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Journal Articles

Anharmonic Pr guest modes in Pr(Os$$_{1-x}$$Ru$$_x$$)$$_4$$Sb$$_{12}$$ investigated by inelastic X-ray scattering

Tsutsui, Satoshi; Kaneko, Koji; Miyazaki, Ryoichi*; Higashinaka, Ryuji*; Aoki, Yuji*; Kobayashi, Riki*; Wakimoto, Shuichi; Baron, A. Q. R.*; Sugawara, Hitoshi*; Sato, Hideyuki*

JPS Conference Proceedings (Internet), 3, p.011060_1 - 011060_5, 2014/06

Journal Articles

Quantitative analysis of cisplatin sensitivity of human esophageal squamous cancer cell lines using in-air micro-PIXE

Tanaka, Naritake*; Kimura, Hitoshi*; Faried, A.*; Sakai, Makoto*; Sano, Takaaki*; Inose, Takanori*; Soda, Makoto*; Okada, Koji*; Nakajima, Masanobu*; Miyazaki, Tatsuya*; et al.

Cancer Science, 101(6), p.1487 - 1492, 2010/06

 Times Cited Count:12 Percentile:31.84(Oncology)

We examined the intracellular localization of cisplatin, a key chemotherapeutic agent, in esophageal cancer cell lines and determined their sensitivity to cisplatin using in-air micro-PIXE. Two human esophageal squamous cell carcinoma (ESCC) cell lines, TE-2 and TE-13, were examined for their response to cisplatin using MTT assay, flow cytometry and DNA fragmentation assays. Real-time reverse transcription-polymerase chain reaction was also used to evaluate the mRNA expression of multidrug resistance protein 2 (MRP2) in both cell lines. Platinum localizations of intracellular and intranuclear were measured using in-air micro-PIXE. TE-2 cells were more sensitive to cisplatin than TE-13 cells. The results of this study suggest that in-air micro-PIXE could be a useful quantitative method for evaluating the cisplatin sensitivity of individual cells. Finally, we speculate that MRP2 in the cell membrane may play an important role in regulating cisplatin sensitivity of ESCC cells.

Journal Articles

Precise intensity measurements in the $$^{14}$$N(n,$$gamma$$)$$^{15}$$N reaction as a $$gamma$$-ray intensity standard up to 11 MeV

Miyazaki, Itaru*; Sakane, Hitoshi*; Takayama, Hirokazu*; Kasaishi, Masafumi*; Tojo, Akinori*; Furuta, Masataka*; Hayashi, Hiroaki*; Suematsu, Osamu*; Narasaki, Hiromichi*; Shimizu, Toshiaki*; et al.

Journal of Nuclear Science and Technology, 45(6), p.481 - 486, 2008/06

 Times Cited Count:5 Percentile:35.13(Nuclear Science & Technology)

The intensities of the prompt $$gamma$$ rays from the $$^{14}$$N(n,$$gamma$$)$$^{15}$$N reaction have been precisely measured. As the samples, a liquid nitrogen target and a deuterated melamine (C$$_{3}$$D$$_{6}$$N$$_{6}$$) were used. The previous values widely used as intensity standards agreed with those obtained in this study within 4-5% in the 2-11 MeV region, however, showed a monotonous decrease with the increase of $$gamma$$-ray energy.

Journal Articles

Radioactive waste management in O-arai Research and Development Center

Maeda, Atsushi; Kowata, Koichi; Yamazaki, Yasuo; Takahashi, Kozo; Okubo, Toshiyuki; Miyazaki, Hitoshi

Dekomisshoningu Giho, (33), p.58 - 66, 2006/03

By the Japan Atomic Energy Agency (JAEA), designed decommissioning of nuclear facility and the treatment and disposal of radioactive waste will be carried out systematically and efficiently as responsibility as the installer of the nuclear power facility and generator of radioactive waste. This paper shows the present status of radioactive waste management in O-arai Research and Development Center, one of the research and development bases of JAEA. The management of low-level radioactive waste, including those accepted from outside operator of O-arai district, is carried out by the major premise of ensuring safety at O-arai Waste Management Facility. Treatment related to volume reduction and stabilization by means such as incineration and compression of solid waste, and solidification of liquid, as well as waste storage management is steadfastly promoted, so that these substances may be adequately stored and managed until they are disposed of.

