a conduit extending through the shielding material into the chamber, and a securing unit that is disposed in the chamber proximal to the conduit and is adapted to receive a container through the conduit.

Abstract: A long-term storage container (1) for storage of radioactive material to inhibit radioactive radiation therefrom to the outside of the container, the top of said container to be closed by a screw-on radioactive radiation inhibiting lid (7), said container having an integral inner container part (2; 34; 62; 62?) of a first material, e.g. plastic material, an integral outer container part (3; 43; 69) of a second material, e.g. plastic material, and radioactive radiation inhibiting material (4; 38; 68) in an inter-space between the walls and bottoms of said inner and outer container parts. To fill the inter-space an inter-space container part (4; 38; 68) is integrally moulded through injection or pressure moulding and then fitted onto the inner container part (2; 34; 62; 62?) to subsequently mould the outer container part (3; 43; 69) onto the outside of the inter-space container part (4; 38; 68). A specially made container lid (7) is provided.

Abstract: A fuel rack for supporting radioactive fuel assemblies in an underwater (or other submerged) environment that reduces the depth required for the pool to effectuate the fuel rack loading procedure. The fuel rack is specially designed to afford lateral loading. In one embodiment, the fuel rack comprises a body structure comprising at least one substantially vertically oriented elongated cell for receiving a nuclear fuel assembly, the body having a top, a bottom and a first lateral side; at least one elongated slot in the first lateral side of the body structure that forms a passageway into the cell through which a vertically oriented fuel assembly can be loaded; and means for supporting a fuel assembly within the cell in a substantially vertical orientation. In another embodiment, the invention is a method of laterally loading a fuel rack that utilizes rotation of the fuel assembly to secure the fuel assembly within its designated cell.

Abstract: An improved method and apparatus for radiopharmaceutical purification, the apparatus including a chromatographic separating device, a UV-absorption detector, a radioactivity detector and a collection container having a collection inlet valve located at a collection location. Propagation times of eluent between the UV-absorption detector and the radiation detector, as well as between one or both of the detectors and the collection inlet valve, are determined. UV-absorption and radiation data from the detectors are monitored, and an appropriate time period during which the collection valve should be opened is established. Preferably, monitoring and operation of the apparatus is under control of a computer. A user interface display may be provided to enable an operator to monitor the purification process, and to intervene as required and/or appropriate.

Abstract: The invention relates to a canister (1) for final repository of spent fuel elements from a nuclear reactor, comprising an insert (2) that contains said spent fuel elements, an inner copper casing (4a, 4b, 4c) that encloses the insert (2), and at least one outer casing (5a, 5b, 5c) that encloses the copper casting and that consists of a passive-film-forming metal or metal alloy, the passive film on the casing being constituted by an essentially oxidic film that is rich in one or more of the metals in the group of metals that consist of the metals zirconium, chromium and titanium.

Abstract: The invention provides an ion current measurement device for a tool having an ion source. The ion current measurement device comprises an ion collecting cup and a replaceable liner. The ion collecting cup is disposed in the tool and the ion collecting cup possesses a cup opening facing the ion source. The replaceable liner is disposed in the ion collecting cup and the replaceable liner entirely covers a continuous inner sidewall of the ion collecting cup.

Abstract: A fast reactor 1 controlled with a reflector comprises: a reactor vessel 7 accommodating therein a coolant 5; a reactor core 2 disposed in the reactor vessel 7 and immersed in the coolant 5; and a reflector 4 that vertically moves for adjusting leakage of neutrons generated from the reactor core 2 to control a reactivity of the reactor core 2, the reflector 4 including a neutron reflecting part 4a disposed on an outside of the reactor core 2 in a vertically movable manner, the neutron reflecting part 4a having a neutron reflecting ability higher than that of the coolant 5, and a cavity part 4b positioned above the neutron reflecting part 4a, the cavity part 4b having a neutron reflecting ability lower than that of the coolant 5. The neutron reflecting part 4a is formed of a plurality of metal plates 37 that are stacked on each other. Each of the metal plates 37 has a plurality of coolant channels 36 through which the coolant 5 flows.

Abstract: A pharmaceutical pig is used to transport a syringe containing a liquid radiopharmaceutical from a radiopharmacy to a medical facility for administration to a patient. The pharmaceutical pig includes an elongate polymer cap that is removably attached to an elongate polymer base. The elongate polymer cap includes a cap shell that completely encloses a cap shielding element and the elongate polymer base includes a base shell that completely encloses a base shielding element. Preferably the polymer utilized for the cap shell and the base shell is polycarbonate resin, e.g., LEXAN®. An inner liner is not utilized and the cap shielding element and the base shielding element, which are preferably, but not necessarily, made of lead, are completely sealed and unexposed.

Abstract: A device containment apparatus includes a vessel for storing an explosive device and minimizing dispersal of radioactive material. The vessel includes an outer wall defining an interior area. A first frame supports the vessel and supports a first or outer radiation shield that is spaced from the vessel. A second or inner radiation shield can also be provided, supported adjacent the vessel's outer wall by a second frame that includes upper and lower frame rings. The vessel and the second radiation shield can be generally spherical, while the first frame is substantially rectangular, and the first radiation shield includes substantially planar sides.

Abstract: A system and method for storing multiple canisters containing high level waste below grade that afford adequate ventilation of the spent fuel storage cavity. In one aspect, the invention is a system comprising: an air-intake shell forming a substantially vertical air-intake cavity; a plurality of storage shells, each storage shell forming a substantially vertical storage cavity; a hermetically sealed canister for holding high level waste positioned in one or more of the storage cavities so that a gap exists between the storage shell and the canister, the horizontal cross-section of each of the storage cavities accommodating no more than one canister; a removable lid positioned atop each of the storage shells so as to form a lid-to-shell interface, each lid containing an outlet vent forming passageways between an ambient environment and the storage cavity; and a network of pipes forming a passageway between a bottom portion of the intake cavity and a bottom portion of each of the storage cavities.

