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Inoue, Shuichi; Omuro, Tadao; Nabeya, Hideaki; Matsui, Yoshinori; Iida, Kazuhiro; Ito, Kazuyuki; Kimura, Akihiro; Kanno, Masaru
JAEA-Technology 2010-010, 27 Pages, 2012/05
JAEA-Technology-2010-010.pdf:1.99MB
In fuel irradiation transient tests using a boiling water capsule, a dilution tube has been installed in the boiling water capsule in order to detect fission products (FP) from an irradiated fuel, in case of the fuel failure during the transient, by a radiation monitor located outside the reactor. When the fuel failure occurs, the released FP flows out from the capsule through the dilution tube. The dilution tube is designed to minimize the released FP that can be detected by the radiation monitor located outside the reactor. This report summarized the measurement results of the dilution tube installed in the boiling water capsule.
Mori, Yuichiro*; Ide, Hiroshi; Nabeya, Hideaki; Tsukada, Takashi
JAERI-Tech 2002-003, 32 Pages, 2002/02
JAERI-Tech-2002-003.pdf:2.24MB
In relation to the aging of Light Water Reactor (LWR), the Irradiation Assisted Stress Corrosion Cracking (IASCC) has been regarded as a significant and urgent issue for the reliability of in-core components of LWR, and the irradiation research on the IASCC is now under schedule. With the progress of the irradiation research on reactor materials, well-controlled environment conditions during irradiation testing are required. Especially for irradiation testing of IASCC studies, water chemistry control is essential in addition to the control of neutron fluence and irradiation temperature.According to these requirements, at the Japan Atomic Energy Research Institute (JAERI), an irradiation testing facility that simulates in-core environment of Boiling Water Reactor (BWR) has been designed to be installed in the Japan Materials Testing Reactor (JMTR). This facility is composed of the Saturated Temperature Capsules (SATCAP) that are installed into the JMTR's core to irradiate material specimens, the Water Control Unit that is able to supply high-temperature and high-pressure chemical controlled water to SATCAP, and other components.This report describes the design study of water chemistry control system of the Water Control Unit. The design work has been performed in the fiscal year 1999.
Kanno, Masaru; Nabeya, Hideaki; Mori, Yuichiro*; Matsui, Yoshinori; Tobita, Masahiro*; Ide, Hiroshi; Itabashi, Yukio; Komori, Yoshihiro; Tsukada, Takashi; Tsuji, Hirokazu
JAERI-Tech 2001-080, 57 Pages, 2001/12
JAERI-Tech-2001-080.pdf:2.34MB
no abstracts in English
Mori, Yuichiro*; Hanawa, Satoshi; Sato, Tomonori; Ogiyanagi, Jin; Nabeya, Hideaki; Uchida, Shunsuke*
no journal, ,
no abstracts in English
Sato, Tomonori; Hanawa, Satoshi; Uchida, Shunsuke; Ogiyanagi, Jin; Nabeya, Hideaki; Miwa, Yukio; Kaji, Yoshiyuki; Nemoto, Yoshiyuki; Tsukada, Takashi
no journal, ,
To evaluate IASCC, the crack initiation and propagation tests under irradiation conditions have been carried out by using the in-pile loop installed at the Japan Material Testing Reactor (JMTR) of JAEA. In order to evaluate corrosive conditions, a water radiolysis model has been developed. In order to evaluate concentrations of chemical species not only in the test region but also along the sampling line, the model has to cover wide temperature range from room temperature to 288 
C. The dissolved O
, H and HO in sampled water was measured. The conclusions are summarized as follows; (1) The calculated O, H and HO concentrations comparatively agreed with measured values. (2) Decomposition of HO generated OH radicals, which contributed to recombination of HO and H. (3) The applicability and accuracy of the WRAC-JM to estimation of the water chemistry in the in-pile loop had been confirmed.
Matsui, Yoshinori; Nabeya, Hideaki; Kusunoki, Tsuyoshi; Takahashi, Hiroyuki; Aizawa, Masao; Nakata, Masahito; Numata, Masami; Usami, Koji; Endo, Shinya; Ito, Kazuhiro; et al.
no journal, ,
We are proceeding with the study of "R&D Project on Irradiation Damage Management Technology for Structural Materials of Long-life Nuclear Plant". For the study, it is important that the irradiated specimens are gotten by the coupling of JRR-3 and JOYO. This reports the total irradiation plan in the study, and the executed work for the coupling irradiation (JRR-3 and JOYO) including the Hot facilities work of Tokai and Oarai in the 2006 fiscal year.