会议专题

Experimental Performance Analysis for Cold Trap Design

Prototype Fast Breeder Reactor (PFBR) is a 500MWe Liquid Metal Fast Breeder Reactor (LMFBR) under construction at Kalpakkam in India. PFBR is a pool type reactor, with two secondary sodium loops for transferring heat from primary sodium. In the secondary sodium loop, steam generator transfers heat from secondary sodium to the water which in turn becomes super heated steam. In case of a sodium water leak it should be detected in minimum time to ensure nuclear system safety. Hydrogen diffusion during normal operation is a major load in secondary side sodium. If this hydrogen concentration is more, it will mask the detection of small water leaks into sodium and this might result in propagation into large leak and failure of more tubes. Hence it is recommended to maintain a low residual hydrogen concentration during steady state operation. The main function of cold trap is to trap the hydrogen and oxygen content in sodium. The hydrogen impurities can cause plugging in the narrow passages of sodium flow and oxygen can cause corrosion of structural material. Cold trap is a purification unit used in sodium system of FBR’s for maintaining the oxygen/hydrogen level in sodium within acceptable limits. It works on the principle of crystallization and precipitation of oxides/hydrides of sodium in a wire mesh, when the temperature of sodium is reduced below the saturation temperature. The cold traps presently used have chances of prematurely plugging. The plugged cold traps are cleaned and are then put back into service. Frequent cleaning of cold trap results in the long down time of the sodium system. New design of cold trap has been conceived to overcome the above problems. The model cold trap for new design has been fabricated and experimentally tested for its effectiveness. Radiographic examination was carried out and analyzed the impurity deposition pattern. This paper shares the experience gained on experimental testing of new design of cold trap for FBR’s.

Fast breeder reactor sodium purification cold trap

M.G.Hemanath A.Ashok kumar S.Chandramouli C.Meikandamurthy G.Padmakumar K.K.Rajan B.Venkatraman P.Kalyanasundaram G.Vaidyanathan

Indira Gandhi Centre for Atomic Research Fast Reactor Technology Group, Kalpakkam, India -603102

国际会议

The 8th International Topical Meeting on Nuclear Thermal-Hydraulics,Operation and Safety(第八届反应堆热工水力、运行和安全国际会议 NUTHOS-8)

上海

英文

824-833

2010-10-10(万方平台首次上网日期,不代表论文的发表时间)