JAEA Reports

Measurements of Prompt Gamma-Ray Emission Probabilities for Determinations of Neutron Capture Cross Sections of Long Life Nuclides

Miyazaki, Itaru*; Shimizu, Toshiaki*; Shibata, Michihiro*; Kawade, Kiyoshi*; Furutaka, Kazuyoshi; Nakamura, Shoji; Sakane, Hitoshi

JNC TY8400 2005-002, 40 Pages, 2005/06

JNC-TY8400-2005-002.pdf:2.69MB

Accurate cross section data for the neutron capture of long-lived fission products (LLFP) are needed for developing a nuclear transmutation technology which reduces radioactive wastes by transmuting nuclides that have half-lives of as long as a few million years to other nuclides that have much shorter half-lives. There are some nuclides, whose cross sections cannot be measured in activation method. Utilization of prompt gamma-rays is expected to solve this problem. The aim of present study was twofold: (i) to measure emission probabilities of the high energy gamma-ray, up to 10MeV, emitted from$$^{14}$$N(n, gamma)$$^{15}$$N reaction, which are usually used as standards, in order to improve their accuracies and (ii) to develop a measurement method for neutron capture cross sections by using prompt gamma-rays. Emission probabilities of principal prompt gamma-rays from$$^{14}$$N(n, gamma)$$^{15}$$N reaction were determined with 0.2-0.9% errors. For ten nuclides,$$^{23}$$Na,$$^{27}$$Al,$$^{51V,sup}$$55 Mn,$$^{64}$$Ni,$$^{65}$$Cu,$$^{141}$$Pr,$$^{186}$$W, and$$^{197Au,}$$capture cross sections were measured by using prompt gamma-rays and gamma-rays following b-decay. By comparing both cross section values, it was found that emission probabilities of prompt gamma-rays reported in the literatures were systematically larger than those inferred from the cross sections that were determined in activation methods. The cross section of a$$^{104}$$Pd (n, gamma)$$^{105}$$Pd reaction at thermal energy was measured. Considering transmutation of the nuclide, the cross section of$$^{104}$$Pd(n, gamma), which is an isotope of palladium, is also necessary. A lower limit of the cross section was determined with 6% accuracy. Additionally, a method of estimating an upper limit was examined by noting similarity of nuclear structures to the neighboring nuclides. It was estimated that the observed lower limit of emission probabilities correspond to 79% of the cross section.

JAEA Reports

Development of decommissioning management system (10); Improvement of evaluation accuracy and simplification of input work

Kondo, Hitoshi; Miyazaki, Hitoshi*; Okubo, Toshiyuki

JNC TN9410 2005-009, 32 Pages, 2005/03

JNC-TN9410-2005-009.pdf:4.62MB

When the plan of Decommissioning such as nuclear fuel cycle facilities and small-scale research reactor is settled on, it is necessary to optimize the index concerning the decommissioning (such as the cost, the waste and the term of works. etc) by selecting the technology and the process appropriately. In Waste Management section, the development of the Decommissioning Management System (DECMAN) which can calculate these decommissioning indexes from the facilities data and the dismantlement technique automatically is advanced. This report describes the problem found in 2003 and the solution concerning the operation and the evaluation technique.

