Abstract: System and methods are disclosed for controlling a nuclear reactor that uses fuel having plutonium-239. The nuclear reactor includes a neutron moderator, such as ZrH1.6, which behaves as an Einstein oscillator and increases the energy of thermal neutrons into the Pu-239 neutron absorption resonance as the temperature of the nuclear reactor increases. A neutron absorbing element with neutron absorption around 0.3 eV is added to the nuclear reactor to suppress any reactivity gain that can occur due to the increase in temperature. The amount of the neutron absorbing element to be added to the nuclear reactor is calculated such that the reactivity gain that may occur at any time during the life of the fuel is suppressed.

Abstract: An example of a nanoballoon thermal protection system includes a refractory ceramic foam having carbide balloons. The foam has a closed cell structure not allowing liquid to penetrate through the foam. Each of the carbide balloons is hollow and has a diameter greater than 0 nm and less than 900 nm. Each of the carbide balloons includes a refractory carbide. In addition, a vehicle with thermal shield includes a surface and a first and second nanoballoon closed cell foam coatings. Each of the foam coatings has a melting point temperature greater than 1000° C. and a density less than 85%. Each of the foam coatings has hollow balloons having a diameter less than 900 nm. Each of the foam coatings includes a closed cell structure not allowing liquid to penetrate through the respective coating. Methods for manufacturing a nanoballoon system and a nanoballoon thermal protection system are also disclosed.

Abstract: A nuclear reactor includes a pressure vessel, and a control rod assembly including at least one movable control rod comprising a neutron absorbing material, a control rod drive mechanism (CRDM) for controlling movement of the at least one control rod, and a coupling operatively connecting the at least one control rod and the CRDM. The coupling includes a first portion comprising a first material having a first density at room temperature, and a second portion comprising a second material having a second density at room temperature that is greater than the first density. In some embodiments the coupling includes a connecting rod including a hollow or partially hollow connecting rod tube comprising a first material having a first density and a filler disposed in the hollow or partially hollow connecting rod tube, the filler comprising a second material having a second density greater than the first density.

Abstract: The invention concerns a control rod configured for a nuclear power light water reactor of the BWR or PWR kind. The control rod contains absorber material. At least 50%, with respect to weight, of the absorber material that is in the control rod is in the form of hafnium hydride. The invention also concerns the use of such a control rod during operation in a nuclear power light water reactor of the BWR or PWR kind.

Abstract: A reactor core is immersed in a liquid metal coolant in a core barrel of a liquid metal cooled reactor. The reactor core includes a plurality of fuel assemblies contained in the core barrel, a neutron absorber that absorbs a neutron in the reactor core, and a neutron moderator that moderates a neutron therein so as to control a reactivity of the reactor core. The neutron absorber and the neutron moderator constitute a mixture contained in reactivity control assemblies of the reactor core in the liquid metal coolant prior to immersion of the reactor core. The neutron moderator is composed of zirconium hydride.

Abstract: A neutron absorbing insert for use in a fuel rack and method of manufacturing the same. In ones aspect, the invention is a neutron absorbing apparatus comprising: a plate structure having a first wall and a second wall that is non-coplanar to the first wall; the first and second walls being formed by a single panel of a metal matrix composite having neutron absorbing particulate reinforcement that is bent into the non-coplanar arrangement along a crease; and a plurality of spaced-apart holes formed into the single panel along the crease prior to bending.

Abstract: An advanced gray rod control assembly (GRCA) for a nuclear reactor. The GRCA provides controlled insertion of gray rod assemblies into the reactor, thereby controlling the rate of power produced by the reactor and providing reactivity control at full power. Each gray rod assembly includes an elongated tubular member, a primary neutron-absorber disposed within the tubular member said neutron-absorber comprising an absorber material, preferably tungsten, having a 2200 m/s neutron absorption microscopic capture cross-section of from 10 to 30 barns. An internal support tube can be positioned between the primary absorber and the tubular member as a secondary absorber to enhance neutron absorption, absorber depletion, assembly weight, and assembly heat transfer characteristics.

