Examination results on reaction of lithium

Asada, Takashi; Kawai, Masataka *

JNC TN9410 2001-001, 153 Pages, 2000/12

JNC-TN9410-2001-001.pdf:11.14MB

Before the material corrosion tests in lithium, the reactions of lithium with air and ammonia that will be used for lithium cleaning were examined, and the results were as follows. (1)When lithium put into air, surface of lithium changes to black first but soon to white, and the white layer becomes gradually thick. The first black of lithium surface is nitride (LiN) and it changes to white lithium hydroxide (LiOH) by reaction with water in air, and it grows. The growth rate of the lithium hydroxide is about 1/10 in the desiccator (humidity of about 10%) compare with in air. (2)When lithium put into nitrogen, surface of lithium changes to black, and soon changes to brown and cracks at surface. At the same time with this cracking, weight of lithium piece increases and nitridation progresses respectively rapidly. This nitridation completed during 1-2days on lithium rod of 10mm in diameter, and increase in weight stopped. (3)Lithium melts in liquid ammonia and its melting rate is about 2-3 hour to lithium of 1g. The liquid ammonia after lithium melting showed dark brown.

Lithium

JNC TN9410 2000-012, 18 Pages, 2000/09

JNC-TN9410-2000-012.pdf:1.3MB

Properties of lithium and its handling, and corrosion property to structural material were investigated on a viewpoint of use it for coolant on fast reactor. Investigated items are production procedure, physical and chemical properties, corrosion properties, procedure of handling etc., and combustion and extinction of lithium and corrosion properties to structural material were confirmed by tests.

ATR Demonstration reactor integrity verification test for the pressur tube rolled joint portion (Fiscal 1988)

; ; ; ;

PNC TN9410 94-052, 251 Pages, 1994/01

PNC-TN9410-94-052.pdf:9.33MB

The structure of the pressure tube rolled joint portion for the ATR Demonstration Reactor is somewhat changed from that for Fugen, in order reduce the residual stress around the portion. Therefore, Constant Temperature Endurance Test and Thermal Cycle Endurance Test have been conducted under the reactor operating conditions except irradiation to examine the rolled joint integrity. (1)Constant Temperature Endurance Test. In fiscal 1988, Constant Temperature Endurance Test have been performed in the Component Test Loop for 2,033 hours under the reactor operating conditions (pressure 75kg/cm, temperature 280C) for the JP-3 specimen (total testing period 4,033 hours) and the JP-4, JP-5 specimens (total testing period 9,533 hours). After the endurance test it was found by the helium leak test that the rolled joint tightness was maintained enough. Therefore, it was confirmed that the reduction of the residual atress at the rolled joint portion which occurred at the initial stage of the operation did not affect the rolled joint tightness. (2)Thermal Cycle Endurance Test. The helium leak test and the ultrasonic flaw detection test were performed before and after Thermal Cycle Endurance Test (the unmber of thermal cycle increaced from 60 times to 140 times in fisical 1988), of which results showed the integrity of the rolled joint tightness and no crack propagation near the rolled joint portion. Therefore, it was confirmed that 140 times thermal cycle which was the design value for the reactor life of 30 years did not affect the rolled joint tightness and the initiation and propagation of a crack even for the specimen with 200 ppm hydrogen.

Irradiation Creep and growth of pressure tubes in HWR Fugen

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PNC TN9410 87-105, 47 Pages, 1987/08

PNC-TN9410-87-105.pdf:5.29MB

The 165MWe prototype HWR Fugen has been in commercial operation since March 1979. The material of the pressure tube is heat treated Zr-2.5 wt%Nb alloy and the pressure tubes in the Fugen have been irradiated with the maximum fast neutron flux of about 3 10 n/msec. The pressure tubes have been inspected periodically according to the pressure tube monitoring program. In March 1984, inside diameter measurements on a small number of the pressure tubes were performed by using the pressure tube monitoring device adopting an ultrasonic wave method, and the diametrical irradiation creep and growth strain has been assessed. In February 1987, tube length measurements were performed and these data are to be used as the standard value for the estimation of the axial irradiation creep and growth strain. Besides, small diameter specimens pressurized by helium gas have begun being irradiated in the Fugen since April 1987.

Effect of hyperthermal atomic oxygen exposures on hydrogenated diamond-like carbon films

Yokota, Kumiko*; Asada, Hidetoshi*; Tagawa, Masahito*; Ohara, Hisanori*; Nakahigashi, Takahiro*; Yoshigoe, Akitaka; Teraoka, Yuden; Martin, J. M.*; Belin, M.*

no journal, , 

Hydrogenated diamond-like carbon (DLC) is expected as a lubricant for space uses because of its ultra low friction charactor in vacuum. Thus, DLC films were exposed to atomic oxygens which were generated by a laser detonation method simulating a low orbit space environment. The DLC surfaces were analysed and the results are reported in this talk. The hydrogenated amorphous DLC was fabricated by a RF-CVD method on Si substrates. Relative collision energy of space planes against atomic oxygens can be simulated with the space environment experimental apparatus. The DLC films exposed to atomic oxygens were analysed by an SR-PES method etc. The SR-PES was performed at the surface chemical reaction analysis station installed in the BL23SU of SPring-8. It was suggested that some volatile oxides were formed and desorbed from the DLC surface when DLC surface was irradiated by atomic oxygens with an incident energy of 4.2 eV and fluence of 510atoms/cm.