Patent Number: 042749204
Section: claims

1. A water-cooled nuclear reactor which operates at an elevated temperature and pressure during normal operation having passive emergency shutdown and core cooling capability, comprising: a reactor core comprising a plurality of columnar arrangements of nuclear fuel elements disposed during normal operation within a pressure vessel in a chain reacting relationship, said pressure vessel containing at least sufficient energy to disperse the bulk of the core fuel content by driving it from the core;  a plurality of hollow fuel dispersal guide conduits penetrating said pressure vessel at locations beneath said columnar arrangements and generally aligned therewith, said dispersal guide conduits being generally divergent at least along portions of their length substantially immediately beneath said pressure vessel for receiving nuclear fuel elements therefrom in the event of emergency shutdown and for guiding and dispersing said fuel elements whereby said fuel elements become spaced sufficiently to assume a non-critical dispersed configuration;  an external heat sink of capacity adequate to absorb the residual heat contained in the reactor core and spontaneously generated by said nuclear fuel elements after shutdown, said heat sink being disposed beneath said reactor core so that gravitational attraction aids in driving said nuclear fuel elements along said dispersal guide conduits into said dispersed configuration for cooling said nuclear fuel elements in the event of emergency shutdown; means positioned in series with each guide conduit for communicating said conduit with said pressure vessel for initiating transfer of fuel elements from said pressure vessel into said associated dispersal guide conduit in the event of emergency shutdown; and  means positioned in series with each guide conduit and adjacent said heat sink for permitting selective withdrawal of fuel elements from, and/or loading fuel elements into, said associated conduit.  a reactor core comprising a plurality of columnar arrangements of nuclear fuel elements disposed during normal operation within a pressure vessel in a chain reacting relationship, said pressure vessel containing at least sufficient energy to disperse the bulk of the core fuel content by driving it from the core;  a plurality of hollow fuel dispersal guide conduits configured to diverge to a non-critical dispersed configuration penentrating said pressure vessel at locations beneath said columnar arrangements and generally aligned with said arrangements for receiving nuclear fuel elements therefrom in the event of emergency shutdown and for guiding and dispersing said fuel elements whereby said fuel elements become spaced sufficiently to assume a non-critical configuration.  an external heat sink in the form of a body of water of capacity adequate to absorb the residual heat contained in the reactor core and spontaneously generated by said nuclear fuel elements after shutdown, said heat sink being disposed beneath said reactor core so that gravitational attraction aids in driving said nuclear fuel elements along said dispersal guide conduits into said dispersed configuration, and for cooling said nuclear fuel elements by conduction and convection in the event of emergency shutdown;  means positioned in series with each guide conduit between said pressure vessel and said heat sink communicating the conduit with said pressure vessel for initiating transfer of fuel elements from said reactor vessel into said associated dispersal guide conduit in the event of emergency shutdown; and  means positioned in series with each guide conduit and positioned beneath said heat sink in a reactor refueling station for permitting selective withdrawal of fuel elements from, and/or loading fuel elements into, said associated conduits.  a reactor core comprising a plurality of columnar arrangements of nuclear fuel elements disposed during normal operation within a pressure vessel in a chain reacting relationship, said pressure vessel containing at least sufficient energy to disperse the bulk of the core fuel content by driving it from the core;  a plurality of generally divergent hollow fuel dispersal guide thimbles in the form of hollow tubular members penetrating said pressure vessel at locations beneath said columnar arrangements and generally aligned with said arrangements for receiving nuclear fuel elements therefrom in the event of emergency shutdown and for guiding and dispersing said fuel elements whereby said fuel elements become spaced sufficiently to assume a non-critical configuration;  an external heat sink of capacity adequate to absorb the residual heat contained in the reactor core and spontaneously generated by said nuclear fuel elements after shutdown, said heat sink being disposed sufficiently adjacent said reactor core to permit the energy contained in said vessel to drive said fuel elements along said dispersal guide thimbles into a non-critical dispersed configuration and to cool said fuel elements by conduction and convection by said heat sink;  means positioned in series with each guide thimble on a first side of said heat sink between said pressure vessel and said heat sink for communicating the thimble said pressure vessel for initiating transfer of fuel elements from said pressure vessel into said associated dispersal guide thimbles in the event of emergency shutdown; and  means positioned in series with each guide thimble on a second side of said heat sink distant from said pressure vessel for selectively withdrawing fuel elements from and/or loading fuel elements into said associated thimble. 2. A reactor according to claim 1 wherein said heat sink comprises a body of water accommodated within the seismic support region of the reactor, and emergency gating means are provided for permitting gravitational replenishment of evaporated water while preventing the flow of said water out of the heat sink in the event of fuel dispersal guide rupture. 3. A nuclear reactor according to claim 1 including guide means within said pressure vessel for constraining the fuel elements comprising said columnar arrangements in alignment with said fuel dispersal guide conduits while permitting upward and downward slidable movement thereof along said guide means and into or out of said dispersal conduits. 