Abstract: A method for recycling AgInCd control rod absorber bar material from a used control rod from a nuclear power plant includes sectioning AgInCd absorber bar from a used control rod into a first section and a second section, the first section having a higher radioactivity than the second section; and recycling the material of the second section of the AgInCd absorber bar.

Abstract: A control rod is used to control the reaction of a nuclear reactor. The control rod comprises one or more internal rodlet(s) and a hafnium skin that serves as the outermost layer, rather than a stainless steel cladding. Several variations on rodlets are contemplated. The rodlets are made of hafnium or Ag—In—Cd. The resulting control rod, due to the lack of a stainless steel cladding, has a greater rod reactivity worth, increased weight, and high flexibility.

Abstract: A neutron reactor includes a neutron shield which is disposed outside a nuclear reactor core and adapted to absorb neutrons leaking from the core. The neutron shield includes a plurality of containers each of which contains a powdered neutron absorbing material and which are stacked with one another in a vertical direction, and a cladding tube which houses the containers. The neutron absorbing material is composed of B4C powder.

Abstract: A control rod for a pressurized-water nuclear reactor contains an absorber rod which is arranged in a casing tube. At least in a lower section, the absorber rod is provided with at least one recess which takes up at most a portion of the circumferential surface of this section. This reduces problems associated with an expansion in the volume of the absorber rod.

Abstract: A fast reactor having a reactivity control reflector has a reactor vessel in which a coolant is accommodated, a reactor core which is installed in the reactor vessel and dipped with the coolant, and a reflector installed outside of the reactor core so as to be movable in a vertical direction for controlling the reactivity of the reactor core. The reflector of the fast reactor has a lower neutron reflecting portion having a neutron reflection capability higher than that of the coolant and an upper cavity portion located above the neutron reflecting portion and having a neutron reflection capability lower than that of the coolant. The cavity portion is composed of a plurality of cylindrical hermetically-sealed vessels.

Abstract: The present invention provides a gray rod control assembly (GRCA) containing an improved neutron absorber comprised of a porous matrix of refractory metal infused with a neutron absorbing metal or metal alloy for a nuclear reactor. The reactor has a plurality of fuel assemblies, each including numerous elongated fuel rods supported in an organized array by substantially transverse support grids, and a plurality of guide thimbles disposed through the support grids and along the fuel rods. The GRCA includes a spider assembly structured to provide controlled insertion of gray rod assemblies within the thimbles of the fuel assembly, thereby controlling the rate of power produced by the reactor. Each gray rod assembly includes an elongated tubular member, a first end plug, a second end plug and the improved neutron-absorber disposed within the tubular member.

Abstract: The present invention relates to a control rod blade for a boiling water reactor. The control rod blade comprises a plurality of channels, which are arranged to receive an absorber material, a free edge portion with a recess, which comprises outlets for said channels, and a cover element , which is arranged to be attached by means of at least one welding operation such that it seals at least a part of said recess . Furthermore, the control rod blade comprises a profile element , which, before said welding operation of the cover element is performed, is arranged to be applied against a bottom surface in the recess in a position such that the profile element covers the outlets of said channels.

Abstract: The present invention relates to a control rod blade for a boiling water reactor. The control rod blade (2) comprises a free edge portion with a recess (7) which comprises a plurality of outlets, arranged in a row, for channels (3), which are arranged to receive an absorber material (10) and a cover element (4) arranged to be attached along at least a section of the edge portion. The cover element (4) comprises a cover portion (12) arranged to seal the opening of the recess (7) and a support portion (13) arranged to, in a mounted state, abut a bottom surface in the recess (7) and to allow the formation of at least a passage (16) between the outlets of the channel (3) in the recess (7).

Abstract: A control cluster for a pressurized water nuclear reactor comprising a bundle of neutron-absorbing rods each of which comprises a metal tube called cladding which is sealed off by a top end plug at its top end and by a bottom end plug at its bottom end and has a support, or spider, of radiating shape to which the absorber rods are attached through their upper end plugs, characterized in that the cladding of at least some of the absorber rods is weld-free hafnium tubes, the top end plugs of the absorber rods having hafnium cladding being of titanium-based alloy and being welded to the top end part of the hafnium cladding of the absorber rod, the bottom end plugs being of massive hafnium and being welded to the bottom.