JAEA Reports

None

Wada, Yusaku; Okubo, Toshiyuki; Miyazaki, Hitoshi; none; Donomae, Yasushi

JNC TN9410 2005-007, 94 Pages, 2005/03

JNC-TN9410-2005-007.pdf:6.07MB

None

JAEA Reports

The performance tests used the water scrubber for ruthenium rejection

; ; ; Miyazaki, Hitoshi

JNC TN9410 2002-014, 120 Pages, 2002/11

JNC-TN9410-2002-014.pdf:5.97MB

LEDF (Large Equipment Dismantling Facility) will be constructed for the purpose of decontaminating the high level $alpha solid waste generated in oarai engineering center of JNC. And, main processing process of LEDF is incineration and melting system. LEDF will be intended to reduce the secondary waste that occurs along with the operation of the off gas processing equipment of incineration and melting system. It assumed that we are able to eliminate the adsorption tower using silica gel, if the decontamination factor to volatile ruthenium is able to expect in the packed scrubber that is established to remove harmful gas. Thereupon, we carried out this tests that eliminates the adsorption tower and reduces the secondary waste. The decontamination factor (DF) to the volatile ruthenium by the water scrubber is confirmed in the established institution which is in Tokai Works. However, decontamination factor differs and depends on the ruthenium concentration, harmful gas concentration, washing method and also washing condition. Also, the DF value to the volatile ruthenium in the off gas that occurs from incineration and melting system is obtained, does not exist under the same condition as LEDF. Therefore, the decontamination factor to the volatile ruthenium of the packed scrubber under the operating condition of LEDF is confirmed by this test. The main result of this study is as follows (1) In the examination of the test device specification, the packed scrubber design method was investigated. And, the test device that maintained the resemblance nature with a real machine was produced on the basis of this result. (2) In the result of the ruthenium occurrence condition confirmation test, it was confirmed that the test condition such as the kind of the oxidizer, hold temperature of the oxidization reaction container that produce volatile ruthenium continuously, (3) In the result of the occurrence temperature influence confirmation test, it was confirmed that the ...

JAEA Reports

The rationalization design of large equipment dismantling facility (LEDF); Demonstration test on extinguishing of the cell (II)

; ; Matsumoto, Yoshihiro; ; Kato, Noriyoshi; Miyazaki, Hitoshi; Tanimoto, Kenichi

JNC TN9410 2002-010, 62 Pages, 2002/11

JNC-TN9410-2002-010.pdf:2.37MB

The vaporizer in extinguishing of Large Equipment Dismantling Facility (LEDF)that cost is considering as a plan to cut down as part of a rationalization design highly. When the vaporizer is deleted, it becomes here where liquefied carbon dioxide is emitted in the direct cell, it is necessary to grasp the action and extinguishing performance of the pressure change in the cell by rapid evaporation test of the emitted liquefied carbon dioxide. So pressure action inside the fire laboratory in liquefied carbon dioxide release and a putting out the fire tests due to the combustion time of the combustible were enforced by using the general fire laboratory with Demonstration Test on Extinguishing of the cell (I) in the llth year of Heisei. However, since these tests are after laboratory without airtightness, it needs to grasp the pressure action at the time of liquefied carbon dioxide discharge under the airtight high conditions of having assumed the still more nearly actual cell. The cell (II) Demonstration Test on Extinguishing using the vessel of Sodium Leak Fire and Aerosol test rig (SOLFA-2) container inside of OEC was carried out. The results were as follows. (1)In order to grasp the pressure action of the vessel, the internal pressure of SOLFA-2 was set as -50mmH$$_{2}$$O, and emitted liquefied carbon dioxide. Consequently, the tendency for the pressure in the vessel to descend rapidly immediately after liquefied carbon dioxide discharge, and to descend gently-sloping through the process which goes up gradually after that and goes abruptly up for a short time was seen. (2)The process which goes abruptly up in an above-mentioned short time is considered to be the factors with main what some liquefied carbon dioxide emitted in the vessel changed to dry ice, and was deposited taken and sublimating surrounding heat, and evaporating again. (3)It sets to total flooding system and the average minimum temperature in the vessel becomes about -48$$^{circ}$$C, and at ...

JAEA Reports

Rationalization design on large equipment dismantling facility; The cell fire-extinguishing examination (III)

; Matsumoto, Yoshihiro; ; ; Kato, Noriyoshi; Miyazaki, Hitoshi; Tanimoto, Kenichi

JNC TN9410 2002-008, 68 Pages, 2002/07

JNC-TN9410-2002-008.pdf:2.89MB

In order to rationalize for Large Equipment Dismantling Facility (LEDF), the plan of removing vaporizer belong to Cell-fire-extinguishing-system was investigated. When a vaporizer is cut down, It is necessary to grasp a fire-extinguishing performance. The fire-extinguishing performance check examination by liquefaction carbon dioxide in the cell fire-extinguishing examination (I) was carried out in 1999 fiscal year. As the result, The good performance was obtained to polyethylene. But there was the deep-seated fire about a piece of wood. Then, The check items were carbon dioxide (CO$$_{2}$$) concentration and CO$$_{2}$$ concentration holding time for the deep-seated fire in the cell fire-extinguishing examination (III). The results were as follows; (1)By use of the combustion model in which a piece of wood and cotton were put is lit, temperature inside model, mass reduction, and combustion situation were examined. The model burned remarkably in 30$$sim$$60 min. The peak temperature rise to 680 $$^{circ}$$C(MAX), and attained smoldering after (ignition) 70 min. Moreover, in order to determine the generating conditions of a deep-seated fire, the situation of CO$$_{2}$$ extinguishing after ignition by the time lag of 50$$sim$$90 min were examined. The model around ignition 50 minutes was the most difficult to extinguish, and it turned out that they are the conditions which were most suitable for the deep-seated fire examination model of an exam. (2)In order to decide on CO$$_{2}$$ concentration and concentration holding time required for fire extinguishing of the deep-seated fire in LEDF, The fire-extinguishing performance was investigated by 40 $$sim$$ 65% of CO$$_{2}$$ concentration. Consequently, CO$$_{2}$$ concentration required for deep-seated fire extinguishing was understood that 60% or more was required when safety was taken into consideration at 50% or more. Moreover, when it was 50% or more of CO$$_{2}$$ concentration and the holding time of CO$$_{2}$$ concentration ...

