发明名称 Dampfgekuehlter Kernreaktor
摘要 910,300. Nuclear reactors. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Nov. 9, 1960 [Nov. 26, 1959], No. 40172/59. Class 39 (4). A steam-cooled nuclear reactor of the kind comprising a moderator structure penetrated by a lattice of blind-end channels 3 with fuel elements 5 in the channels and with coolant flow barrier sleeves 4 disposed lengthwise, one in -each channel, to define outer, inflow paths 7 with the channel walls and inner, outflow paths 6 with the fuel elements, has beneath the lower end of each barrier sleeve 4 a baffle 8 so disposed with slight clearance from the channel walls to allow steam condensate to descend the walls past itself and which is shaped to deflect steam coolant flowing down the inflow path 7 up the outflow path 6, means being provided for removing condensate collected below the baffle. A moderator-containing calandria tank 2 is pierced by a lattice of calandria tubes 11 which locate the channels 3 and is divided into three horizontal sections 12, 13 and 14 by division plates 15. Section 14 contains light water as neutron shielding and section 13 heavy water as moderator, whilst section 12 contains a structure of graphite granules 70 and boron steel plates 71 (or a combination of graphite and light water) as neutron shielding. The channels 3 are connected by demountable joints 17 to pipes 16 having inlets 18 and outlets 19 separated by sealing rings 20, the pipes 16 terminating at a charge face 21 and being pressure-sealed by removable plugs 22. The barrier sleeves 4, which are mounted inside the channels 3 by means of spiders 23, support the sleeves 24 housing the fuel elements 5 with the spaces 27 between the sleeves 4 and 24 acting as a thermal insulant between the elements 5 and the channels 3. The upper ends of the sleeves 24 support removable neutron scatter plugs 28 as described in Specification 897,446. The channels 3 are of zirconium and the pipes 16 of steel. Steel condensate outlet pipes 10 are connected to apertures 54 in the lower ends 53 of the channels 3 and have flanges 55 carrying plates 59 which support the baffles 8. The baffles have central drain holes 60. Neutron shield plugs 63 having apertures 67 to accommodate the pipes 10 seal the lower ends of the calandria tubes 11. Stressing of the joints 17 is prevented by the use of guide members 38, described in Specification 910,299, which allow lengthwise movement only of the pipes 16 and channels 3. Recesses 45 formed within these members 38 are filled with graphite granules 61 and boron steel plates 62 to provide a neutron shield. The baffles 8 prevent the outlets 10 from being subjected to the full force of inflowing steam upon start-up and, after a shut-down, prevent entrainment of condensed coolant (since this is collected by way of the drain holes 60) with the steam coolant at the next start-up.
申请公布号 DE1172381(B) 申请公布日期 1964.06.18
申请号 DE1960U007597 申请日期 1960.11.22
申请人 UNITED KINGDOM ATOMIC ENERGY AUTHORITY 发明人 BRADLEY NORMAN
分类号 G21C15/20 主分类号 G21C15/20
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