Abstract: An advanced gray rod control assembly (GRCA) is for a nuclear reactor. The reactor has a plurality of fuel assemblies each including numerous elongated fuel rods supported in an organized array by substantially transverse support grids, and a plurality of guide thimbles disposed through the support grids and along the fuel rods. The GRCA includes a spider assembly structured to provide controlled insertion of gray rod assemblies within the thimbles of the fuel assembly, thereby controlling the rate of power produced by the reactor. Each gray rod assembly includes an elongated tubular member, a first end plug, a second end plug, a substantially pure silver neutron-absorber disposed within the tubular member, and a support tube surrounding the neutron-absorber within the tubular member to resist silver-swelling. Delta-power of the reactor is improved by minimizing the exposed surface area of the absorber and distributing it among all of the rods of the GRCA.

Abstract: A neutron absorbing coating for use on a substrate, and which provides nuclear criticality control is described and which includes a nickel, chromium, molybdenum, and gadolinium alloy having less than about 5% boron, by weight.

Abstract: A reactivity control rod adapted to be used in a reactor core of a fast reactor and disposed at a substantially central portion of the reactor core for controlling a reactivity therein. The reactivity control rod includes a wrapper tube surrounded by a plurality of fuel rods in a reactor core, and a plurality of neutron absorber rods arranged in the wrapper tube. At least one of the plurality of neutron absorber rods includes a cladding tube and a mixture filled in the cladding tube. The mixture is composed of a neutron absorber that absorbs a neutron and a neutron moderator that moderates the neutron.

Abstract: An absorber body arranged to absorb radiation in a nuclear energy arrangement. The absorber body comprises more than one area with a locally reduced thickness.

Abstract: A control rod for a BWR according to the present invention comprises a first unit composed of a tie rod, a handle mounted on an axially upper portion of the tie rod and a lower support member or falling speed limiter mounted on a axially lower portion of the tie rod; and a second unit composed of a sheath containing therein reactivity control material, an upper end plate mounted on an axially upper portion of the sheath and a lower end plate mounted on an axially lower portion of the sheath, wherein an upper portion of the upper end plate is fixed to the handle, a lower portion of the lower end plate is fixed to the lower support member or falling speed limiter, whereby the control rod is constructed as a joined body of the first unit and the second unit.

Abstract: A sleeve assembly for refurbishing a fuel rack having cells in which fresh or spent nuclear fuel assemblies may be stored, in which the cells have elongate rack walls extending from a rack base plate and the rack base plate has flow holes communicating with the cells. The sleeve has at least one elongate wall extending from the topside of a sleeve base having an opposed bottom side. The sleeve base has a flow hole extending therethrough that communicates with one of the rack base plate flow holes. A pin assembly disposed in the sleeve base flow hole has resilient tabs extending beyond the bottom side of the sleeve base for extending into a rack base plate flow hole and resiliently engaging the rack base plate when the sleeve assembly is installed in one of the cells. The pin assembly resists horizontal and vertical movements of the sleeve assembly, permits water flow into the cell and permits sleeve assembly removal tools and inspection devices to access the pin assembly.

Abstract: An alloy of zirconium and niobium that includes erbium as a consumable neutron poison, its method of preparation and a component comprising said alloy are provided. This invention relates to an alloy of zirconium and niobium that includes erbium as a consumable neutron poison. The invention also relates to a method for the preparation and conversion of said alloy and a component comprising said alloy. Such an alloy is particularly intended for the manufacture of cladding and/or other elements or structural components of fuel assemblies for nuclear reactors using water as coolant.

Abstract: A hermaphroditic absorber exploits the inherent spatial change in the neutron spectrum within a lumped poison mass in a thermal reactor neutron flux field. The hermaphroditic absorber (poison mass) incorporates two types of absorbers, the first being a strong thermal absorber near the surface of the mass, and the second being a strong resonant absorber in the interior of the poison mass. The outer regions of the poison mass are comprised of a strong “1/v” thermal absorber, and the inner region of the poison mass is comprised of a resonance absorber. This resonance absorber more appropriately exploits the hardened characteristics of the neutron spectrum within the absorber mass by selectively absorbing the epi-thermal neutrons. The creation of the hermaphroditic poison mass permits an increase in the control material worth while maintaining the external dimension of the structure containing the control material, such as a BWR control rod.

