Japan Nuclear Safety Institute had recently reported the pioneering deterministic evaluation approach for nuclear power plant under seismic induced fault displacement. But the uncertainty of fault displacement based on probabilistic hazard analysis is described to be greater than that of other natural phenomena e.g. earthquake ground motions or seismic acceleration vibration in the report. Furthermore, for plant-wide risk assessment against fault displacement hazards beyond design basis displacement level, it is seriously necessary to promote a series of fundamental studies and develop the standard procedures regarding not only accident sequence analysis but also fragility analysis of buildings and structures as well as components and piping systems. Based on the above background, the objective of this study is focusing to obtain basic fragility data for the aleatory and epistemic uncertainties of structural responses for nuclear power plant buildings against fault displacement. A number of nonlinear soil-structure finite element analyses against relatively large fault displacement are performed with the randomness of soil and building material properties, the uncertainly of contact parameters relating to friction between soil and building, and also the uncertainty of fault hazards such as fault types and geometries. Their quantitative results for fragility data are shown in this paper.

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Nonlineardynamic analysis methods for reinforcedconcrete shear waUs of reacterbUildings are proposed． In the methods ， the strain rate effects are considered on skeleton curves of the shear walls ． The effects a ［ e re − evaluated based on Iest results ． Theproposedmethods are applied to the simUlation an 証 ysis of shaking table tests ofthe reinforcedconcrete shearwalls 、 The calculation results by the proposed mcthod show better agr ment with the test resuhs than the calcUlat 沁 n resUlts from 山 e conventional mcthod do ． Keyw ・rds 'reinf ・ t ・ ced C ・ nerete shear) valL nvnlinear dynantic analysis ， stJ ' ain 厂ate ， skelet ・ n curve ・ ' resteringfo 厂ce ． characteristics ・ reactor buitding 鉄筋

Construction of a nuclear power plant (NPP) requires a very long period because of large amount of construction materials and many issues for negotiation among multiple sections. Shortening the construction period advances the date of return on an investment, and can also result in reduced construction cost. Therefore, the study of this subject has a very high priority for utilities. We achieved a construction period of 37 months from the first concrete work to fuel loading (F/L) (51.5 months from the inspection of the foundation (I/F) to the start of commercial operation (C/O)) at the Kashiwazaki-Kariwa NPPs No. 6 and 7 (KK-6/7), which are the first ABWR plants in the world. At TEPCO’s next plant, we think that a construction period of less than 36 months (45 months from I/F to C/O) can be realized based on conventional methods such as early start of equipments installation and blocking of equipment to be brought in advance. Furthermore, we are studying the feasibility of a 21.5-month construction period (30 months from I/F to C/O) with advanced ideas and methods. The important concepts for a 21.5-month construction period are adoption of a new building structure that is the steel plate reinforced concrete (SC) structure and promotion of extensive modularization of equipment and building structure. With introducing these new concepts, we are planning the master schedule (M/S) and finding solutions to conflicts in the schedule of area release from building construction work to equipment installation work (schedule-conflicts). In this report, we present the shortest construction period and an effective method to put it into practice for the conventional general arrangement (GA) of ABWR. In the future, we will continue the study on the improvement of building configuration and arrangements, and make clear of the concept for large composite modules of building structures and equipment.

Many researches and experimentS have already been conducted tO eva ］ uate 血 e energy dissipaIion capacity on p 且 as 口 c state of RC shear wan ． However， rnost of the researches and experiments are based on static loading tests or dynamic loading tests using small − scaled sp imens ． The au 山 ors carriedouIdynamic vibraIion 電 ests ushlg a loI of large − scaled spec imens ef RC Shear walls tO propOse a modelof hys電eresis loop and damping fac旗)r u 丗 ized in a dynamic analysis ． This rep 〔 〕 rI pro ヤ ides an energy dissipadon capacity on plastic 漁 te of RC shear walls based on 重 he results of those【 esIs， and provides hysteresis models for dynamic analysis ．