Patent ES-288273-A1 (ES)
Title: Multi-pass, vapor moderated and cooled nuclear reactor and method of operating to variably moderate and control same
IPC: G21C1/08
Filed: 1963-05-22
Abstract: In a heterogeneous reactor th core is arranged for the passage therethrough of gaseous moderator-coolant fluid providing neutron moderation by hydrogen atoms and effecting reactor criticality serially in three passes. In the first pass the gaseous fluid flows over some of the fuel elements in the second pass the gaseous fluid flows between fuel elements without flowing directly over them and in the third pass the gaseous fluid flows over the remainder of the fuel elements. The preferred gaseous moderator-coolant fluid is steam at super-critical pressures alternative fluids are: vaporous hydrocarbons, e.g. acetylene or benzene, pure hydrogen, steam or mixtures of any of these with inert gases. The moderating effect of steam is a function of its density and the latter can be varied by varying its pressure or temperature or by diluting the steam with a non-moderating gaseous fluid, e.g. heavy water steam. A reactor 20, Fig. 1, in a pressure vessel 22 is moderated and cooled by a gaseous fluid driven by a pump 40 through the reactor core in three passes 24, 26 and 28. In the first pass 24 the fluid flows downwardly and cools some of the fuel elements by passing in parallel streams through tubes surrounding those elements, in the second pass 26 the fluid flows upwardly through the core without contacting any fuel elements, and in the third pass 28 the fluid flows downwardly in parallel streams through tubes surrounding the remaining fuel elements and cools those elements. The fluid acts as moderator in each pass. The heated fluid passes through line 32 to heat exchangers 34, 36 where it gives up its heat to a secondary heat transfer fluid and is driven by the pump 40 through a third heat exchanger 46. The heat exchanger 46 may serve as a generator of vapour which is heated in the heat exchangers 34, 36 and functions as the secondary heat transfer fluid. The primary fluid returns to the reactor through a line 30. An orifice 48 in the pump outlet line 42 creates a slight pressure drop between its two sides, these two sides being connected by lines 50, 52 to a chamber 54. Gaseous moderator coolant may be admitted to the system through a line 56 having a metering device 58 and removed from the system through a line 60 and metering device 62. A valve 63 permits rapid reduction of the fluid pressure to shut down the reactor. The devices 58, 62 thus enable the power output of the reactor to be controlled, the Specification giving typical temperature and pressure and other qualities of steam both at commencement of the reactor operation and after the core has aged, the accumulated poisons requiring that steam pressure be increased to increase its density to maintain the chain-reaction throughout the reactor life. The chamber 54 increases the volume of the system outside the reactor and permits temperature rises or falls in the reactor to have greater effects upon the average gaseous fluid density. The Specification explains how the reactor tends to automatically regulate its reactivity to maintain a given heat output and how its heat release tends to automatic flux flattening. In an embodiment of the reactor, Fig. 2, a pressure vessel 22 has an inlet nozzle 82, an outlet nozzle 124, a thermal shield 88 and a layer of neutron reflecting material 90, further neutron reflecting material being provided at 132, 134 and further thermal shielding at 136, 138. The vessel is divided into an inlet plenum 94, a core region 95 and an outlet plenum 96 by upper and lower tube sheets 97, 98. Tubes 112, belonging to the first pass 24 of Fig. 1, are secured at their upper ends to the sheet 97 and extend with a sliding fit through a secondary upper tube sheet 110, their lower ends debuching into the lowermost part of the core region 95. Tubes 114, belonging to the third pass 28, are secured at their lower ends to the tube shaft 98 and terminate at their upper ends in the space between the sheets 97, 110, Fig. 5. Tube sheet 98 forms the top of an outlet header 118 connected through pipes 120 to the nozzle 124. An annular condensate collection chamber 140 is provided in the plenum 94, a baffle 142 forcing the incoming fluid over the chamber before it passes through the central passageway to the fuel elements. Each tube 112, 114 contains a fuel element 160 having a head 150, the fuel elements being arranged on a triangular pitch and in hexagonal bundles (Figs. 3, 4, not shown). For each tube 112 there are three tubes 114, the tubes 114 being surrounded by heat insulation 166. Each bundle includes tube sheets 148, 156 supported on the tube sheet 97 by spacers 154, the fuel elements 160 being supported by the heads 150 resting on the sheets 148. The primary fluid enters the nozzle 82 and passes through orifices 152 in tube sheets 148, 156 and through the space between sheets 97, 156 to enter the upper ends of the tubes 112. The fluid leaves the tubes 112 at their lower ends and passes upwardly through the core in the spaces between the tubes 112, 114, the fluid flowing through passages (not shown) in the reflector 132 and tube sheet 110 and thence enters the upper ends of the tubes 114. The fluid discharges from the lower ends of the tubes 114 into the header 118 and thence flows to the outlet nozzle 124. A third pass tube 114 (Fig. 7, not shown) encloses a fuel element 160 having longitudinal spacing strips 168 and heat insulated by stainless steel wool 174 disposed between a corrugated tubular member 170, and an outer tube 172. A first pass tube 112 (Fig. 8, not shown), is similar to Fig. 7 but omits the insulation 174 and outer tube 172. In a modified tube 114 (Fig. 9, not shown), the heat insulation is provided by layers of stainless steel foil and the outer tube is strengthened by grooves or dimples. To obtain an advantageous distribution of heat release along the fuel elements the thermal insulation 174 of Fig. 7 may include ZrH2 in regions where more moderation is desired and Al2O3 in other regions where such additional moderation is not desired. The Specification gives constructional and operating data of a reactor utilizing steam at supercritical pressures for moderator and coolant, the reactor being loaded with U-235 and U-238 so that, in addition to producing power, it functions as a breeder.