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Ichikawa, Shoichi; Chiba, Yusuke; Ono, Fumiyasu; Hatori, Masakazu; Kobayashi, Takanori; Uekura, Ryoichi; Hashiri, Nobuo*; Inuzuka, Taisuke*; Kitano, Hiroshi*; Abe, Hisashi*
JAEA-Research 2016-021, 32 Pages, 2017/02
JAEA-Research-2016-021.pdf:5.0MB
In order to reduce the influence on a plant schedule of the MONJU by the maintenance of dew point hygrometers, The JAEA examined a capacitance type dew point hygrometer as an alternative dew point hygrometer for a lithium-chloride type dew point hygrometer which had been used at the CV-LRT in the MONJU. As a result of comparing a capacitance type dew point hygrometer with a lithium-chloride type dew point hygrometer at the CV-LRT (Atmosphere: nitrogen, Testing time: 24 hours), there weren't significant difference between a capacitance type dew point hygrometer and a lithium-chloride type dew point hygrometer. As a result of comparing a capacitance dew point hygrometer with a high-mirror-surface type dew point hygrometer for long term verification (Atmosphere: air, Testing time: 24 months), the JAEA confirmed that a capacitance type dew point hygrometer satisfied the instrument specification (
2.04
C) required by the JEAC4203-2008.
Nakazawa, Takashi; Kikuchi, Hisaki; Yasu, Katsuji; Yoshino, Toshiaki; Ashikagaya, Yoshinobu; Sato, Koichi; Minowa, Yuji; Nomura, Toshibumi
JAERI-Tech 2001-010, 125 Pages, 2001/03
no abstracts in English
Nakazawa, Takashi; Yoshino, Toshiaki; Yasu, Katsuji; Ashikagaya, Yoshinobu; Kikuchi, Hisaki
JAERI-Tech 2001-001, 101 Pages, 2001/02
JAERI-Tech-2001-001.pdf:5.15MB
no abstracts in English
Ito, Hideaki; ; ; Okubo, Toshiyuki
PNC TN9410 96-298, 177 Pages, 1996/11
The fuel handling facility in "JOYO" must maintain an argon atmosphere and be gas tight; this prevents the oxidation of sodium adhering to a fuel assembly and leakage of radioactive gases. Periodic leak testing of the double O-ring gas seal had been performed at increasing pressure to assure its specified leak tightness. The problem with this method was that it took a long time to obtain an accurate measurement. The leak testing methods for the fuel handling facility, the reactor containment vessel, and other vessels were all reexamined. As a consequence, it was determined that alternative devices and methods for improving the leak rate measurements should be studied. Four methods of leak testing were evaluated; the present increasing pressure method, helium leak testing, decreasing pressure method, and a liquid nitrogen decreasing pressure method. A new automatic leak measurement device was used in these evaluations. The results of the utilization and limitations of the four methods of leak testing are summarized as follows. (1) The decreasing pressure leak testing method was efficient with regard to accuracy and stability for use in the fuel handling facility. (2) The automatic leak measurement device used a statistical calculation to measure the leak rate stability and it met the specified measurement requirements. (3) The leak rate measuring time was reduced by half with this new device and it could also simultaneously examine other objects.
; ; ; Miyake, Osamu
PNC TN9410 93-068, 81 Pages, 1993/03
In order to be useful for selecting specifications about the safety of the large scale fast breeder reactor on and after Monju, following items were studied. (1)Design conditions of the reactor containment, (2)scenarios as to beyond design basis accident (3)sodiunl fire, (4)fission product retention capability in sodium, and (5)applicability or the method of PSA. Technical documents provided for these studies are summarized in this report.
; ; ; Miyake, Osamu
PNC TN9410 92-068, 73 Pages, 1992/03
ln order to be useful for selecting specifications about the safety of the large scale fast breeder rector on and after Monju, following items were studied. (1)Design conditions of the reactor containment, (2)scenarios as to evaluation of core disruptive accident, and (3)applicability of the method of PSA. Technical documents provided for these studies are su㎜arized in this report.
*; *; Himeno, Yoshiaki; Haga, Kazuo*; Miyake, Osamu; *; *
PNC TN9410 90-119, 58 Pages, 1990/03
With a view to giving reasonable requirements for design of containment features in a large LMFBR, this study discusses the following issues: selection of representative events considered in the safety design/evaluation, consideration of the effect of sodium on FP retention in the "Hypothetical Accident" (site evaluation accident), and evaluation of safety margin against beyond-design-basis events. This report contains some technical documents which are provided to the study group meeting.
Hiroi, Hiroshi*; Matsuki, Takuo*; Miyake, Osamu; *; Himeno, Yoshiaki
PNC TN9410 88-078, 105 Pages, 1988/07
Following the study in JFY86, parametric calculations of a sodium leak accident in the plant were conducted using the CONTAIN code. This is to clarify influences of the design conditions and assumptions of the accident and to study characteristics of the "hot cell" concept and the "confinement united with the building" system. In addition, a model of heat transfer from bare pipes and components was incorporated into the code. The major conclusions are as follows: (1)Incorporation of the model of heat transfer from bare pipes to the cell atmosphere reduced the release of fission products (FP) to 20
30% of that obtained in the previous calculations in JFY86. (2)The most influential parameter on the FP release was the leak rates of cell to the confinement or the atmosphere. (3)Location of sodium leak, oxygen concentration in the cell, and capacity of the normal off-gas system scarcely affected the FP release. (4)The FP release in all calculational cases were far below the target values which are assumed for a site evaluation of a large FBR.
; ; ; ;
Journal of Nuclear Science and Technology, 10(9), p.566 - 573, 1973/09
no abstracts in English
;
Karyoku Hatsuden, 22(7), p.906 - 912, 1971/08
no abstracts in English
Ito, Chikara
no journal, ,
no abstracts in English
-ray detector development in the experimental fast reactor JoyoIto, Chikara
no journal, ,
no abstracts in English
Abe, Satoshi; Ishigaki, Masahiro; Shibamoto, Yasuteru; Yonomoto, Taisuke
no journal, ,
no abstracts in English
