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Journal Articles

Seismic capacity evaluation of a group of vertical U-tube heat exchanger with support frames for seismic PSA

Watanabe, Yuichi*; Muramatsu, Ken; Oikawa, Tetsukuni

Nuclear Engineering and Design, 235(23), p.2495 - 2512, 2005/12

 Times Cited Count:2 Percentile:80.93(Nuclear Science & Technology)

This paper presents an evaluation of seismic capacity of a group of vertical U-tube type heat exchangers(HXs) with support frames for residual heat removal systems of BWRs for seismic Probabilistic Safety Assessment in Japan. The median capacity was evaluated by a time history response analysis with a detailed model for a representative HX selected from four HXs. The logarithmic standard deviation(LSD) for uncertainty due to lack of knowledge was evaluated with consideration of the variabilities in three influential parameters, i.e., diameter of anchor bolt, weight of HX and position of center of gravity of HX. The dominant failure mode of HXs was the failure of anchor bolts of lugs mainly due to shearing stress. The capacity expressed in terms of zero period acceleration on the foundation of HX was evaluated to be 4,180 Gal(4.3 g) for median, LSD for uncertainty due to randomness was 0.11 from the variability in material property and LSD due to lack of knowledge was 0.21 to 0.53 depending on combination of the variability in design parameters to be considered.

JAEA Reports

Management techniques of the JRR-4 heat exchanger

Horiguchi, Hironori; Oyama, Koji; Ishikuro, Yasuhiro; Hirane, Nobuhiko; Ito, Kazuhiro; Kameyama, Iwao

JAERI-Tech 2005-001, 38 Pages, 2005/02

JAERI-Tech-2005-001.pdf:2.79MB

After JRR-4 heat exchanger was renewed in made of stainless steel from carbon steel, it was examined how to manage the heat exchanger. The main subject is the cleaning technology of the heat exchanger. The recovery of old heat exchanger cooling performance has been by only chemical cleaning. Now we use chemical and dry cleaning as a new technique. It helps prevent of corrosions of secondary pipes and reduce of management costs. This report describes the performance management and cleaning technology of the JRR-4 heat exchanger and the management of the JRR-4 coolant.

Journal Articles

Mechanical properties on multi stage blazed fin body with ultra fine off-set fin for compact heat exchager at Elevated Temperature

Ishiyama, Shintaro

Nippon Kinzoku Gakkai-Shi, 68(7), p.490 - 497, 2004/07

 Times Cited Count:0 Percentile:100(Metallurgy & Metallurgical Engineering)

SUS304 multi stage blazed fin core body for GTHTR300 was tested its high temperature strength, fatigue and creep and it was found that the body behaves as same strength of SUS304 material.

Journal Articles

Study of power conversion unit design of Gas Turbine High Temperature Reactor (GTHTR300)

Takada, Shoji; Takizuka, Takakazu; Kunitomi, Kazuhiko; Yan, X.; Minatsuki, Isao*

Dai-31-Kai Gasu Tabin Teiki Koenkai Rombunshu, p.55 - 60, 2003/06

no abstracts in English

Journal Articles

Stress analysis of plate-fin type heat exchanger

Matsui, Shingo*; Muto, Yasushi*; Shiina, Yasuaki

Nippon Genshiryoku Gakkai Wabun Rombunshi, 2(2), p.175 - 186, 2003/06

no abstracts in English

Journal Articles

High temperature mechanical properties on multi stage blazed fin body with ultra fine off-set fin for compact heat exchanger

Ishiyama, Shintaro; Muto, Yasushi

Nippon Kikai Gakkai Rombunshu, A, 69(679), p.682 - 688, 2003/03

no abstracts in English

Journal Articles

Design study of power conversion system for the Gas Turbine High Temperature Reactor (GTHTR300)

Takada, Shoji; Takizuka, Takakazu; Kunitomi, Kazuhiko; Yan, X.; Katanishi, Shoji; Kosugiyama, Shinichi; Minatsuki, Isao*; Miyoshi, Yasuyuki*

Nippon Genshiryoku Gakkai Wabun Rombunshi, 1(4), p.341 - 351, 2002/12

no abstracts in English

Journal Articles

Heat transfer characteristics of a steam reformer inserted metallic wire

Takeda, Tetsuaki

Nippon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.199 - 202, 2002/00

There are several methods for enhancement of heat transfer such as attaching various type fins on a channel surface of a heat exchanger tube and a steam reforming tube. The objective of this study is to clarify characteristics of heat transfer and pressure drop in the channel inserted metallic wire with high porosity. A heat transfer experiment was performed using a horizontal circular tube to obtain the heat transfer characteristics of the channel inserted copper wire. From the results obtained in this experiment, it seems to be probable that an enhancement of heat transfer method using metallic wire inserts is further improved under the high temperature conditions in efficiency as compared with the other methods.