Abstract: A neutron shield is formed of a boron carbide-metal matrix composite having a density ranging from 2.5 to 2.8 g/cm.sup.3 and a composition ranging from approximately 10 to 60 weight % of boron carbide and 40 to 90 weight % of metal matrix. The metal matrix is aluminum, magnesium, titanium, or gadolinium or one of their alloys. The boron carbide includes one or more metal elements added to improve the chelating properties of the metal matrix material by forming intermetallic bonds with the metal matrix material. The metal additives are present in the composite in an amount less than approximately 6% by weight. The shield may be in container or plate form.

Abstract: The alloy contains, expressed in atomic percentages, 9 to 12% of indium and 4 to 5.35% of cadmium, the remainder consisting of silver with the exception of unavoidable impurities in very low quantities. The alloy preferably contains 9 to 10% of indium and 4.35% to 5.35% of cadmium. The alloy can be used in the form of pellets or bars placed inside a tubular casing, in order to form a neutron-absorber component of a rod cluster for controlling the reactivity of a pressurized water nuclear reactor.

Abstract: A replacement rod for insertion into a nuclear fuel assembly to replace a fuel rod containing a neutron absorbing, fissile fuel, includes Hafnium sufficient to substantially replace the neutron absorption capacity of the fuel rod. The replacement rod also includes a non-fissile second material that is commonly used for structures in nuclear fuel assemblies. The second material is preferably selected from the group consisting of a stainless steel, a zirconium alloy and zirconium. In one embodiment, the Hafnium is fabricated into a cylindrically-shaped rodlet, or core, and the second material is fabricated into an annulus around the core. Alternatively, the Hafnium and the second material are each distributed about uniformly throughout a cylindrical volume of the replacement rod. Refurbishing nuclear fuel assemblies by replacing damaged fuel rods with replacement rods according to the invention obtains an improved peaking factor over prior art methods.

Abstract: Method of fabricating a multi-ply carbon fibre fabric, preform or composite material from a layer of unidirectionally aligned carbon fibres of ultra-high modulus and a layer of low modulus carbon fibre comprising the steps of: arranging in superimposed relationship the layer of unidirectionally aligned carbon fibres of ultra-high modulus and the layer of low modulus carbon fibres so that at least a substantial number of the fibres of low modulus are disposed transversely of the fibres of the ultra-high modulus fibre layer, and connecting the two layers by interlacing fibres of the layer of low modulus fibres with those of the layer of ultra-high modulus fibres by needle-punching using felting needles orientated and configured so that their barbs snag only the low modulus fibres during passage through the layers.

Abstract: A neutron absorbing apparatus which includes two adjacent neutron absorbing plates and a mounting assembly with latching means configured to be easily secured to fuel assemblies while the fuel assemblies remain under water in a fuel storage rack, thereby eliminating the need to remove the fuel assemblies or the fuel storage rack for installation. The two neutron absorbing plates are positioned orthogonally to form a chevron cross section which can be placed about the fuel assemblies by insertion in the existing space between the fuel assemblies and the cell walls of a fuel storage rack. A prescribed orientation of the chevron configured neutron absorbing plate in the cells of the fuel storage rack together with the selected use of a single neutron absorbing plate economically provides sufficient neutron absorption in all radial directions about the fuel assemblies to maintain safe storage conditions in closely packed fuel storage racks.

Abstract: During operation of a light water moderated and cooled nuclear reactor, rods varying the neutron energy spectrum are introduced into the core of the reactor in the course of a first phase of the cycle in order to reduce the ratio of the volume of moderator to the volume of fissile material in the core. In a second phase of the cycle the spectrum displacement rods are extracted. The rods are of a mixture of thorium energy neutrons. The rods may be of fertile material and--depleted uranium. The invention is of particular interest in PWRs.

