Experience with the Molten-Salt Reactor Experiment

熔盐反应器 裂变材料 熔盐 核工程 液态氟化物钍反应堆 裂变产物 乏核燃料 关闭 环境科学 核能 浓缩铀 核反应堆堆芯 废物管理 钍燃料循环 混合氧化物燃料 放射化学 工程类 化学 材料科学 核物理学 物理 冶金 中子
作者
P.N. Haubenreich,J.R. Engel
出处
期刊:Nuclear applications & technology [Informa]
卷期号:8 (2): 118-136 被引量:413
标识
DOI:10.13182/nt8-2-118
摘要

AbstractThe MSRE is an 8-MW(th) reactor in which molten fluoride salt at 1200°F circulates through a core of graphite bars. Its purpose was to demonstrate the practicality of the key features of molten-salt power reactors.Operation with 235U (33% enrichment) in the fuel salt began in June 1965, and by March 1968 nuclear operation amounted to 9000 equivalent full-power hours. The goal of demonstrating reliability had been attained—over the last 15 months of 235U operation the reactor had been critical 80% of the time. At the end of a 6-month run which climaxed this demonstration, the reactor was shut down and the 0.9 mole% uranium in the fuel was stripped very efficiently in an on-site fluorination facility. Uranium-233 was then added to the carrier salt, making the MSRE the world's first reactor to be fueled with this fissile material. Nuclear operation was resumed in October 1968, and over 2500 equivalent full-power hours have now been produced with 233U.The MSRE has shown that salt handling in an operating reactor is quite practical, the salt chemistry is well behaved, there is practically no corrosion, the nuclear characteristics are very close to predictions, and the system is dynamically stable. Containment of fission products has been excellent and maintenance of radioactive components has been accomplished without unreasonable delay and with very little radiation exposure.The successful operation of the MSRE is an achievement that should strengthen confidence in the practicality of the molten-salt reactor concept.

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