Abstract: A customizable thin plate fuel form and reactor core therefor are disclosed. The thin plate fuel will comprise a fuel material embedded within a matrix material, with the entire unit having a coating. The thin plate fuel may be flat or curved and will have flow channels formed within at least the top surface of the fuel plate. The structure of the thin plate fuel will make it easier for coating with Tungsten or any other suitable material that will help contain any byproducts, prevent reactions with the working fluid, and potentially provide structural support to the thin plate fuel.

Abstract: A nuclear reactor core comprising fissile material is surrounded by a core former. The core former comprises one or more single-piece annular rings wherein each single-piece annular ring comprises neutron-reflecting material. In some embodiments the core former comprises a stack of two or more such single-piece annular rings. In some embodiments the stack of single-piece annular rings is self-supporting. In some embodiments the stack of single-piece annular rings does not include welds or fasteners securing adjacent single-piece annular rings together. A core basket may contain the nuclear reactor core and the core former, and in some embodiments an annular gap is defined between the core former and the core basket. In some embodiments the core former does not include welds and does not include fasteners.

Abstract: Embodiments are directed to providing a user interface (UI) that streamlines and simplifies the process of monitoring critical power-generation module (PGM) parameters after a PGM assembly is shutdown. The UI displays, in real-time, indicators corresponding to one or more post-shutdown PGM parameters. The UI provides indications of whether the post-shutdown PGM parameters meet post-shutdown criteria of the PGM assembly. When a post-shutdown PGM parameter does not meet the post-shutdown criteria, a user alert is provided to the user. A protocol may additionally be provided to the user. In some embodiments, the protocol may enable the user to return the PGM assembly to a condition that satisfies the post-shutdown criteria. The protocol may be a safety protocol and/or an asset protection protocol.

Abstract: A high-temperature containment-isolation system for transferring heat from a nuclear reactor containment to a high-pressure heat exchanger is presented. The system uses a high-temperature, low-volatility liquid coolant such as a molten salt or a liquid metal, where the coolant flow path provides liquid free surfaces a short distance from the containment penetrations for the reactor hot-leg and the cold-leg, where these liquid free surfaces have a cover gas maintained at a nearly constant pressure and thus prevent high-pressures from being transmitted into the reactor containment, and where the reactor vessel is suspended within a reactor cavity with a plurality of refractory insulator blocks disposed between an actively cooled inner cavity liner and the reactor vessel.

Abstract: Length adjustment can be performed in a simple manner and without impairment of the insulating effect in an insulation cassette for the heat insulation of elongated elements. A multilayer insulation includes flat reflection elements (21, 22). Each layer of the insulation has at least two of the flat reflection elements (21, 22), which overlap at least partly at their ends (24) facing each other.

Abstract: A system includes a containment vessel configured to prohibit a release of a coolant, and a reactor vessel mounted inside the containment vessel. An outer surface of the reactor vessel is exposed to below atmospheric pressure, wherein substantially all gases are evacuated from within the containment vessel.

Abstract: Disclosed herein is a fully passive decay heat removal system utilizing a partially immersed heat exchanger, the system comprising: a hot pool; an intermediate heat exchanger which heat-exchanges with the sodium of the hot pool; a cold pool; a support barrel extending vertically through the boundary between the hot pool and the cold pool; a sodium-sodium decay heat exchanger received in the support barrel; a sodium-air heat exchanger provided at a position higher than the sodium-sodium decay heat exchanger; an intermediate sodium loop connecting the sodium-sodium decay heat exchanger with the sodium-air heat exchanger; and a primary pump, wherein a portion of the effective heat transfer tube of the sodium-sodium decay heat exchanger is immersed in the cold pool, particularly in a normal operating state, and the surface of the lower end of a shroud for the sodium-sodium decay heat exchanger, the lower end being immersed in the sodium of the cold pool, has perforated holes.

Abstract: A system includes a containment vessel configured to prohibit a release of a coolant, and a reactor vessel mounted inside the containment vessel. An outer surface of the reactor vessel is exposed to below atmospheric pressure, wherein substantially all gases are evacuated from within the containment vessel.