4. A nuclear reactor according to claim 1 further comprising longitudinally straight-edged guide means radially positioned around each of said columnar arrangements for constraining the fuel elements of said arrangements in alignment with said fuel dispersal guide conduits while permitting upward and downward slidable movement along said straight edged guide means and into or out of said dispersal guide conduits. 5. A nuclear reactor according to claim 1 wherein a plurality of fuel elements comprising a plurality of columnar arrangements, each has a generally longitudinally extending hollow interior portion and is disposed in said reactor core on a guide member inserted into said hollow interior portion for constraining said fuel elements in alignment with said fuel dispersal guide conduits while allowing upward and downward slidable movement thereof along said guide member and into or out of said dispersal guide conduits. 6. A nuclear reactor according to claim 5 wherein a pluraltiy of said columnar arrangements comprises one or more hollow dummy elements positioned at the levels of one or more respective core support frames for limiting horizontal movement and vibration of said columnar arrangement. 7. A nuclear reactor according to claim 5 wherein the uppermost element of said columnar arrangement comprises a hollow dummy spacer with an enlarged funnel-shaped receptacle for facilitating engagement with said guide member during fuel loading. 8. A nuclear reactor according to claim 1 wherein the portion of the reactor beneath said columnar arrangement is provided with a surface shaped to funnel molten material from said columnar arrangement into said dispersal guide conduits. 9. A nuclear reactor according to claim 1 wherein said means for initiating transfer of said fuel elements from said core into each dispersal guide conduit comprise a piston member positioned within, and slidable along, the hollow interior of said conduit and held in position at the pressure vessel by pressurized fluid for supporting said fuel elements during normal operation of the reactor. 10. A nuclear reactor according to claim 9 wherein said pressurized fluid used to hold said piston in position is comprised of reactor coolant quality water. 11. A nuclear reactor according to claim 9 wherein said piston member comprises sealing means for sealing said fuel dispersal guide conduit from said reactor pressure vessel during normal core operation. 12. A nuclear reactor according to claim 9 wherein said guide conduits comprise sealing shoulders for receiving said piston in sealing engagement while said piston member is held in position for supporting said fuel elements during normal core operation. 13. A nuclear reactor according to claim 1 wherein a plurality of said fuel elements comprise clad fuel elements of nuclear fuel having a maximum longitudinal dimension not exceeding about three times the maximum transverse dimension in order to facilitate entry into said fuel dispersal guide conduits. 14. A nuclear reactor according to claim 1 wherein a hollow tubular member of neutron absorbing material is disposed around at least a portion of the emergency dispersal path of said fuel elements. 15. A nuclear reactor according to claim 1 wherein a plurality of said fuel elements having hollow interiors are provided with a plurality of longitudinally extending concave grooves for permitting cladding expansion with minimal reduction of cladding wall thickness upon fuel swelling. 16. A nuclear reactor according to claim 15 wherein a plurality of said fuel elements having hollow interiors are provided with a cladding tightly compressed onto a fuel pellet for facilitating heat transfer from fuel to coolant. 17. A nuclear reactor according to claim 16 wherein a plurality of said fuel elements with compressed cladding are provided with cladding which is of reinforced thickness as compared to the thickness of cladding required to obtain comparable heat transfer in a corresponding, non-compressed structure. 18. A nuclear reactor according to claim 1 wherein a plurality of said fuel elements are provided with a plurality of longitudinally extending concave grooves for permitting cladding expansion with minimal reduction of cladding wall thickness upon fuel swelling. 19. A nuclear reactor according to claim 18 wherein a plurality of said fuel elements are provided with a cladding tightly compressed onto a fuel pellet for facilitating heat transfer from fuel to coolant. 20. A nuclear reactor according to claim 19 wherein a plurality of said fuel elements with compressed cladding are provided with cladding which is of reinforced thickness as compared to the tickness of cladding required to obtain comparable heat transfer in a corresponding, non-compressed structure. 21. A nuclear reactor according to claim 1 wherein a plurality of said fuel elements are assembled into a multi-element cluster. 22. A nuclear reactor according to claim 1 comprising a plurality of normally open isolation valves for permitting fuel discharge into said fuel dispersal guide conduits. 23. A reactor according to claim 1 including a reactor refueling station coupled to said fuel dispersal guide conduits for on-line refueling. 24. A reactor according to claim 1 wherein said means associated with each conduit for communicating said conduit with said pressure vessel for initiating transfer of fuel elements comprises a pressure barrier to provide sealing engagement between said reactor pressure vessel and said dispersal guide conduits during normal reactor operation. 25. A nuclear reactor according to claim 1 wherein a plurality of said columnar arrangements of nuclear fuel elements comprise one or more dummy spaces for supporting said nuclear fuel elements in the operative region of the reactor core. 26. A water-cooled nuclear reactor which operates at an elevated temperature and pressure during normal operation having passive emergency shutdown and core cooling capability, comprising. 27. A nuclear reactor according to claim 26 further comprising a refueling station positioned beneath said heat sink for withdrawal of fuel elements from, and/or loading fuel elements into, said associated conduits. 28. A water-cooled nuclear reactor which operates at an elevated temperature and pressure during normal operation having passive emergency shutdown and core cooling capability, comprising: