Controllable long term operation of a nuclear reactor

Abstract

Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like.

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       29 . A method of modifying a nuclear fission facility, the method comprising:
 providing a first fast neutron spectrum nuclear fission core assembly with a first operational subsystem of a first type;   emplacing a second fast neutron spectrum nuclear fission core assembly with a second operational subsystem of the first type; and   coupling the second operational sub system of the second fast neutron spectrum nuclear fission core assembly to the first operational subsystem.   
   
   
       30 . The method of  claim 29 , wherein the first operational subsystem of a first type is a first cooling system and the second operational subsystem of the first type is a second cooling system. 
   
   
       31 . The method of  claim 30 , wherein coupling the first operational sub system to the second operational sub system includes coupling the first cooling system to the second cooling system without disconnecting the first fast neutron spectrum nuclear fission core assembly from the first cooling system. 
   
   
       32 . The method of  claim 29 , further including configuring a power generation unit to respond to the first cooling system after coupling the second cooling assembly of the second fast neutron spectrum nuclear fission core assembly to the first cooling system. 
   
   
       33 . The method of  claim 32 , wherein configuring a power generation unit to respond to the first cooling system after coupling the second cooling assembly to the first cooling system includes configuring a power generation unit to extract energy from to the first cooling system. 
   
   
       34 . A method of transferring heat from a nuclear fission reactor core, the method comprising:
 generating heat from propagating nuclear fission deflagration wave fission in a nuclear fission reactor core; and   transferring the heat from propagating nuclear fission deflagration wave fission to a condensed phase density fluid.   
   
   
       35 . The method of  claim 34 , wherein the condensed phase density fluid includes at least one condensed phase density fluid selected from a group including: water, liquid metals, terphenyls, polyphenyls, fluorocarbons, and FLIBE 
   
   
       36 . A method of cooling a propagating nuclear fission deflagration wave reactor, the method comprising:
 directing a heat absorbing material in a liquid state into thermal contact with a propagating nuclear fission deflagration wave heat generating region;   flowing the heat absorbing material to a region substantially out of thermal contact with the propagating nuclear fission deflagration wave heat generating region; and   extracting heat energy from the heat absorbing material at the region substantially out of thermal contact with the propagating nuclear fission deflagration wave heat generating region.   
   
   
       37 . A method of cooling a propagating nuclear fission deflagration wave reactor, the method comprising:
 directing a heat absorbing material into thermal contact with a propagating nuclear fission deflagration wave heat generating region, wherein the heat absorbing material includes non-nuclear-inert material;   flowing the heat absorbing material to a region substantially out of thermal contact with the propagating nuclear fission deflagration wave heat generating region; and   extracting heat energy from the heat absorbing material at the region substantially out of thermal contact with the propagating nuclear fission deflagration wave heat generating region.   
   
   
       38 . The method of  claim 37 , wherein the non-nuclear-inert material is selected to form a substantially liquid state upon extracting heat energy from the heat absorbing material at the region substantially out of thermal contact with the propagating nuclear fission deflagration wave heat generating region. 
   
   
       39 . The method of  claim 37 , wherein the non-nuclear-inert material is selected to reside in a substantially gaseous state upon extracting heat energy from the heat absorbing material at the region substantially out of thermal contact with the propagating nuclear fission deflagration wave heat generating region. 
   
   
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       54 . A method of controlling reactivity in a nuclear fission reactor, the method comprising:
 detecting a temperature at least one location in a core of a nuclear fission reactor;   producing a signal responsive to the detected temperature;   transmitting the signal responsive to the detected operating temperature to a control system; and   varying absorption characteristics of a neutron absorbing material proximate to the at least one location responsive to the transmitted signal.   
   
   
       55 . The method of  claim 54 , wherein the neutron absorbing material includes lithium. 
   
   
       56 . The method of  claim 55 , wherein the lithium includes Li6. 
   
   
       57 . The method of  claim 55 , wherein the lithium includes liquid lithium. 
   
   
       58 . The method of  claim 55 , wherein the neutron absorbing material does not include liquid lithium. 
   
   
       59 . The method of  claim 54 , wherein detecting a temperature at least one location in a core of a nuclear fission reactor includes thermally coupling to the at least one location with a thermocouple. 
   
   
       60 . The method of  claim 54 , wherein transmitting the signal responsive to the detected temperature to a control system includes transmitting an electrical signal to the control system. 
   
   
       61 . The method of  claim 54 , wherein transmitting the signal responsive to the detected temperature to a control system includes transmitting an optical signal to the control system. 
   
   
       62 . The method of  claim 54 , wherein transmitting the signal responsive to the detected temperature to a control system includes transmitting a radiofrequency signal to the control system. 
   
   
       63 . The method of  claim 54 , wherein transmitting the signal responsive to the detected temperature to a control system includes transmitting an acoustic signal to the control system. 
   
   
       64 . The method of  claim 54 , wherein transmitting the signal responsive to the detected temperature to a control system includes transmitting a magnetic signal to the control system. 
   
   
       65 . The method of  claim 54 , wherein detecting a temperature at least one location in a core of a nuclear fission reactor includes thermally coupling to the at least one location with a fluid. 
   
   
       66 . The method of  claim 65 , wherein the fluid includes a liquid. 
   
   
       67 . The method of  claim 66 , wherein the liquid includes a neutron absorbing liquid. 
   
   
       68 . A temperature control apparatus for nuclear fission reactor, the apparatus comprising:
 a core region;   a first fluid containing structure thermally coupled to the core region and containing a first fluid;   a second fluid containing structure oriented for absorption of neutrons from the core region and containing a second fluid chemically different from the first fluid.   
   
   
       69 . A temperature control apparatus for nuclear fission reactor, the apparatus comprising:
 a core region;   a first fluid containing structure thermally coupled to the core region and containing a first fluid; and   a second fluid containing structure oriented for absorption of neutrons from the core region and containing a second fluid substantially isotopically the same as the first fluid.   
   
   
       70 . The temperature control apparatus of  claim 69 , further comprising a pressure converter coupled between the second fluid and the first fluid. 
   
   
       71 . The temperature control apparatus of  claim 70 , wherein the pressure converter includes a pressure reducing mechanism. 
   
   
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