Abstract: The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel that has a hemispherical lower section that increases in volume from the center line of the reactor to the outer extent of the diameter of the thermal insulating barrier and smoothly transitions up the side walls of the vessel. The space between the thermal insulating harrier and the reactor vessel forms a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive inlet valve for the cooling water includes a buoyant door that is normally maintained sealed under its own weight and floats open when the cavity is Hooded. Passively opening steam vents are also provided.

Abstract: In a reactor vessel thermal load reducing system near the surface level of a coolant, the present invention is characterized in that a heat conductive member is installed not contacting the reactor vessel wall in an area above and below the coolant liquid surface, and the heat conducting member is attached to a guard vessel, the heat conducting member being made of material of good heat conductivity.

Abstract: Example embodiments provide a Basemat-Internal Melt Arrest and Coolability device (BiMAC) that offers improved spatial and mechanical characteristics for use in damage prevention and risk mitigation in accident scenarios. Example embodiments may include a BiMAC having an inclination of less than 10-degrees from the basemat floor and/or coolant channels of less than 4 inches in diameter, while maintaining minimum safety margins required by the Nuclear Regulatory Commission.

Abstract: A clamp assembly for securing a thermal sleeve and an elbow in a pipe assembly in a nuclear reactor. The clamp assembly comprises a sleeve clamp adapted to be arranged surrounding the elbow at a first joint between the elbow and a thermal sleeve, and comprising a sleeve support adapted to extend across the first joint. The clamp assembly comprises at least one clamp arm with a first end arranged to rest against at least one of a core shroud and a core plate support ring, to provide support for the positioning of the sleeve clamp.

Abstract: An alignment system that employs jacking block assemblies and alignment posts around the periphery of the top plate of a nuclear reactor lower internals core shroud to align an upper core plate with the lower internals and the core shroud with the core barrel. The distal ends of the alignment posts are chamfered and are closely received within notches machined in the upper core plate at spaced locations around the outer circumference of the upper core plate. The jacking block assemblies are used to center the core shroud in the core barrel and the alignment posts assure the proper orientation of the upper core plate. The alignment posts may alternately be formed in the upper core plate and the notches may be formed in top plate.

Abstract: The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel that has a hemispherical lower section that increases in volume from the center line of the reactor to the outer extent of the diameter of tiie thermal insulating barrier and smoothly transitions up the side walls of the vessel. The space between the thermal insulating harrier and the reactor vessel forms a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive inlet valve for the cooling water includes a buoyant door that is normally maintained sealed under its own weight and floats open when the cavity is Hooded. Passively opening steam vents are also provided.

Abstract: A top guide to shroud head interface is described. In one embodiment, the interface includes a top guide that includes a flange that is configured to engage a corresponding flange of the shroud head. The top guide flange includes a plurality of frusto-conical shaped guide pins extending from the top surface of the flange. The shroud head flange includes a plurality of guide pin openings configured to align with the guide pins located on the top guide flange. Each guide pin opening includes a frusto-conical portion that extends through the flange from the bottom surface of the shroud head flange and has a slope equal to the slope of the frusto-conical pins. Each guide pin opening also includes a cylindrical portion that extends from the small base of the frusto-conical portion of the guide pin opening to the top surface of the shroud head flange.

Abstract: A joint for interfacing a steel head closure and a steel-lined prestressed concrete reactor vessel (PCRV). The steel head closure is bolted to a thick steel annular plate and a thermal barrier is arranged in a volume bounded by the head ring, the liner and the concrete of the PCRV wall. The thermal barrier is made of zirconia sand or other material having a low thermal conductivity, a high bulk modulus equal to that of concrete, and a low shear modulus. Differential thermal expansion of the vessel head closure and PCRV is accommodated by a flexible connection of the PCRV liner to the inner periphery of the head ring. In the alternative, the steel head closure is interfaced to the top of the PCRV via a sliding joint or a thermal stress relief ring. In accordance with a further alternative, thermal stresses in the steel vessel head closure are mitigated by reducing the temperature of the head closure by installing thermal insulation on all internal surfaces thereof.