Journal Articles

Design of power conversion system of Gas Turbine High Temperature Reactor (GTGTR300)

Takada, Shoji; Takizuka, Takakazu; Kunitomi, Kazuhiko; Yan, X.; Katanishi, Shoji; Kosugiyama, Shinichi; Shiozawa, Shusaku

Nippon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.189 - 192, 2002/00

no abstracts in English

Journal Articles

The Effect of unbalance flow on the performance of compact heat exchanger for HTGR-GT system

Ishiyama, Shintaro; Muto, Yasushi; Ogata, Hiroshi*; Yamada, Seiya*

Nippon Genshiryoku Gakkai-Shi, 43(11), p.1136 - 1148, 2001/11

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of the compact heat exchanger for HTGR, 1; Fabrication of the ultra fine off-set fin

Ishiyama, Shintaro; Muto, Yasushi; Tanihira, Masanori*; Ogata, Kan*; Kamito, Yoshimi*; Igari, Toshihide*

Nippon Genshiryoku Gakkai-Shi, 43(6), p.603 - 611, 2001/06

 Times Cited Count:5 Percentile:64.97(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Computer simulation analysis on the machinability of alumina dispersion enforced copper alloy for high performance compact heat exchanger

Ishiyama, Shintaro; Muto, Yasushi; Nishii, Takashi*; Kasaba, Michihiro*

Nippon Kinzoku Gakkai-Shi, 65(6), p.524 - 533, 2001/06

no abstracts in English

JAEA Reports

Stress analysis of plate-fin structures in recuperator

Matsui, Shingo*; Muto, Yasushi; Shiina, Yasuaki

JAERI-Tech 2000-083, 107 Pages, 2001/01

JAERI-Tech-2000-083.pdf:3.46MB

no abstracts in English

Journal Articles

Technical issues and their solutions in HTGR gas turbine system

Muto, Yasushi; Ishiyama, Shintaro

Nippon Genshiryoku Gakkai-Shi, 42(10), p.1020 - 1027, 2000/10

 Times Cited Count:1 Percentile:87.37(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

None

Okamoto, Koji*; *

JNC-TY9400 2000-016, 90 Pages, 2000/06

JNC-TY9400-2000-016.pdf:2.53MB

no abstracts in English

JAEA Reports

JOYO MK-II core plant characteristics test data

JNC-TN9410 2000-010, 72 Pages, 2000/03

JNC-TN9410-2000-010.pdf:2.14MB

The experimental fast reactor JOYO served as the MK-II irradiation bed core for testing fuel and material for FBR development for 16 years from 1982 to 1997. During the MK-II core operation, extensive data were accumulated from the plant characteristic tests. Tests conducted at JOYO included operating characteristic tests for confirming operational safety, performance tests for confirming design performance of the MK-II core, and special tests for research and development ofthe plant. In this report, the outline and the results of each test item are shown. These test data can be provided by the magnet-optical disk.

JAEA Reports

JOYO coolant sodium and cover gas purity control database (MK-II core)

; ; Saikawa, Takuya*; Sukegawa, Kazuya*

JNC-TN9410 2000-008, 66 Pages, 2000/03

JNC-TN9410-2000-008.pdf:1.39MB

The experimental fast reactor "JOYO" served as the MK-II irradiation bed core for testing fuel and material for FBR development for 15 years from 1982 to 1997. During the MK-II operation, impurities concentrations in the sodium and the argon gas were determined by 67 samples of primary sodium, 81 samples of secondary sodium, 75 samples of primary argon gas, 89 samples of secondary argon gas (the overflow tank) and 89 samples of secondary argon gas (the dump tank). The sodium and the argon gas purity control data were accumulated from in thirty-one duty operations, thirteen special test operations and eight annual inspections. These purity control results and related plant data were compiled into database, which were recorded on CD-ROM for user convenience. Purity control data include concentration of oxygen, carbon, hydrogen, nitrogen, chlorine, iron, nickel and chromium in sodium, concentration of oxygen, hydrogen, nitrogen, carbon monoxide, carbon dioxide, methane and helium in argon gas with the reactor condition.

JAEA Reports

Study on sodium coolant loop-type reactor; Parametric study on maximum thermal stress depending on routing dimension of piping system

Tsukimori, Kazuyuki; Furuhashi, Ichiro*

JNC-TN9400 2000-049, 93 Pages, 2000/03

JNC-TN9400-2000-049.pdf:2.82MB

lt is one of the important key points to reduce thermal stress of the primary piping system in the design of sodium coolant loop-type FBR plants. The objectives of this study are to understand the characteristics of the thermal stresses in the simple S-shaped hot leg piping systems which run from the outlet nozzle of the reactor vessel (R/V) to the inlet nozzle of the intermediate heat exchanger (IHX), and to propose some recommendable routings of piping systems. Results are summarized as follows. (1)Generally, the thermal stresses in elbows are severer than those at nozzles. The tendency was observed that the stress in elbow decreases with the increase of the distance between the outlet nozzle of R/V and the inlet nozzle of IHX and also the distance between the outlet nozzle of R/V and the liquid surface level. (2)lt is expected to reduce thermal stresses in elbow to big extent by adopting super 90 degree elbows. Therefore, in these cases the dimension region which satisfies the allowable stress is broad compared with that in the case of the conventional 90 degree elbow. (3)The stress estimations in elbow based on 'MITl notice No.501' become excessively large compared with the results by FEA using shell elements, when the maximum stress occurs at the end of elbow. ln these cases, the estimation can be rationalized by replacing the maximum stress by the mean of stresses at the end and at the middle of the elbow. (4)Two routings with 105 degree elbows are recommended. 0ne has the advantage from the view point of reduction of length of pipe and the other does from the view point of reduction of thermal stresses, compared with the routing with 90 degree elbows.

Journal Articles

Feasibility design study of compact heat exchanger for HTGR gas turbine systems

Ishiyama, Shintaro; Muto, Yasushi; Kasaba, Michihiro*; Kaneta, Takayoshi*

Nippon Genshiryoku Gakkai-Shi, 42(3), p.196 - 203, 2000/03

 Times Cited Count:1 Percentile:87.37(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of HTGR-GT power generation system, 1; Development status in Japan

; Miyamoto, Yoshiaki; Tanaka, Toshiyuki

Karyoku Genshiryoku Hatsuden, 50(9), p.1123 - 1130, 1999/09

no abstracts in English

68 (Records 1-20 displayed on this page)