Patent GB-966874-A (GB)
Title: Improvements in or relating to nuclear reactors
IPC: G21C1/00
Filed: 1961-03-16
Abstract: 966, 874. Nuclear reactors. GENERAL ELECTRIC CO. March 16, 1961 [March 18, 1960], No 9639/61. Heading G6C. A liquid moderated nuclear reactor comprises a core providing elongated, parallel, coolant flow passages in which are mounted fuel element assemblies, the fuel elements of which are spaced apart from one another by a distance sufficient to provide, with the moderating coolant in the intervening spaces and in the absence of vaporized moderating coolant, a given moderator-to-fuel ratio, wherein each passage is separated from the immediately adjacent passages by a single wall of structural material of low neutron absorption cross-section and wherein the peripheral fuel elements in each assembly are spaced apart from the proximate peripheral fuel elements in the adjacent fuel assemblies by a distance through said single wall sufficient to provide, with the moderating coolant in the intervening spaces on each side of the wall and in the absence of vaporized moderating coolant, a moderator-to-fuel ratio which is substantially the same as that within each of the passages. As shown in Fig. 4, the core comprises square section flow channels 20 arranged in checkerboard fashion to leave intermediate open coolant flow passages 106, 114 and 116. In each of the flow passages enclosed by channels 20 and the flow passages 106 between these channels is disposed an assembly of fuel elements 120, (e.g. of sintered UO 2  including 1. 5% U<SP>235</SP>O 2 ) and the core is enclosed in a shroud 22 fitted with strips 23, 25 of the same thickness as the channels 20 adjacent the outer open flow passages 114, 116. If each fuel element 120 has a radius r and the elements are spaced apart by a distance d 1 , then the volumetric moderator-to-fuel ratio R 1  equals d 1 <SP>2</SP> - <SP>#</SP>r<SP>2</SP>/#r 2  In regions 128, 130 however, adjacent the peripheral fuel elements, the volumetric moderator-to-fuel ratio R 2  equals (d 4 -t)<SP>2</SP> -#r<SP>2</SP>/#r<SP>2</SP>, where d 4  is the distance between a peripheral fuel element within a flow channel 20 and a proximate fuel element in an open flow passage and t is the channel wall thickness. Since d 4  = d 1  + t, R 1  = R 2  and the ratio is therefore uniform throughout the core. In alternative embodiments the core structure is built up from sheets 140 bent at 90 degrees angles (Fig. 6), or from sheets 154 bent at 30 degrees angles with strips 170 secured to alternate bends (Fig. 7). In Fig. 14 is shown a fore-shortened longitudinal view of a portion of the core, the fuel assemblies 228 being secured in position by spring-loaded lugs 240 on handles inserted in openings 202 in the channel walls. At the lower ends of the fuel assemblies are locking elements 234 which press latches 220 mounted in the channel walls into openings 182 in the core support grid 26. The individual fuel elements 226 in each fuel assembly 228 are spaced from each other by wire mesh spacer structures disposed at intermediate points along their length. A control element 122 of cruciform cross-section substantially the same as that of an outline drawn around a plurality of adjacent fuel elements tangent to their exterior surfaces is (included in the embodiment) shown in Fig. 4. Another form of control element 252 having a square section central opening 254 is shown in Fig. 16, the transverse dimension of this opening being preferably between 0. 25 and 5 times the slowing down length (i.e. the vector distance a neutron moves from its formation as a fission neutron through a given moderator in attainment of thermal energy). The element 252 is connected to a drive mechanism for reciprocation in a flow passage formed between flow channels 200 by means of a rod 258 secured to a yoke 260 at each end of which is a latching mechanism 262. Each mechanism 262 comprises a rod 266 which on rotation causes a cam 270 to displace locking balls 272 outwardly into engagement with detents 276 on the inner surface of the upper end of the control element 252. The element 252 is connected at its base to either a fuel assembly follower in the form of a fuel assembly 228a (Fig. 16) or a void follower of the same crosssection as the element and internally supported by a bundle of tubes or a solid bar. While the invention is described with particular reference to a boiling water reactor using light water as the moderating coolant, it also encompasses the use of moderating coolants other than light water, e.g. heavy water and hydrocarbons such as diphenyl, the isomeric terphenyls, naphthalene or anthracene. The coolant may be either boiling or non- boiling.