Abstract: The present invention provides a radiation-shielding container for a radiopharmaceutical that may be magnetically picked and placed, assembled and dis-assembled.

Abstract: A long-term antimatter storage device that may be energized by a low power magnetron and can function autonomously for hundreds of hours on the energy provided by batteries. An evacuated, cryogenic container is arranged with a source of positrons and a source of electrons positioned in capture relation to one another within the container so as to allow for the formation of a plurality of positronium atoms. A microwave resonator is located within the container forming a circularly polarized standing wave within which the plurality of positronium atoms rotate. Radioactive sources for small stores and low energy positron accelerators for large stores are used to efficiently fill the device with positronium in seconds to minutes. The device may also be arranged to provide for the extraction of positrons. A method for storing antimatter is also provided.

Abstract: A method is disclosed to determine an inspection protocol for radioactive material in shipping containers using an inspection technique threshold characteristic. The method includes weighing a container prior to shipment and determining a relative position of the container weight to at least one of a number of predetermined inspection technique threshold lines in an inspection threshold characteristic. Each of the of the predetermined inspection technique threshold lines corresponds to at least one of a number of inspection techniques. The container is classified as either a heavy container or a light container relative to at least one of the inspection techniques according to the relative position of the container weight to at least one of the predetermined inspection technique threshold lines. An inspection protocol for radioactive material in the container is selected according to the classification of the container.

Abstract: A method and apparatus for transporting radiopharmaceuticals. Typically, the apparatus is a two-part assembly, each part having an exterior shell, a radiation shield and a non-porous lining. Additionally, the assembled apparatus has a sealed internal chamber suitable for carrying a syringe or a sharps container containing a syringe. The internal chamber of the radiopharmaceutical pig is lined with a non-porous lining, typically a durable plastic, that prevents contamination of the radiopharmaceutical doses, the radiation shield, or the environment. Additionally, the non-porous lining can be quickly and easily cleaned and sterilized, avoiding the often difficult, to impossible, task of cleaning and sterilizing the radiation shield of the radiopharmaceutical pig. The non-porous lining is surrounded by a radiation shield that is typically comprised of elemental lead. The radiation shield prevents radiation from the radiopharmaceutical from contaminating the user or environment.

Abstract: A lead shielding for a betatron in an X-ray generator is provided that includes at least four shielding parts of which two are semi-cylindrical and provided with recesses in the envelope surfaces thereof. The semi-cylindrical shielding parts are arranged in corresponding recesses of the remaining shielding parts by means of the envelope surfaces thereof, such that the recesses in the envelope surfaces form air channels between the semi-cylindrical shielding parts and the remaining shielding parts.

Abstract: A radioactivity dose calibrator system measures the quantity of radioactive material contained in a sample-vial or syringe without removing the vial or syringe from its primary radiation shield. The system comprises a first radiation detector, a second radiation detector, a transportable, shielded radioactive material sample-holder, a signal-processing circuit and a video display.

Abstract: A device for producing a fluid containing a radioactive constituent, comprising a shielded chamber (5) with an opening for receiving an isotope container (6) housing a radioactive isotope (7); a chamber closure (18) adapted for cooperating with and closing the chamber opening; a first fluid port comprising a first hollow needle projecting into the shielded chamber from the chamber closure for fluid communication with the isotope container; a second fluid port comprising a second hollow needle projecting into the shielded chamber from the closed end of the chamber opposite the chamber closure for fluid communication with the isotope container; first and second compressible buffers (28, 29) mounted so as to surround at least partially the respective first and second hollow needles (12, 13), each buffer providing an outer surface for contact with opposed ends of the isotope container; and a spacer of a predetermined thickness associated with one or each of the first and second compressible buffers for determinin

Abstract: A system and method for storing spent nuclear fuel that affords adequate cooling capabilities under “smart flood” criteria.

Abstract: The invention relates to the confinement of an alloy formed of actinide transuranic radioactive wastes and beryllium metal within a neutron moderating and reflecting apparatus to cause accelerated destruction (burning) of the actinide wastes. Waste actinides, including plutonium, neptunium, americium, and curium, emit alpha particles by radioactive decay. The alpha particles are converted into neutrons by the beryllium through an alpha-neutron (alpha, n) reaction. The neutrons developed by the alpha, n reaction are moderated by a surrounding layer of graphite, which allows the slowed neutrons to cause additional fission or decay events within the waste actinide alloy. This process is passive because the alpha particles that initiate the actinide burning are an intrinsic physical property of the actinides.

Abstract: A structure of an electron beam apparatus having shielding properties for shielding against an environmental magnetic field is provided. The electron beam apparatus comprises a mirror barrel for housing a magnetic lens for converging an electron beam onto a specimen and a specimen chamber for housing the specimen, wherein a non-magnetic material having conductivity is used as a material for at least one of the mirror barrel and a main body of the specimen chamber. The material for the mirror barrel or the main body of the specimen chamber is an aluminum alloy and a thickness of a sidewall of the mirror barrel or the main body of the specimen chamber is 10 mm or more. A magnetic plate having a thickness smaller than that of the sidewall of the mirror barrel or the main body of the specimen chamber is provided on an inner sidewall of the mirror barrel or the main body of the specimen chamber.