Development of sodium facilities for NSRR fast reactor fuel tests. 1. Purification/charging and test loops

In order to commercialize fast reactors, which are expected to be long-term transmuters of plutonium and long half life radioactive wastes (such as americium) from light water reactors, safety research on fuel behavior under accident conditions and establishment of the safety guidelines are essential. Sodium facilities, such as, (1) Purification/charging loop and test loop, and (2) Proto-type sodium capsule, were developed and fabricated in order to irradiate fast reactor fuels under sodium cooling conditions in the Nuclear Safety Research Reactor (NSRR) of JAERI, aiming to investigate fuel behavior under transient over-power conditions. This report presents the purpose, outlines, specifications, capabilities and operation results of the facilities. The purification/charging loop is licensed as a part of the NSRR, which enables the facility to be used for the future irradiation capsule. The test loop was designed to perform thermal/hydraulic tests with heater pins and development of instruments. Additional facilities, such as, disassembling facility of test fuels and capsules contaminated with sodium after the irradiation tests are needed for the future irradiation tests. (author)