JAEA Reports

The design of the hazardous substance sorting system applicability check of X-ray fluorescence spectrometer

; ; ; Kato, Noriyoshi; Miyazaki, Hitoshi; Tanimoto, Kenichi

JNC TN9410 2002-006, 49 Pages, 2002/07

JNC-TN9410-2002-006.pdf:1.84MB

Construction of LEDF (Large Equipment Dismantling Facility) is being planned by Waste Management Section. This purpose of LEDF is the melting treatment of the radioactive waste in OEC (O-arai Engineering Center) and the waste package in JAERI (O-arai Japan Atomic Energy Research Institute). It is also considered about the disposal plan of the future. Therefore LEDF has the sorting process of waste because of the removal of problematic substances. But that process is conducted using its human eyes. This process needs automatic operation because of high classification accuracy, high reliability, burden reduction of a worker. Then we select EXFS (Energy dispersive X-ray Fluorescence Spectrometer), and conducted the measurement of waste (a sample) with this device. That purpose is to confirm an application as the sorting device. A confirmation result is shown in the following. (1)Sorting performance Measurement is possible without pretreatment, if it is metal. However, sorting is difficult when paint, plating, impurities, etc. are shown in the surface. (2)Measurement position It is necessary to set a gap of the measurement thing from a measurement position to 4㎜ or less. (3)Radiation influence Because the background had risen by the influence of a radiant ray, the distinction of Fluorescence X-ray became difficult. Therefore the distinction of materials became impossible. Aluminum is influenced specially by it. As a conclusion, the application nature of EXFS thing Sorting System is high. But there is a bad influence by radiation. Therefore, difficult is installation into the cell. In order to apply EXFS to LEDF, it is necessary to place it outside the cell and to use as the help of the visual inspection.

JAEA Reports

Rationalization design on large equipment dismantling facility; The cell fire-extinguishing examination I

Donomae, Yasushi; Matsumoto, Yoshihiro; Kikuchi, Yutaka; Kato, Noriyoshi; Miyazaki, Hitoshi; Tanimoto, Kenichi

JNC TN9410 2001-021, 73 Pages, 2002/01

JNC-TN9410-2001-021.pdf:3.91MB

In order to rationalize for Large Equipment Dismantling Facility (LEDF), the plan of removing vaporizer belong to Cell-fire-extinguishing-system was investigated. In this test, in order to study the behavior of pressure in cell, when the liquefaction carbon dioxide (liq-CO$$_{2}$$) is emitted, and the performanee of extinguishing fires, the test of behavior of pressure and the extinguishing fires take effect. Also the extinguishing fires test used water-mist take effect for complement liq-CO$$_{2}$$. The results as follows; (1)In the test of behavior of pressure, Liq-CO$$_{2}$$ was emitted test room under -40mmAq negative pressure. Room pressure was increase about 0.8mmAq/sec at first. After 29sec, the pressure was increase slowly about 0.1mmAq/sec. After 120sec, the increase was drastic about 1.5mmAq/s. (2)In the test of extinguishing fires by liq-CO$$_{2}$$, under -40mmAq, Polyethylene and wooden chips + cotton (crib) was burn. Polyethylene was extinguished perfectly, but the embers remained in cribs. While the room pressure was increase about 1.3mmAq/sec for 10sec at first. After 30 sec, the pressure was increase about 1mmAq/sec. On the other hand, the drastic increase of pressure disappeared between 100sec to 120sec by change the nozzle size from 14mm$$^{2}$$ to 10mm$$^{2}$$. (3)In the test of extinguishing fires by water-mist, Cribs was extinguished perfectly, but Polyethylene was extinguished difficulty under the same condition of liq-CO$$_{2}$$ test. (4)Therefore the results, It's coped with the fire extinguishing and the keeping negative pressure for LEDF cells. Therefore nozzle size is fitted cell volume as changing 14mm$$^{2}$$ to 10mm$$^{2}$$. (5)As the performance of extinguishing fires by liq-CO$$_{2}$$, It is necessity the concentration of above 50% CO$$_{2}$$ for combustibles as cribs, remaining the embers. (6)On the other hand, It is necessity most study for the adoption of water-mist. Therefore water-mist was not effective for polyethylene, and it needed water ...

