Correlation between cleavage fracture toughness and charpy impact properties in the transition temperature range of reactor pressure vessel steels

Onizawa, Kunio; Suzuki, Masahide

JSME International Journal, Series A, 47(3), p.479 - 485, 2004/07

In the structural integrity assessment of reactor pressure vessel, fracture toughness values are estimated by assuming that the radiation effect on fracture toughness is equivalent to that on Charpy properties. Therefore, it is necessary to establish the correlation between both properties especially on irradiation embrittlement. In this paper, we present the fracture toughness data obtained by applying the master curve approach that was adopted recently in the ASTM test method. Materials used in this study are five ASTM A533B class 1 steels and one weld metal. Neutron irradiation for Charpy-size specimens as well as standard Charpy-v specimens was carried out at the Japan Materials Testing Reactor. The shifts of the reference temperature on fracture toughness due to neutron irradiation are evaluated. Correlation between the fracture toughness reference temperature and Charpy transition temperature is established. Based on the correlation, the optimum test temperature for fracture toughness testing and the method to determine a lower bound fracture toughness curve are discussed.

Mechanical properties of HIP bonded joints of austenitic stainless steel and Cu-alloy for fusion experimental reactor blanket

Sato, Satoshi; Takatsu, Hideyuki; Hashimoto, T.*; Kurasawa, Toshimasa; Furuya, Kazuyuki; *; Osaki, Toshio*; Kuroda, Toshimasa*

Journal of Nuclear Materials, 233-237(PT.B), p.940 - 944, 1996/00

https://doi.org/10.1016/S0022-3115(96)00259-0

no abstracts in English

Aseismic study of high temperature gas-cooled reactor core with block-type fuel(3rd report,effect of excitation directions and core support stiffness

; *

Nihon Kikai Gakkai Rombunshu, C, 51(464), p.746 - 755, 1985/00

https://doi.org/10.1299/kikaic.51.746

no abstracts in English

Two-Dimenional Vertical model Seismic Test and Analysys for HTGR Core

; *

JAERI 1282, 68 Pages, 1983/02

JAERI-1282.pdf:3.43MB

no abstracts in English

Effect of applied stress on temper embrittlement of 2 1/4 Cr-1Mo steel

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Trans.Iron Steel Inst.Jpn., 22, p.863 - 868, 1982/00

no abstracts in English

Seismic response of high temperature gas-cooled reactor core with block-type fuel,III; Vibration experiment of two-dimensional vertical slice core model

; *

Journal of Nuclear Science and Technology, 18(7), p.514 - 524, 1981/00

https://doi.org/10.3327/jnst.18.514

no abstracts in English

One-Region Core ModelSeimic Test and Analysis for HTGR Core

; *

JAERI-M 9199, 61 Pages, 1980/11

JAERI-M-9199.pdf:3.81MB

no abstracts in English

Delta-wrinkly zone observed near crack of ductile zircaloy-2 cladding during impact loading test

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Journal of Nuclear Science and Technology, 15(3), p.230 - 232, 1978/03

https://doi.org/10.3327/jnst.15.230

no abstracts in English

Core seismic experiment of a full-scale single model for a fast reactor

Iwasaki, Akihisa*; Sawa, Naoki*; Matsubara, Shinichiro*; Kitamura, Seiji; Okamura, Shigeki*

no journal, , 

A fast reactor core consists of several hundred core elements, which are hexagonal flexible beams embedded at the lower support plate in a hexagonal arrangement, separated by small gaps, and immersed in a fluid. Core elements have no support for vertical fixing in order to avoid the influence of thermal expansion and swelling. These days, in Japan, larger earthquake vibrations are postulated in seismic evaluations. So, it is necessary to consider vertical displacements (rising) and horizontal displacements of the core elements simultaneously because vertical seismic vibrations are larger than the acceleration of gravity. The 3D vibration behavior is affected by the fluid force of the ambient coolant and contact with the surrounding core elements. In this study, single-model vibration tests using a full-scale test model were conducted, and the basic characteristics of 3D vibration behavior of the core element were examined. In addition, structures restricting vertical displacements (dashpot structure) were devised, and their effectiveness was verified. As a result of the tests, the effects of the ambient condition (in air, in static water, and in flowing water), gap between the pads, vibration directions, vibration waves, and dashpot structures on the vibration behavior of the core element were examined. As regards the ambient condition, the vertical displacements were larger in flowing water that simulates the coolant flow than in air and in static water, because of upward fluid force in flowing water. As regards the gap between the pads, the larger the gaps was, the stronger the interferences due to horizontal displacements, and the smaller the vertical displacements were. The dashpot structure was verified to be suitable for reducing vertical displacements.

Study on the predictive evaluation method of nonlinear sloshing wave height and load of cylindrical tanks, 2; Shaking table test and analysis for nonlinear sloshing

Sago, Hiromi*; Yamamoto, Tomohiko; Miyazaki, Masashi; Tanaka, Masaaki; Yokoi, Shinobu*; Yamane, Yuma*; Nishiwaki, Yoshinori*; Morita, Hideyuki*; Iwasaki, Akihisa*; Ikesue, Shunichi*; et al.

no journal, , 

The design basis ground motions have been revised to improve the seismic resistance of nuclear power plants. The reduction of seismic forces not only horizontally but also vertically has required more critical than in the past to ensure the seismic resistance of components. Notably, the design of a Sodium-Cooled Fast Reactor will require reducing the seismic forces applied to the components because of the components with thin wall thickness. To overcome this problem, the authors plan to introduce a seismic isolation system. When the sloshing wave height is small, it can be approximated with a linear vibration model. However, when the sloshing wave height increases and the sloshing becomes nonlinear, it is necessary to evaluate the wave height using other methods such as numerical analysis. Although the evaluation of nonlinear sloshing wave height is important, there are few examples which quantitatively evaluate the wave height of nonlinear sloshing. This paper reports the results of the sloshing water test carried out to obtain test data for the construction of the evaluation method and the results of the reproduction analysis carried out using the VOF method.