Abstract: A nuclear reactor having structural members made of austenitic stainless steel which is corrosion-resistant in an environment of neutron irradiation, and can suppress stress corrosion cracking and embrittlement. At least one additive selected from the group consisting of Ti more than 0.2% by weight but not more than 0.6%, Zr more than 0.2% but not more than 1.14%, Hf more than 0.2% but not more than 2.24%, V more than 0.2% but not more than 0.64%, Nb more than 0.5% but not more than 1.17% and Ta more than 0.5% but not more than 2.27% is added to austenitic stainless steel containing Cr, Ni and so on, and said at least one exists in a solid-solution state. In addition, the steel has a wholly austenitic structure substantially free of carbide. In order to maintain the irradiation-induced segregation prevention effected by the addition element, the C content is limited to 0.01 to 0.008%, and the N content is limited to 0.001 to 0.0%.

Abstract: In a field of commercial nuclear reactors, a control blade, which is inserted into and withdrawn from the core of a nuclear reactor so as to start/shut-down the operation thereof and to control the reactor power, must have soundness, high reactivity and long life. The control blade for nuclear reactors is arranged to prevent swelling of a neutron absorber so as to improve the soundness. Furthermore, even if the swelling takes place, the soundness of the control blade can be maintained. The control blade is arranged to prevent the swelling phenomenon in such a manner that boron exhibiting excellent neutron absorbing performance absorbs hydrogen which is produced as a result of reactions with the neutrons. The control blade for nuclear reactors has an upper structure member, a lower structure member, a central tie member disposed between the upper and lower structure members, a plurality of wings connected to each other by the central tie member, and neutron absorber enclosed in the wing.

Abstract: A zirconium alloy absorber material is described which can be used in structural components in light water nuclear reactors. The zirconium alloy absorber material includes a zirconium alloy material, such as Zircaloy-2 or Zircaloy-4, which has been modified by the addition of isotopically pure erbium-167 in an amount ranging from about 0.1 to about 0.4 wt. %, and preferably about 0.2 wt. %.

Abstract: A burnable-absorber-containing zirconium alloy is described for application to the inside surface of cladding tubes for light water nuclear reactors. The alloy comprises naturally occurring erbium in a range from a measurable amount up to about 20 wt. % or isotopically purified erbium-167 in a range from a measurable amount up to about 5 wt. %; tin in a range from a measurable amount up to about 0.5 wt. %; iron in a range from a measurable amount up to about 0.2 wt. %; chromium in a range from a measurable amount up to about 0.1 wt. %; niobium in a range from a measurable amount up to about 0.1 wt. %; silicon in a range from about 50 to about 120 parts per million ("ppm"); oxygen in a range from a measurable amount up to about 800 ppm; and the balance zirconium. Such an alloy provides an effective absorber material for reactor control, while providing adequate mechanical properties and corrosion resistance for the intended application.

Abstract: By using AVLIS or other methods capable of providing a depleted isotopic mixture, troublesome isotopes such as Gd.sup.154, Gd.sup.156 and Er.sup.166 are selectively removed from naturally occurring isotopic mixtures, while avoiding the additional costs associated with complete fractionation of the mixture. Such mixtures can be used to provide a burnable nuclear fuel absorber having a selectively depleted isotope or isotopes. In particular, the invention concerns burnable absorbers containing erbium with a depleted 166 isotope, gadolinium with a depleted 156 isotope or with depleted 154 and 156 isotopes, and methods for making such absorbers.

Abstract: The invention relates to a process for the production of a neutron absorbing pellet for use in a nuclear reactor control device, comprising the following stages:a) compactable products are prepared incorporating as % by weight electrolytic crystals or chips of Hf and optionally boron carbide powder with a total weight (HF+B.sub.4 C) of 40 to 100%, the Hf:(Hf+B.sub.4 C) ratio being 0.20 to 1 and optionally other metallic elements melting at above 400.degree. C.;b) these products are mixed and compressed in a mould in one or more filling and compression operations until a pellet is obtained with an apparent density higher than 80% of its average density in the solid state;c) a sintering treatment is optionally carried out on said pellet;d) the pellet is or has been extracted from the mould;e) the pellet is optionally ground.

Abstract: A method for coating a nuclear fuel pellet is provided in which a liquid sol is formed containing the makings of a rare earth metal oxide. The liquid sol is applied to the exterior surface of the nuclear fuel pellet and the pellet is baked to form a solid coated pellet. If desired, zirconium diboride may be dispersed within the rare earth metal oxide matrix. Preferably, the rare earth metal oxide is either erbium oxide or gadolinia.

