Improvement in oil seal performance of Gas Compressor in HTTR

Oyama, Sunao*; Hamamoto, Shimpei; Kaneshiro, Noriyuki*; Nemoto, Takahiro; Sekita, Kenji; Isozaki, Minoru; Emori, Koichi; Ito, Yoshiteru*; Yamamoto, Hideo*; Ota, Yukimaru; et al.

JAEA-Technology 2007-047, 40 Pages, 2007/08

JAEA-Technology-2007-047.pdf:18.83MB

High-Temperature engineering Test Reactor (HTTR) built by Japan Atomic Energy Agency (JAEA) has commonly used reciprocating compressor to extract helium gas and discharge helium gas into primary/secondary coolant helium loop from helium purification system. Rod-seal structure of the compressor is complicated from a prevention coolant leak standpoint. Because of frequently leakage of seal oil in operation, Rod seal structure isn't as reliable as it should be sustainable in the stable condition during long term operation. As a result of investigations, leakage's root is found in that seal were used in a range beyond limit sliding properties of seal material. Therefore a lip of the seal was worn and transformed itself and was not able to sustain a seal function. Endurance test using materials testing facility and verification test using a actual equipment on candidate materials suggest that a seal of fluorine contained resin mixed graphite is potentially feasible material of seal.

Operating document on management division waste management section in Tokai works in 2002 fiscal year

Kobayashi, Kentaro; Isozaki, Koei

JNC TN8440 2003-003, 139 Pages, 2003/04

JNC-TN8440-2003-003.pdf:19.77MB

This document is announced about task of Waste Management Division Waste Management Section in the 2002 fiscal year. Mainly, our task is that treated Low level solid waste, stored Low level solid waste and stored High level solid waste. Those wastes are generated from Tokai reprocessing plant in Tokai Works. We carried out task safety as planned. The results are as follows. (1)We incinerated that combustible Low level solid waste of 70.5 ton in Incinerate facility. Such wastes were generated from operation of Tokai reprocessing plant and cleaned up operation of Tokai bituminization facility (The fire and explosion incident of Tokai bituminization facility). (2)We stored Low level solid waste that generated the waste of 1,071 drums. It is found that Storage facilities will not fill on this condition Low level radioactive waste treatment facility is started operation. (3)We stored High level solid waste that generated the waste of 117 drums from Tokai reprocessing plant. And, it is found that there facilities will not fill on this condition generated wastes of about 100 drams by a year. (4)We started printing of the data from the 2002 fiscal year to intranet which amount of stored Low level solid waste and High level solid waste in order to educate the amount reduction of waste generating (at those facilities).

Fabrication of saturated temperature capsule for IASCC study

Ishikawa, Kazuyoshi; Kikuchi, Taiji; Isozaki, Futoshi*; Inoue, Hiromi; Oba, Toshihiro; Matsui, Yoshinori; Saito, Takashi; Nakano, Junichi; Tsuji, Hirokazu

JAERI-Tech 2002-061, 69 Pages, 2002/08

JAERI-Tech-2002-061.pdf:12.21MB

Study of irradiation assisted stress corrosion cracking (IASCC) is an important subject for the plant life assessment and extension of the light water reactors (LWRs). It is necessary that initiation mechanism of IASCC should be made clear under combined effect of irradiation, environment and stress in order to understand IASCC phenomena. Under the existing circumstance, Saturated Temperature Capsule (SATCAP) were fabricated for the irradiation test of IASCC studies in Japan Material Testing Reactor (JMTR). SATCAP is the irradiation rig to irradiate materials in high pressure water of controlled chemistry and temperature simulating Boiling water reactors (BWRs) core environment from the new water feelding system of out-of-pile. This report describes (1) investigation of technical problems for the design and fabrication of SATCAP, (2) the tests results of the problems and (3) fabrication and inspection of SATCAP.

The Method for decrease of helium gas leak with double O-ring rubber gasket

Oba, Toshihiro; Kikuchi, Taiji; Taka, Isamu; Isozaki, Futoshi*; Chiba, Masaaki; Ishikawa, Kazuyoshi; Inoue, Hiromi*; Terunuma, Isao*; Sawabe, Masaki*; Tsuda, Kazumi*; et al.

JAERI-Tech 2001-067, 29 Pages, 2001/11

JAERI-Tech-2001-067.pdf:1.93MB

no abstracts in English

None

Sakagawa, Yoshinobu; ; ; Inanobe, Kazuhide*; ; ; *

PNC TN8410 98-080, 177 Pages, 1997/12

PNC-TN8410-98-080.pdf:9.93MB

None

Out-pile tests for improved type rabbits in JMTR

Kitagishi, Shigeru; Isozaki, Futoshi; Takita, Kenji; Aoyama, Masashi; Matsui, Yoshinori

no journal, , 

As one of the production of radioisotopes, JMTR has a plan to produce Mo which is a parent nuclide of Tc. The new hydraulic-rabbit-irradiation-facility is carried out to be set up in the preparation of the Mo production facility. For the expansion of use, the new facility was designed to be able to irradiate rabbits more than it used to be. However, it takes more than about ten days to assemble the rabbit. For this reason, it is required shortening of the assembly period. The improved type of rabbit, which was developed to shorten the assembly period in JRR-3, was focused. And, out-pile tests were carried out for research of the fabrication of the improved type rabbit and the endurance performance under the usage environment in JMTR. In these tests, first, the assembly device for the improved type of rabbit was designed and fabricated, and the fabrication test was carried out using the assembly device. Next, the endurance performance tests were carried out using mock-up rabbits. From the results of these tests, there were bright prospects of the manufacturability of the improved type of rabbit had good sealing performance and utilizing in the irradiation test of JMTR.

Development of safety review method to cope with an aging degradation for the facilities using nuclear material, 2; Risk assessment flow of equipments

Tamaoki, Yuichi; Isozaki, Ryosuke; Suzuki, Ryuta; Akada, Masataka; Sawahata, Satoshi; Yonezawa, Ryoma; Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki

no journal, , 

no abstracts in English

Development of risk assessment method to cope with an aging degradation for the facilities using nuclear material, 1; Risk point evaluation of aging equipment

Isozaki, Ryosuke; Tamaoki, Yuichi; Suzuki, Ryuta; Akada, Masataka; Sawahata, Satoshi; Suzuki, Hisashi; Yonezawa, Ryoma; Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki

no journal, , 

no abstracts in English