Reactor core for a high temperature reactor gasgekuehlten

摘要

1507970 Reactors WESTINGHOUSE ELECTRIC CORP 6 Jan 1977 [6 Jan 1976] 00351/77 Heading G6C A fuel arrangement for a h.t.g.r. comprises a plurality of adjacent vertical columns (Fig. 1, not shown), each column comprising a stack of fuel assemblies, each fuel assembly, Fig. 3, comprising an elongated graphite moderator block 44 through which a number of spaced fuel passageways 50, 52 and a central control passageway 20 extend axially. Fissile fuel elements 42 (U-235) are removably received within passageways 50 while fertile fuel elements 40 (Th-232) are removably received within passageways 42, there being twice as many fertile elements 40 so fissile elements 42, the former being of smaller diameter than the latter. Fig. 5 shows a referactory fuel retainer 54 bonded to the bottom of each fuel passageway with an internal opening that exposes the end of a fuel element 40, 42, as allowing the element to be pushed out of the block 44 when so desired. A chamfered portion 58 of the retainer 54 ensures a continuous coolant path even if the fuel elements of a column are slightly misaligned. A removable retainer, such as one threaded or pinned into the block 44 at one or both extremities, could alternatively be used. A burnable neutron poison, e.g. boron, may be incorporated into the block 44 during manufacture. The fuel elements 40, 42 are extruded as elongated right circular cylinders each having a central circular coolant passageway and formed of fuel particles homogeneously distributed in a high density graphite matrix. A matrix of high density, e.g. 1À9 g./c.c., is attained by use of an 85 : 15 wt. ratio graphite flour/carbon black extrusion mix. The fuel particles (Figs. 7a, 7b, not shown) comprise a core of 93% enriched U-235, U-233 or Th-232 surrounded by a porous pyrocarbon buffer coat and a dense isotropic pyrocarbon coat, which in one form, are subsequently surrounded by a silicon carbide coat and an isotropic pyrocarbon caot. After a four year residence in the core, with a given fuel assembly progressing downward through the core until the fourth year when it is placed at the exit end of the core (Figure 8, not shown), the assembly is removed to an on-site hot cell where the spent fissile elements 42 are replaced with new fuel while the fertile elements 40 may be recycled.