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Yuguchi, Takashi*; Ogita, Yasuhiro; Kato, Takenori*; Yokota, Rintaro*; Sasao, Eiji; Nishiyama, Tadao*
Journal of Asian Earth Sciences, 192, p.104289_1 - 104289_16, 2020/05
Times Cited Count：5 Percentile：31.49(Geosciences, Multidisciplinary)Quartz from a granitic pluton is found to have formed through sequential growth events under different mechanisms and crystallization temperatures, which can provide new insights into magmatic processes of granitic magmas that were eventually consolidified into plutons. The events were identified using (1) the description of crystal shape and occurrence, (2) the study of the internal structure with cathodoluminescence (CL), and (3) derivation of the crystallization temperatures based on TitaniQ thermometry. The magmatic quartz crystals from the Toki granite, central Japan, are characterized as having the following internal structures: oscillatory zonation, no-oscillatory zonation with luminescence graduation (gradational zonation), and heterogeneous CL. The quartz crystals with oscillatory zonation were formed in the temperature range of about 800 
C to below 700 C, which is referred to as oscillatory zoning temperature (OZT) conditions. The CL zonation pattern was controlled by the temperature conditions and titanium diffusivity in the melt (magma). The crystallization process of quartz within the Toki granite reveals the cooling processes of the granitic pluton; the lithofacies with a high frequency of oscillatory-zoned quartz underwent slower cooling under the OZT conditions than those in other lithofacies.
Hamamoto, Shimpei; Tochio, Daisuke; Ishii, Toshiaki; Sawahata, Hiroaki
Nihon Genshiryoku Gakkai Wabun Rombunshi, 16(4), p.169 - 172, 2017/12
A melt wire was installed at the tip of the control rod in order to measure the temperature of High Temperature engineering Test Reactor (HTTR). After experience with reactor scrum from the state of reactor power 100%, the melt wire was taken out from the control rod and appearance has been observed visually. It was confirmed that the melt wires with a melting point of 505 C or less were melted, and the melt wires with a melting point of 651 C or more were not melted. Therefore, it was found that the highest arrival temperature of tip of the control rods where the melt wires are installed reaches within the range of 505 to 651 C. And it was found that the control rod temperature at the time of reactor scram does not exceed the using temperature criteria (900 C) of Alloy 800H of the control rod sleeve.
Lee, S.; Kondoh, Takashi; Yoshino, Ryuji; Cho, T.*; Hirata, Mafumi*; Miura, Yukitoshi
Transactions of Fusion Technology, 39(1T), p.151 - 154, 2001/01
no abstracts in English
Inagaki, Terumi*; Ishii, Toshimitsu
Infrared Physics & Technology, 41(6), p.325 - 337, 2000/12
Times Cited Count：21 Percentile：72.65(Instruments & Instrumentation)no abstracts in English
Kondoh, Takashi
Purazuma, Kaku Yugo Gakkai-Shi, 76(9), P. 888, 2000/09
no abstracts in English
*
JNC TN1400 2000-007, 100 Pages, 2000/07
JNC-TN1400-2000-007.pdf:4.67MB
no abstracts in English
Hayakawa, Shigeo*; Harada, Kengo*; Arakawa, Kazuo; Morishita, Norio
Journal of Chemical Physics, 112(19), p.8432 - 8435, 2000/05
Times Cited Count：19 Percentile：50.78(Chemistry, Physical)no abstracts in English
; *; Tokizawa, Takayuki; *
JNC TY6400 2000-013, 102 Pages, 2000/02
JNC-TY6400-2000-013.pdf:2.45MB
None
J.S.Koog*; Sakasai, Akira; Koide, Yoshihiko; Shirai, Hiroshi; Kamada, Yutaka; Fukuda, Takeshi; Yoshino, Ryuji; JT-60 Team
Review of Scientific Instruments, 70(1), p.372 - 374, 1999/01
Times Cited Count：3 Percentile：33.24(Instruments & Instrumentation)no abstracts in English
Inagaki, Terumi*; Ishii, Toshimitsu; Okamoto, Yoshizo*
Hihakai Kensa, 48(10), p.673 - 681, 1999/00
no abstracts in English
; *; Miyakawa, Shunichi; *;
PNC TN9410 98-035, 60 Pages, 1998/03
This report describes the development activities for the fabrication of the Thermal Expansion Difference irradiation temperature monitor (TED) at the Oarai Engineering Center (OEC)/PNC. TED is used for various irradiation tests in the experimental fast reactor JOYO. TED is the most accurate off-line temperature monitor used for irradiation examination. The TED is composed of a metallic sphere lid and either a stainless steel or nickel alloy container. Once the container is filled with sodium, the metallic sphere lid is sealed by using a resistance weld. This capsule is then loaded into a reactor. Once a TED is loaded into the JOYO reactor, the sodium inside the metallic container increases as a result of thermal expansion. The TED identifies the peak irradiation temperature of the reactor based on a formula correlating temperature to increment values. This formula is established specifically for the particular TED being used during a calibration process performed when the TED is fabricated. Initially the TED was developed by Argonne National Laboratory (ANL) in the United States, and was imported by PNC for use in the JOYO reactor. In 1992 PNC decided to fabricate TED domestically in order to ensure the stability of future supplies. Based on technical information provided by ANL, PNC began fabrication of a TED on an experimental basis. In addition, PNC endeavored to make the domestically produced TED more efficient. This involved improving the techniques used in the sodium filling and the metallic sphere welding processes. These quality control efforts led to PNC's development of processes enabling the capsules to be filled with sodium to nearly 100%. As a result, the accuracy of the temperature dispersion in the out-pile calibration test was improved from 
10C to 5. In 1996 the new domestically fabricated TED was attached to a JOYO irradiation rig. In March of 1997, irradiation of the rig was started on the 30th duty cycle operation, .
