Fast breeder prototype reactor Monju fuel assembly water flow test

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This paper describes the FBR fuel assembly flow test which PowerReactor & Nuclear Fuel Development Corporation(PNC)is nowdeveloping for"MONJU".An experiment was performed by loading fuel assembly into the waterloop and the total pressure drop in the fuel assembly and its componentpressure drop were measured.The tested fuel assemblies consist of 7 reactor core fuel assembliesand 1 blanket fuel assembly. These fuel assemblies were manufacturedby 5 companies as the first preproduction for"MONJU". Reactor corefuel assemblies were classified into 5 grid type spacer fuel assembliesand 2 wire wrapped spacer fuel assemblies.The water temperature was 60-C,but one of the total fuel assemblypressure drop tests was done at 30,40,60-C,and in these tests theeffect of water temperature on the pressure drop was ascertained.The Reynolds number of the investigation at the pin bundle ranged be-tween 2.0x104 and 5.0x104 in the reactor core fuel assembly testsand between 5x103 and 2x104 in the blanket fuel