Applicability of redundant pairs of SOI transistors for analog circuits

Makihara, Akiko*; Yokose, Tamotsu*; Tsuchiya, Yoshihisa*; Tani, Koichi*; Morimura, Tadaaki*; Abe, Hiroshi; Shindo, Hiroyuki*; Ebihara, Tsukasa*; Maru, Akifumi*; Morikawa, Koichi*; et al.

Proceedings of 10th International Workshop on Radiation Effects on Semiconductor Devices for Space Applications (RASEDA-10) (Internet), p.119 - 122, 2012/12

no abstracts in English

Experiments on the water leak detection systems in the 50MW steam generator test facility (9); Cold trap efficiency test, hydrogen background concentration test, hydrogen flux through tube test

Kaneko, Yoshihisa*; Nishikimi, Masakazu*; Shirato, Seiichi*; *

PNC TN941 85-22, 142 Pages, 1985/02

PNC-TN941-85-22.pdf:3.57MB

Series of tests on water leak detection system for Monju steam generators have been excuted in the 50MW Steam Generator Test Facility (50MW SGTF). This paper describes the test results about the removal efficiency of hydrogen by the secondary cold trap, the hydrogen background concentration and hydrogen flux through heat transfer tubes to secondary sodium in steam generator (SG) in order to make clear the hydrogen behavior during ordinary plant operation from October in 1976 to July in 1983. Main results from these tests are: (1)The removal efficieney of hydrogen by the cold trap is 7080 percents, but it shows tendency to decrease when difference between hydrogen concentration at cold trap and that in secondary main loop is small. (2)Hydrogen flux through tubes is smaller than the value which is reported in the first report of these series reports. (3)It is found that the hydrogen background concentration in the secondary main loop of 50MW SGTF is thoroughly low. (4)It is estimated that the hydrogen background concentration in the secondary main loop in Monju plant is lower than 169 ppb.

Environmental effect test of rupture disk (I)

Kaneko, Yoshihisa*; *; Nishikimi, Masakazu*; *; *

PNC TN941 84-93, 139 Pages, 1984/06

PNC-TN941-84-93.pdf:14.96MB

Rupture disks were tested for a purpose of examination of burst characteristic, corrosion, change of metal formation and mechanical characteristic. Those rupture disks were installed at evaporator (reverse buckling type), superheater (reverse buckling type) and reaction product vessel (tension loaded type) and were used from September, 1975 to January, 1983 at 50 MW steam generator test facility (50 MW SGTF). Main results are the following; (1)Burst pressure of used and unused rupture disks of steam generator and reaction product vessel was lower than the value measured at producted time. But it satisfied specification in purchase. (2)Burst characteristic of rupture disk for steam generator did not Change even after they were used for 1013812387 hours through at the condition of 200430C and 0.7 1.4kg/cmg. (3)Rupture disks of steam generator and reaction product vessel opened perfectly at burst test. (4)Corrosion was scarcely found. (5)Metal formation and mechanical and physical characteristics of material (Inconel X-750) of rupture disk has changed (age hardnening) through environment effect. (6)If we use Inconel X-750 as rupture disk material for steam generator, we must put in operation after ageing treatment. Otherwise it is desirable to use Inconel 600 or 625 which is not effected by age hardnening and has heatproof and corrosion-resistance characteristics.