JAEA Reports

The canister durability tests of the in-can type incineration-melting furnace

; Kato, Noriyoshi; Miyazaki, Hitoshi; Tanimoto, Kenichi

JNC TN9410 2001-018, 114 Pages, 2001/09

JNC-TN9410-2001-018.pdf:12.35MB

Construction of LEDF (Large equipment dismantling facility) which has the in-can type incineration-melting furnace is planned. The in-can type incineration-melting furnace performs incineration and melting solidification of radioactive waste within the canister made from ceramics, and is characterized by discarding the canister. On the other hand, as for this furnace, the amount of incineration is restrained to canister capacity, Therefore, how to repeat incineration and melting can be considered as a method of increasing the amount of incineration. However, we were anxious about the contact time of the melt and a canister extending, the amount of wear of canister base material increasing, or the heat load (heat cycle) to a canister increasing, and the material intensity of canister base material falling, in order that this method may repeat incineration and melting. then, the tests used imitation waste, are the conditions which repeat (1,3, 10 bathes) the incineration temperature of 1000 $$^{circ}$$C, and the melt temperature of 1500 $$^{circ}$$C, and investigated change of the amount of wear of canister base material and high temperature bend strength. The result is as follows. (1) The amount of wear of canister base material was 0.09 mm/h at the maximum. This result was a sufficiently few value, even if compared with the conventional result (1.0 mm/h). Moreover, the high temperature bend strength of canister base material is about 3 Mpa on an average, and change was seen before and after the examination to which heat load is applied. (2) These tests showed that the factor which spoils the soundness of a canister was oxidization degradation of the canister base material by peeling from the base material of Glaze (glass coating material). The portion embrittlement by oxidization degradation is locally worn down by contact of the melt. (3)Heat-resistant temperature of Glaze is about 1300 $$^{circ}$$C. At the melting operation temperature of 1500 $$^{circ}$$C, and ...

JAEA Reports

The estimation of the amount of the clearance level waste in the decommissioning waste; from the irradiation fuel and material testing facilities)

Kondo, Hitoshi; ; Namekawa, Takashi; ; Miyazaki, Hitoshi; Tanimoto, Kenichi

JNC TN9410 2001-006, 43 Pages, 2000/12

JNC-TN9410-2001-006.pdf:1.49MB

In order to make a contribution to the clearance level decision work of the research facility which handle radioisotope (RI), fuel and so on, the amount of waste from decommissioning the facility was investigated. The investigation were the estimation of the amount of decommissioning waste and the evaluation of the amount of clearance level waste for four facilities which are Fuel Monitorring Facility (FMF), Alpha-Gamma Facility (AGF), Materials Monitoring Facility (MMF), and Waste Dismantling Facility (WDF). The result of estimation and valuation are as follows. (1)The amount of the decommissioning waste for FMF is about 71500 tons. (Concrete is about 67500 tons, metal is about 3,600 tons, and others is about 300 tons.) (2)The amount of the decommissioning waste for AGF is about 14200 tons. (Concrete is about 13300 tons, metal is about 600 tons, and others is about 200 tons.) (3)The amount of the decommissioning waste for MMF is about 18000 tons. (Concrete is about 17100 tons, metal is about 700 tons, and others is about 100 tons.) (4)The amount of the decommissioning waste for WDF is about 28600 tons. (Concrete is about 27900 tons, metal is about 700 tons, and others is about 20 tons.) (5)All concrete waste and over 70% of metal waste is included the clearance level or non-radioactive waste. (6)By excluding a waste under the clearance level from a disassembly waste, the radioactive waste for the decommissioning the facility can be drastically reduced.