Hiranai, Shinichi; Yokokura, Kenji; Moriyama, Shinichi; *; *; Fujii, Tsuneyuki
JAERI-Tech 98-006, 27 Pages, 1998/03
no abstracts in English
; Eto, Motokuni; Akiba, Masato; Inagaki, Terumi*; Okamoto, Yoshizo*
Kashika Joho Gakkai-Shi, 18(67), p.36 - 42, 1997/10
no abstracts in English
*; Akino, Norio; *
Nihon Kikai Gakkai Rombunshu, B, 63(611), p.220 - 223, 1997/07
no abstracts in English
*; Akino, Norio; *
Nihon Kikai Gakkai Rombunshu, B, 63(611), p.213 - 219, 1997/07
no abstracts in English
Isozaki, Kazunori;
PNC TN9410 97-062, 169 Pages, 1997/05
Sodium leak accident of MONJU was caused high cycles fatigue damage of thermometer well by flow-induced vibration. It was due to the sy㎜etric vortex shedding which was occurred rear flow of thermometer well. So, Thermometer wells installed in primary and secondary heat transport systems of JOYO were evaluated of flow-induced vibration. Evaluation of flow-induced vibration of thermometer well was done checking of flow-induced vibration base on authorized design report for JOYO, evaluation of summary flow-induced vibration by natural frequency of thermometer well in sodium as cantilever models, and evaluation based on small velocity rule of ASME Code Section III Appendix N-1300. By this result, thermometer wells (12B piping of secondary cooling system) were not sattisfied requirement to avoid flow-induced vibration by small velocity rule. Therfore, Detailed vibration characteristic analysis, water flow-induced vibration test, dumping test and evaluation of structural integrity were carried out. These results, vibration amplitude of well on the tip was 0.13mm (vibration non-dimensional amplitude of 0.015) and peak stress of 2.9kg/mm
is occurred. Thermometer wells (12B piping of secondary cooling system) which occurred peak stress by flow vibration was confirmed enough to satisfy 5.3kg/mm2 of design fatigue limit.
Iwata, Koji; *; *; *; *; *; *
PNC TN9410 97-042, 8 Pages, 1997/03
A design guide for flow-induced vibration of thermometer wells is proposed to prevent the recurrence of the failure of thermometer wells, which was the direct cause of the 1995 sodium leak incident of the secondary main piping of the prototype fast breeder reactor MONJU. As a supplement to the technical standards in force for MONJU, the design guide specifies the methods of evaluation and the design criteria on structural integrity against flow-induced vibration for thermometer wells, which are inserted into pipes of fast breeder reactors. The design guide is a PNC's (Power Reactor and Nuclear Fuel Development Corporation) internal guide for MONJU, which is to be used, with the permission of outside authorities, to confirm the integrity of the existing equipments as well as to make an improved design of thermometer wells. The proposed design guide was prepared by the Special Working Group on Thermometer Design Guide, organized in PNC during the period from May to November, 1996.
Kawada, Koji; Ohno, Shuji; Miyake, Osamu; ; ; Tanabe, Hiromi
PNC TN9410 97-036, 243 Pages, 1997/01
As a part of the work for investigating the sodium leak accident which occurred in Monju on December 8, 1995, three tests, (1)sodium leak test, (2)sodium leak and fire test-I, and (3)sodium leak and fire test-II, were carried out at OEC/PNC. Main objectives of these tests are to confirm leak and burning behavior of sodium from the damaged thermometer, and effects of the sodium fire on integrity of the surrounding structure, etc. This report describes the result of the sodium fire test-I carried out as a preliminary test. The test was performed using SOLFA-2 (Sodium Leak, Fire and Aerosol) facility on April 8, 1996. In this test, sodium heated to 480C was leaked for approximately 1.5 hours from a leak simulated apparatus and caused to drop onto a ventilation duct and a grating with the same dimensions and layout as those in Monju. The main conclusions obtained from the test are shown as below. (1)Observation from video cameras in the test revealed that in early stages of sodium leak, sodium dropped down out of the flexible tube of thermometer in drips. This dripping and burning were expanded in range as sodium splashed on the duct. (2)No damage to the duct itself was detected. However, the aluminum louver frame of the ventilation duct's lower inlet was damaged: Its machine screws had come off, leaving half of the grill (on the grating side) detached. (3)No large hole, like one seen at Monju, were found when the grating was removed from the testing system for inspection, although the area centered on the point that the sodium attacked was damaged in a way indicating the first stages of grating failure: The 5-mm- square lattice was corroded through in some parts, and many blades (originally 3.2 mm thick) had become like the blade of a sharp knife. (4)The burning pan underside thermocouple near the leak point measured 700C in roughly 10 minutes, and for the next hour remained stable between 740C and 770C. There was a ...