Abstract: The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel to form a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive valving also includes bistable vents at the upper end of the thermal insulating barrier for releasing steam. A removable, modular neutron shield extending around the upper end of the reactor cavity below the nozzles forms with the upwardly and outwardly tapered transition on the outer surface of the reactor vessel, a labyrinthine channel which reduces neutron streaming while providing a passage for the escape of steam during a severe accident, and for the cooling air which is circulated along the reactor cavity walls outside the thermal insulating barrier during normal operation of the reactor.

Abstract: The confining and covering enclosure (10) comprises a heat-insulating wall (13, 14) designed to insulate thermally the outer surface (2a) of the vessel head (2). The heat-insulating wall (13, 14) is leaktight to the fluid coming from the vessel of the reactor in the case of leakage and comprises leaktight connection seals (15, 27) at the outer surface (2a) of the head and at the adaptors (6) serving to delimit a chamber (30) for confinement and for recovery of leakage gases.

Abstract: A superconductive apparatus having therein at least a superconductive member includes a lithium containing member so as to interrupt neutrons directed to the superconductive member.

Abstract: A nuclear reactor installation includes a reactor pressure vessel and a reactor core in the reactor pressure vessel. A supporting and protective structure supporting the reactor pressure vessel and surrounding the reactor pressure vessel on the bottom and laterally, has a bottom region and a circumferential wall. A core catcher device for the reactor core has a collecting basin for a core melt being installed below the reactor pressure vessel. The collecting basin has a bottom wall and a jacket wall being respectively separated from the bottom region and the circumferential wall of the supporting and protective structure by a spacing gap. Cooling channels are disposed in the spacing gap at the bottom wall and the jacket wall for exterior cooling of the collecting basin with a cooling liquid. Turbulence bodies are disposed in a surface region of the bottom wall for generating a turbulent flow of the cooling liquid flowing from the inside to the outside over the bottom wall toward the jacket wall.

Abstract: A nuclear reactor is provided having a generally cylindrical reactor vessel disposed within an opening in a primary shield. The opening in the primary shield is defined by a plurality of generally planar side walls forming a generally polyhedral-shaped opening. The reactor vessel is supported within the opening in the primary shield by reactor vessel supports which are in communication and aligned with central portions of some of the side walls. The reactor vessel is connected to the central portions of the reactor vessel supports. A thermal insulation polyhedron formed from a plurality of slidably insertable and removable generally planar insulation panels substantially surrounds at least a portion of the reactor vessel and is disposed between the reactor vessel and the side walls of the primary shield. The shape of the insulation polyhedron generally corresponds to the shape of the opening in the primary shield.

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: An improvement is set forth in a thermionic fuel element which includes a collector base supporting a collector adjacent and closely spaced from an emitter which is supported by an emitter base, the emitter base being adapted to be heated by a heat source. In accordance with the invention a thermal shield structure is located between a portion of the emitter and the collector. The shield structure insulates that portion of the collector opposite the shield structure from receiving at least a portion of the radiation developed by the heat source.

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: An insulation system including support for lagging, especially metal lagging, supports lagging at a distance above industrial piping and prevents fibrous insulation, used to insulate the piping, from being compressed and eventually significantly damaged by foot traffic, thus creating a treadable insulation system with valuable application in nuclear reactor containment areas.

Abstract: A liquid metal nuclear reactor has a sodium tank, having a closed arcuate bottom and upstanding cylindrical wall for containing a reactor core in a pool of liquid metal coolant, which is disposed in a guard tank having a bottom and upwardly extending cylindrical shell, and a support inside the guard tank adjacent the closed bottom of the sodium tank to support the two tanks in spaced relationship to each other. The sodium tank has an open top spaced from an overlying closure deck, with the cylindrical shell of the guard tank secured to the closure deck. The support is preferably an inner ledge. Support legs are also provided about the bottom periphery of the guard tank adapted to rest on a base mat of a reactor cavity.