JAEA Reports

Tests on decisive proof for the incinerating and melting facility using the in-can type high frequency induction heating

; ; Kato, Noriyoshi; Miyazaki, Hitoshi; Tanimoto, Kenichi

JNC TN9410 2000-002, 149 Pages, 1999/12

JNC-TN9410-2000-002.pdf:23.51MB

LEDF (Large Equipment Dismantling Facility) is the solid waste processing technology development facility that carries out high-volume reduction and low dosage processing. The high-volume reduction processing of the high dose $$alpha$$-waste configured with combustible waste, pvc & rubber, spent ion exchange resin, and noncombustible waste have been planned the incinerating and melting facility using the in-can type high frequency induction heating in LEDF. This test is intended to clarify the design data. It was confirmed that the incinerating and melting performance, molten solid properties and exhaust gas processing performance with pilot testing equipment and bench scale equipment. The result of this test are as follows. (1)Processing speed is 6.7kg/h for the combustible waste, 13.0kg/h for the ion exchange resin, and 30.0kg/h for the noncombustible waste. For above optimum processing conditions are as follows. (a)Operating temperature is 1000$$^{circ}$$C for the combustible waste, 1300$$^{circ}$$C for the ion exchange resin, 1500$$^{circ}$$C for the noncombustible waste. (b)Air flow is 90Nm$$^{3}$$/h. Air temperature is 300$$^{circ}$$C. Air velocity is 20m/s. (2)Incineration time per day is 5h. Warm-up time and incineration time from the stop of waste charging is 0.5h. Melting time per day is 5h inconsideration of heating hold time of incinerated ash and melting of quartz. Warm-up time is 0.5h. (3)The system decontamination factor in Co, Cs and Ce with pilot testing equipment is 10$$^{5}$$ or more. (4)Design data of the iron doped silica gel judged to be have a applicability as RuO$$_{4}$$ gas absorber is as follows. (a)Its diameter distribute in the range of 0.8-1.7mm. (b)To have a decontamination factor of 10$$^{3}$$ can achieve for retention time of 3 seconds and its life time is about 1 year. (5)In terms of the distribution of the nuclear species in molten solid is evenly distributed. It was also confirmed that the distribution of main elements in ceramic layer is ...

JAEA Reports

None

; ; Miyazaki, Hitoshi; ; Tanimoto, Kenichi; Terunuma, Seiichi

PNC TN9420 95-011, 13 Pages, 1994/10

PNC-TN9420-95-011.pdf:8.44MB

None

JAEA Reports

None

; Nakano, Tomoyuki; Miyazaki, Hitoshi;

PNC TN9420 94-015, 80 Pages, 1994/07

PNC-TN9420-94-015.pdf:2.92MB

None

JAEA Reports

None

; Miyazaki, Hitoshi; ; Tanimoto, Kenichi; Terunuma, Seiichi

PNC TN9420 94-010, 103 Pages, 1994/04

PNC-TN9420-94-010.pdf:2.89MB

None

Oral presentation

The Large-scale numerical simulation of nuclear power plant on ITBL grid infrastructure, 1; System outline

Tian, R.; Miyazaki, Akemi; Matsubara, Hitoshi; Nakajima, Norihiro; Tani, Masayuki

no journal, , 

A nuclear power plant is made up of numerous components that are interconnected to each other. Upon external load, they act in a certain interactive way to bear the external load. Therefore, it is an important issue to understand the interaction effect and integrated behaviors of these components. At the current stage, a nuclear power plant is assumed to be a unified structure, and hence it is impossible to evaluate the interaction effects among these components. We have recently established a new approach called assembled structure analysis. In this talk, we will give an introduction of the outline of the entire nuclear power plant simulation system and the fundamental system design of the connection effect evaluation methods.

Oral presentation

The Large-scale numerical simulation of nuclear power plant on ITBL grid infrastructure, 2; Numerical simulation results

Miyazaki, Akemi; Tian, R.; Matsubara, Hitoshi; Nakajima, Norihiro; Tani, Masayuki

no journal, , 

A nuclear power plant is made up of numerous components that are interconnected to each other. Upon external load, they act in a certain interactive way to bear the external load. Therefore, it is an important issue to understand the interaction effect and integrated behaviors of these components. At the current stage, a nuclear power plant is assumed to be a unified structure, and hence it is impossible to evaluate the interaction effects among these components. We have recently established a new approach called assembled structure analysis. In this presentation, we will demonstrate the static simulation results of stresses/strain of the cooling system of the nuclear power plant, and show the great possibility of modeling the nuclear power plant in entire in near future.

22 (Records 1-20 displayed on this page)