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Umeda, Hisao;
PNC TN9410 93-156, 147 Pages, 1993/06
(1)[0BJECT] The object of this test is to obtain structural failure data of a typical structural model representing FBR components subjected to thermal loadings in order to develop more rationalized structural strength evaluation methods. This report provides the experimental results. (2)[TEST MODEL] The Welded Vessel Model has noteworthy typical shapes and stress distributions as can be found in the structural design of Large Type Fast Breeder Reactor, and the modified austenitic stainless steel, SUS316FR, which is hopeful for LFBR is incorporated. (3)[THERMAL TRANSIENT TEST CONDITION] Thermal creep-fatigue test was conducted with the Thermal Transient Test Facility for Structures (TTS). The test model was subjected to cyclic thermal transient of 250 
C - 600 C by sodium. The cycle time of one thermal transient was 3 hrs, in which 250C sodium flowed into the model for 1 hr and 600 C sodium for 2 hrs. The thermal transient was as severe as the by temperature change rate of 40 C/sec. (4)[TEST RESULTS] The Thermal Transient Test was completed at 1055 cycle due to crack observation on the upper Y-junction. (5)[TEMPERATURE TRANSIENT] The temperature data was obtained which was necessitated for the subsequest thermal stress analysis. The observed temperature transients were steeper than analyses. (6)[CRACK OBSERVASION] Observation method with use of "STRAW SCOPE" during the test was effective for identification of crack initiation.
Umeda, Hisao; Tanaka, Nobuyuki; Watashi, Katsumi; Kikuchi, Masayuki; Iwata, Koji
Nuclear Engineering and Design, 140, p.349 - 372, 1993/06
None
; Umeda, Hisao; ; ;
PNC TN9410 92-116, 174 Pages, 1992/01
The design and fabrication of the Filletted vessel Thermal Bending Model which is to be tested at TTS are described in this report. The objective of this model is to obtain the thermal transient strength of biaxial stress condition, which appears at Y-piece structures or the portions in the vicinity of sodium surface, and fillet welding which are noteworthy portions from the structural integrity viewpoint of Fast Breeder Reactor (FBR) components. As the testing portion, this model has three kinds of skirt structure, a thick walled cylinder and four stabilizer plates which are attatched on inner shell by fillet welding. The objective of the skirt structures and the thick walled cylinder is to investigate the relations between stress ratio, hoop and axial stress, and thermal transient strength, and they are designed in order to have same maximum principal stress range and large variation in the ratio of hoop to axial stress. The model has a straw-bag-like body which constituted with filleted cylinders, a thick walled cylinder and upper/lower trisphere dished plate. The model is supported with support cone at lower trisphere dished plate. The model has inner shell which strive for sodium flow stability.
Umeda, Hisao; ; ;
PNC TN9410 91-253, 221 Pages, 1991/01
The objective of this test is to obtain structural failure data of a typical structural model represening FBR components subjected to thermal loadings, and thereby to develope structural strength evaluation methods. This report provides the test results and crack observasion on the Stress Mitigation Structure Model(2). Thermal creep-fatigue test was conducted with the Thermal transient Test Facility for Structures(TTS). The test was successfuly performed, and we observed creep-fatigue cracks at all expected portions. The flow straightner which is a tested portion for confirmation of function appeared to be safety. Cracks were found on the surfaces of perforated plate and also inside of the tube-to-perforated plate weldments. There was no corrosion althogh sodium adhered to the joining face. The Performance of a thermal insulator could not be confirmed because sodium flowed inside it. The ultrasonic examination before inspection was effective for fine cracks even though it was impossible to catch exact depth. The temperature data and creep-fatigue cracks, that can be utilized to develop the design methods of the FBR components, could be obtained.
Tanaka, Nobuyuki; Watashi, Katsumi; Umeda, Hisao; Kikuchi, Masayuki; Iwata, Koji
Int Symp on Structral Mechanics in Reactor Technology, ,
None
Yamamoto, Takashi; Onoda, Shinobu; Oshima, Takeshi; Naydenov, B.*; Dolde, F.*; Fedder, H.*; Honert, J.*; Jelezko, F.*; Wrachtrup, J.*; Teraji, Tokuyuki*; et al.
no journal, ,
no abstracts in English
Onoda, Shinobu; Yamamoto, Takashi; Abe, Hiroshi; Hanaya, Hiroaki; Oshima, Takeshi; Taniguchi, Takashi*; Teraji, Tokuyuki*; Watanabe, Kenji*; Koizumi, Satoshi*; Kanda, Hisao*; et al.
no journal, ,
no abstracts in English
Nakamura, Hironobu; Kuribayashi, Toshihiro; Umeda, Hisao; Yaegashi, Masahiro
no journal, ,
In the activity to understand the nuclear security in the testing research reactor, we conduct a presentation in the international regional workshop conducting by the IAEA. In the presentation, as the efforts by the operator in the testing research reactor, we report organization of testing research reactor in JAEA, strategic physical protection measures (no including detail of measures), information control, efforts of insider threat measures (trustworthiness program and cyber security, etc.) and activity of nuclear security culture ferment. In addition, as the role to keep the nuclear security appropriately, we explain the important points to conduct nuclear security, establishment of comprehensive nuclear security system and improvement of responce skills by training, in the operator's point of view.