Abstract: A nuclear power plant with a gas cooled high temperature reactor, installed in a prestressed concrete pressure vessel with the operational and decay heat removal systems. The prestressed concrete pressure vessel has a thermal protection system, with a thermal insulating layer and a liner cooling system. The liner cooling system, which is includes water carrying cooling pipes, which along with intermediate heat exchangers and cooling water pumps make up a closed intermediate cooling loop used for removal of the decay heat in case a failure of the decay heat removal systems. The elements of the invention assure an adequate water flow for the removal of decay heat in the liner cooling system in any situation, i.e. such that the decay heat may also be removed by natural convection. These element insure a sufficient driving pressure differences and minimize pressure losses in the intermediate cooling loop.

Abstract: A nuclear reactor having a remotely removable and replaceable thermal insulating shield for the head. Access permitting removal and replacement of the head is thus afforded.The thermal insulating shield includes a vertical frame of insulating material of polygonal transverse cross section encircling the head. A top panel of insulating material is mounted on the top of the frame pivotal by remote actuation between a horizontal position and a retracted position which may be vertical. In the horizontal position, the panels mate to provide thermal shielding for the head.

Abstract: A thermal barrier for use in a nuclear reactor facility is disclosed herein. Generally, the thermal barrier comprises a flexible, heat-resistant web mounted over the annular space between the reactor vessel and the guard vessel in order to prevent convection currents generated in the nitrogen atmosphere in this space from entering the relatively cooler atmosphere of the reactor cavity which surrounds these vessels. Preferably, the flexible web includes a blanket of heat-insulating material formed from fibers of a refractory material, such as alumina and silica, sandwiched between a heat-resistant, metallic cloth made from stainless steel wire. In use, the web is mounted between the upper edges of the guard vessel and the flange of a sealing ring which surrounds the reactor vessel with a sufficient enough slack to avoid being pulled taut as a result of thermal differential expansion between the two vessels.

Abstract: Modular ultrafiltration device for the cooling liquid of a nuclear reactor, comprising a radiation absorbing containment (1), an ultrafilter (15) arranged in the containment (1), a heat exchanger (32) placed in the containment (1), and connection pieces intended for the various parts of the ultrafilter (15) and heat exchanger (32) and passing through the wall of the containment (1) in a leak-proof manner. A heat-insulating material (41) fills the inner volume of the containment (1). The modular device can easily be connected to an auxiliary circuit of the nuclear reactor. The ultrafiltration wall can be replaced without any difficulty.

Abstract: A nuclear component horizontal seismic restraint. Small gaps limit horizontal displacement of components during a seismic occurrence and therefore reduce dynamic loadings on the free lower end. The reactor vessel and reactor guard vessel use thicker section roll-forged rings welded between the vessel straight shell sections and the bottom hemispherical head sections. The inside of the reactor guard vessel ring forging contains local vertical dovetail slots and upper ledge pockets to mount and retain field fitted and installed blocks. As an option, the horizontal displacement of the reactor vessel core support cone can be limited by including shop fitted/installed local blocks in opposing alignment with the reactor vessel forged ring.

Abstract: A control unit for a nuclear reactor constituted by a plurality of sealed vessels (17) communicating with the inside of the tank of the reactor (15) which they extend upwards above its cover (16); each containing a displacement mechanism for a unit absorbing neutrons in the core of the reactor. The drive motors (18) for the mechanisms are positioned in the upper part of the sealed vessels (17) within vertical aeration ducts (32). The control unit includes a supporting and insulating device for the sealed vessels (17) constituted by a vertical structure (23) fast to the cover of the tank (16), a horizontal strengthening plate (27) fixed to the upper part of the vertical structure (23) and a heat-insulating envelope (36) surrounding the sealed vessels (17) to a level below the level of the motors (18). The invention is particularly applicable to pressurized water nuclear reactors equipped with screw and nut mechanisms.