Abstract: Neutron absorbing refractory B.sub.4 C--Gd and Gd.sub.2 O.sub.3 --Gd cermets, B.sub.4 C--Gd and Gd.sub.2 O.sub.3 --Gd metal-matrix composites, and B.sub.4 C--Gd.sub.2 O.sub.3 ceramic-ceramic composites can be manufactured by applying fundamental thermodynamic and kinetic guidelines as processing principals.Three steps are involved in the fabrication of these new compositions of matter. First, the starting materials are consolidated into a compacted porous green body. Next, the green body is densified using the appropriate method depending on the class of material sought: cermet, metal-matrix composite, or ceramic-ceramic composite. Finally, either during the densification process or by subsequent heat treatment, new phase evolution is obtained via interfacial chemical reactions occurring in the microstructures.The existence of a new phase has been identified in B.sub.4 C--Gd and B.sub.4 C--Gd.sub.2 O.sub.3 composites.

Abstract: A method and apparatus for improving the performance of a thermal breeder reactor having regions of higher than average moderator concentration are disclosed. The fuel modules of the reactor core contain at least two different types of fuel elements, a high enrichment fuel element and a low enrichment fuel element. The two types of fuel elements are arranged in the fuel module with the low enrichment fuel elements located between the high moderator regions and the high enrichment fuel elements. Preferably, shim rods made of a fertile material are provided in selective regions for controlling the reactivity of the reactor by movement of the shim rods into and out of the reactor core. The moderation of neutrons adjacent the high enrichment fuel elements is preferably minimized as by reducing the spacing of the high enrichment fuel elements and/or using a moderator having a reduced moderating effect.

Abstract: The subject of the invention is a method of making a clad metal, neutron absorbing element, and the neutron absorbing element produced by preparing compactable metal products comprising (weight %) HF at least 25%, Zr and/or Zr alloys=0 to 75%; Ti and/or Ti alloys=0 to 75%; Hf-ZR alloys containing <55% Zr=0 to 75%; Hf-Ti alloys containing <55% Ti=0 to 75%; neutron absorbing metal elements melting at over 400.degree. C.: <0.2% and other metal elements melting at over 400.degree. C.: 0 to the balance, the balance being less than 5%; introducing at least some of these products into a metal container with an open end; compressing the products in the container, or compressing them before putting them into the container; if necessary repeating the introduction and compression of the products until the container is at least 95% full; and closing the open end of the container by welding on a metal lid or plug and providing an internal vacuum. The element is used, e.g.

Abstract: An austenitic steel excellent in resistance to neutron irradiation embrittlement which contains, by weight, not more than 0.03% carbon, not more than 1% silicon, 5 to 25% manganese, 15 to 26% chromium, and 10 to 20% nickel, the ratio of atomic volume of chromium to the average atomic volume of matrix of the steel being from 0.900 to 1.030. It is possible to add to the austenitic steel, besides the above-mentioned alloying elements, at least one element selected from the group consisting of niobium, titanium, zirconium, tantalum and vanadium which are effective in corrosion resistance and irradiation embrittlement under neutron irradiation in total amounts of not more than 1.0%. At least one of components composing the inside of a nuclear reactor or nuclear fusion reactor is made of the austenitic steel.

Abstract: A nuclear reactor core has a first group of fuel rods containing fissionable material and no burnable absorber, and a second group of fuel rods containing fissionable material and two burnable absorber materials. The groups of fuel rods are arranged in the core for controlling power peaking and moderator temperature coefficient. The number of fuel rods in the first group are greater than the number in the second group. The two burnable absorber materials can be provided as separate coatings or a mixture. One burnable absorber material is an erbium-bearing material such as erbium oxide and the other is a boron-bearing material such as zirconium diboride. Alternatively, the erbium-bearing material can be interspersed or mixed with the fissionable material.