Abstract: A pressurized nuclear water reactor has a substantially cylindrical flow liner with a cylindrical wall section and bottom and an open top. A barrel forms a riser chamber that contains the core in the flow liner. A pressure vessel contains the cylindrical flow liner to form a second annular chamber therebetween that contains a supplementary liquid coolant, with insulation means to provide a major portion of the supplementary liquid coolant at a first temperature and a minor portion thereof at a second higher temperature. Upon depressurization in the vessel, fluid communication means enable injection of supplementary liquid coolant from the second annular chamber into the core upon flashing of a minor portion to vapor. A further pool of water outside the pressure vessel, and insulation on the wall, maintain the desired temperature in the supplementary liquid coolant supply. Injection or removal of borated solution, as a chemistry control solution, into or from the supplementary liquid coolant is provided.

Abstract: A thermal insulating blanket used for insulating pipes and equipment in nuclear power plant containment buildings is resistant to tearing if impinged upon by a high force liquid stream (i.e., during a loss of coolant accident--LOCA) and if torn is cut into small pieces which will not clog the protective screen of the emergency cooling system recirculating sump. The blanket consists of a filler layer of thermal insulating fibers, such as glass fiber wool or ceramic fiber wool, a waterproof sheet, and a wire mesh casing surrounding the filler layer and sheet. The wire casing dissipates the force of high force liquid streams which may strike the blanket during a LOCA and in the event that the filler layer is torn, the filler layer is cut into small pieces as it passes through the casing. Preferably, a wire mesh spetum lies within the filler layer to assist in cutting up the torn filler layer.

Abstract: A thermal barrier/core support for the fuel core of a nuclear reactor having a metallic cylinder secured to the reactor vessel liner and surrounded by fibrous insulation material. A top cap is secured to the upper end of the metallic cylinder that locates and orients a cover block and post seat. Under normal operating conditions, the metallic cylinder supports the entire load exerted by its associated fuel core post. Disposed within the metallic cylinder is a column of ceramic material, the height of which is less than that of the metallic cylinder, and thus is not normally load bearing. In the event of a temperature excursion beyond the design limits of the metallic cylinder and resulting in deformation of the cylinder, the ceramic column will abut the top cap to support the fuel core post.

Abstract: A reflective type insulation is utilized to elevate the temperature in the loop seal of a pressurizer. Damage to safety valve components and downstream piping caused by water in the piping is substantially reduced by exposing the loop seal piping to a portion of the outer surface of the pressurizer. Safety valve allowable sustained operating temperature requirements are considered in the insulation system design.

Abstract: The invention relates to a nuclear reactor cooled by a liquid metal comprising a vessel (12) containing the reactor core (24), a vessel shaft (18) and a sealing slab (14).The bottom (12a) of the vessel rests on the bottom (52) of the vessel shaft via supports (54) defining between the said two bottoms a space (56) in which circulates a cooling fluid such as air. A skirt (74) surrounds vessel (12) and rests on the vessel shaft bottom (52) for supporting slab (14).Application to the construction of simpler and less expensive fast neutron reactors than those hitherto known.

Abstract: In a liquid metal cooled nuclear reactor with a nuclear fuel assembly in a coolant-containing primary vessel housed within a concrete containment vault, there is thermal insulation to protect the concrete, the insulation being disposed between vessel and concrete and being hung from metal structure secured to and projecting from the concrete, the insulation consisting of a plurality of adjoining units each unit incorporating a pack of thermal insulating material and defining a contained void co-extensive with said pack and situated between pack and concrete, the void of each unit being connected to the voids of adjoining units so as to form continuous ducting for a fluid coolant.

Abstract: The combination in a nuclear reactor of a concrete containment and thermal insulation for the roof of the containment, the thermal insulation being secured to the roof by hangers each of which has a linkage connector at its upper end by means of which it is secured to the roof, the linkage connector permitting movement of the hanger in two dimensions, and means at the lower end of each hanger serving to support the thermal insulation from beneath and permitting lateral movement of the insulation in two dimensions.

Abstract: A nuclear reactor having a remotely removeable and replaceable thermal and/or radiation insulating shield for the head. This shield is formed of interlocked integrated shielding units of thermal insulating material. Each unit has a vertical member and a horizontal member. Each unit has a lifting-and-lowering rod on its top and it may be raised vertically by a remotely operable clamp engaging the head. The interlocking surfaces of adjacent units are so formed that when any unit is raised or lowered vertically its interlocking surface readily slides along the interlocking surfaces of the units adjacent to it with which it is interlocked.

Abstract: A support structure for a nuclear reactor is disclosed comprising a primary support element connected with the roof of the pressure vessel and a secondary support element joined with the primary support element. The thermal roof shield and the roof reflector are connected to the secondary support element.

Abstract: A pressurized water nuclear reactor comprises a reactor vessel arranged in a pool made in the form of a pressure vessel, the pool being filled with a strongly neutron-absorbing liquid, for example borated water. The reactor vessel, in addition to being connected to a primary system, is provided with a lower shutdown opening, arranged below the reactor core, for pool liquid and with an upper shutdown opening, arranged above the core, for pool liquid.

Abstract: A gas cooled, high temperature nuclear reactor is provided with a base plate arranged under the reactor core and over the bottom of the prestressed concrete pressure vessel serving as the bottom shield. The bottom shield comprises at least two plates arranged coaxially with respect to each other, one above the other. Each plate comprises several partially interconnected parts with the lower plate being placed at an axial and vertical distance from the bottom liner of the prestressed concrete pressure vessel and also from the upper plate.

Abstract: Heat insulation for domeshaped bottom and/or cover regions of a pressure vessel, the heat insulation being penetrated by a multiplicity of pressure vessel unions extending parallel to the axis of the pressure vessel, including an integral dome formed of heat insulation having a passage formed therein for each of the pressure vessel unions, guide elements extending parallel to the axis of the pressure vessel for centering the heat-insulation dome with respect to the pressure vessel and for axially movably mounting the heat-insulation dome so that it can be lowered from a largely convection-proof operating position thereof to a storage position thereof onto an assembly platform, whereby the union passages of the pressure vessel are exposed for in-service testing, and can be raised back to the operating position thereof.

Abstract: A nuclear power plant with a metallic, circulatory cooling loop formed with welding seams and including, as components thereof, a reactor pressure vessel, a heat consumer and a pump, as well as a coolant line connecting the components to one another, and thermal insulation provided on the cooling loop, the welding seams being testable by a track-traversing testing device, including a multiplicity of fixedly installed tracks having like profile and being associated, respectively, with welding seams on the components and the cooling line, at least part of the thermal insulation being in vicinity of the tracks and being formed as removable cassettes.

Abstract: An apparatus for thermally insulating nuclear reactor primary vessels. The apparatus includes a plurality of cylindrical reflective metal plates located within the primary vessel for thermally insulating the side walls of the vessel from the temperatures generated by the reactor. The reflective plates are radially spaced apart and are positioned in an annular inverted U-shaped chamber that traps inert gas around the reflective plates. The plates and the annular chamber insulate the side walls of the primary vessel from the temperatures generated by the reactor.

Abstract: A neutron protection thermal insulating material is obtained by adding a boron compound and, if necessary, a hydrous compound, to chrysotile asbestos fibers. To form the material, the asbestos is opened with the use of a surface active agent in the presence of water. The boron compound is added and air bubbles are incorporated into the mixture which is then dried, molded and compressed. The resulting product is characterized by a construction wherein the opened asbestos fibers are oriented in substantially parallel relation to each other and in the direction perpendicular to the compression direction and air pockets are flatly arranged between the fibers and substantially parallel thereto to reduce thermal conduction through the material in the direction parallel to the direction of compression.

Abstract: Improved thermal insulation for a nuclear reactor deck comprising many helical coil springs disposed in generally parallel, side-by-side laterally overlapping or interfitted relationship to one another so as to define a three-dimensional composite having both metal and voids between the metal, and enclosure means for holding the composite to the underside of the deck.