Abstract: A control blade for a nuclear reactor having inserted upper end structural members and inserted lower end structural members connected to a plurality of wings each in the form of a generally rectangular plate having an longitudinal axis extending in the longitudinal direction of the control blade, the wing being disposed to form a cross-shaped section of the control blade. The wings and the structural members are connected to and supported on a central connection member. Each wing or a sheath member formed within each wing is formed from a diluted alloy obtained by diluting a long-lived neutron absorber such as hafnium with a diluent such as zirconium or titanium. A plurality of neutron absorber housing holes are formed in the diluted alloy section.

Abstract: A lanthanide oxide selected from the group consisting of dysprosium oxide, erbium oxide, europium oxide, gadolium oxide and samarium oxide is formed into a compact and sintered to produce a body useful as a control rod material in a water cooled nuclear reactor. The lanthanide oxide is preferably combined with a corrosion stabilizing group 4A metal oxide such as hafnium oxide.

Abstract: A workable, boron-containing, stainless steel alloy and an article formed therefrom are disclosed together with a process for manufacturing same. The alloy consists essentially of, in weight percent, about______________________________________ w/o ______________________________________ Carbon 0.10 max. Manganese 2.00 max. Silicon 1.00 max. Phosphorus 0.045 max. Sulfur 0.010 max. Chromium 16.00-22.00 Nickel 10.00-15.00 Molybdenum 0-3.0 Boron 0.2-2.0 Nitrogen 0.075 max. ______________________________________and the balance consisting essentially of iron. The as-worked alloy in accordance with the invention is characterized by having a boride particle areal density per weight percent boron (A.sub.N) defined by the relationshipA.sub.N .gtoreq.58,080-18,130 (%B).The as-worked alloy of the invention is further characterized by having a Charpy V-notch impact strength (CVN) defined by the relationshipCVN.gtoreq.85.917 x e.sup.-1.20297(%B).

Abstract: A neutron reactivity control system for a LWBR incorporating a stationary seed-blanket core arrangement. The core arrangement includes a plurality of contiguous hexagonal shaped regions. Each region has a central and a peripheral blanket area juxapositioned an annular seed area. The blanket areas contain thoria fuel rods while the annular seed area includes seed fuel rods and movable thoria shim control rods.

Abstract: A radiation shielding material for intercepting not only .gamma. rays and x rays but also neutrons, comprising sulfur, iron oxide powder, lead oxide powder, gadolinium oxide powder and hydrogen-occluding alloy powder; and a process for preparing the radiation shielding material.

Abstract: A mechanical spectral shift reactor comprises apparatus for inserting and withdrawing water displacer elements having differing neutron absorbing capabilities for selectively changing the water-moderator volume in the core thereby changing the reactivity of the core. The displacer elements may comprise substantially hollow cylindrical low neutron absorbing rods and substantially hollow cylindrical thick walled stainless rods. Since the stainless steel displacer rod have greater neutron absorbing capability, they can effect greater reactivity change per rod. However, by arranging fewer stainless steel displacer rods in a cluster, the reactivity worth of the stainless steel displacer rod cluster can be less than a low neutron absorbing displacer rod cluster.

Abstract: Annular pellets of burnable poison specifically boron carbide, B.sub.4 C, in a matrix of a refractory material, specifically aluminum oxide, Al.sub.2 O.sub.3, are produced. The pellets are of small wall thickness. Powders of the Al.sub.2 O.sub.3 and the B.sub.4 C are milled in a ball mill in water in which a wetting agent, a surfactant and a deflocculant are included to produce a slurry. Organic binders and plasticizers are added. Then the slurry is spray dried in a centrifugal separator. The resulting powder is poured into a mold and a turbular green body is formed by isostatic pressure. The tube may be sintered to size as a whole and then cut into lengths; i.e., pellets, or the green body may be cut into green-body pellets which are then sintered.

Abstract: A nuclear fuel assembly comprising a plurality of fuel rods, each fuel rod comprising a cladding tube closed at both ends and filled with cylindrical nuclear fuel pellets such as sintered uranium dioxide or uranium plutonium dioxide. All or nearly all of the cylindrical pellets are coated with a refractory boride coating of sufficient thickness to prevent mechanical interaction between the pellets and the tube. The isotopic composition of the boron in the refractory boride is adjusted for each batch of fuel pellets, rods, or assemblage of rods so that the initial excess reactivity, k, of the batch, when assembled in a reactor core, is nearly zero.