THERMAL STRESS AT AN OFF-ANGLED INTERFACE

Thermal stress at an off-angled interface is considered as a model analysis for “weld line” in an injection-molded FRP. The off-angled interface is a line interface between two bonded anisotropic solids, at which the axis ofanisotropy in each solid is inclined to the interface. Applying the regular technique of integral transforms, we obtain the exact solution for temperature and stress induced by a spontaneous heat source. Especially for the temperature we get a closed-form solution in one term of the exponential function. Extensive numerical computations are carried out for a Nylon 66 compounded with 33 wt% glass fiber and show the stress field near the weld line (off-angled interface). The interfacial shear stress attains its maximum value more quickly than the normal stress. However, the highest normal stress on the interface increases with increasing off-angle, the highest shear stress has a maximum at 43-deg off-angle. The shear stress is 2.8 times greater than that in the isotropic solid and is also 1.34 times greater than that for 90-deg off-angle. This indicates that the lowest strength of the weld line would occur when the off-angle is about 43 deg for our case of Nylon 66.     

Magnetization ringing in the B phase of superfluid3He

We study theoretically the ringing of magnetization in superfluid³He-B for two configurations: the ringing in the Leggett configuration in the presence of a transverse field and the longitudinal ringing in the parallel plate configuration. It is shown that the time variation of the magnetization is described in terms of three distinct ringing frequencies in these general configurations.     

船用柴油机NOx等有害排放气体的评价及处理研究--燃料喷射系统对乳化燃料在船用柴油机上使用的影响及脱硝装置的适用性

对原试验用柴油机的燃料喷射系统进行了改造。改造后的燃料喷射系统不仅可降低 NOx 的排放 ,而且使高加水率乳化燃料的使用成为可能。但另一方面 ,在低负荷时 ,使用乳化燃料不但不能获得预期的降低 NOx 排放效果 ,反而使其它有害排放增加。所以 ,也对降低 NOx 排放方法之一的脱硝装置进行了探讨 ,对其在船用柴油机上的适用性进行了试验 ,并获得了较好的效果     

Safety performance of the 4S reactor on the ATWS events – statistical estimation of uncertainty

4S reactor is a sodium-cooled fast reactor developed as a small-decentralized power supply. The name of “4S” in this reactor stands for Super-Safe, Small and Simple, and they show representative features of the reactor.

The purpose of the present work is to evaluate quantitatively the super-safety of 4S reactor, and the safety performance is analyzed with ARGO-3, which is a plant dynamics code of a sodium-cooled fast reactor.

In this evaluation, some events, such as Unprotected Loss of Flow (ULOF) and Unprotected Transient Overpower (UTOP), are selected as typical cases from various transients and accidents. After metrics concerned with safety design is defined for each event, it is evaluated with statistical methods whether each metric satisfies acceptance criteria in a given criteria level.

Result about ULOF is as follows. The coolant temperature in the nominal hottest assembly outlet, “T_c” is selected as metric, and the upper side value of 95% confidential section in T_c is below 900 °C that is acceptance criteria. Also in UTOP, it is shown that the fuel maximum temperature in the nominal hottest assembly, “T_f” satisfies acceptance criteria. This result shows that 4S reactor has margin for safety acceptance criteria.     

Phase diagram for the helical texture in 3He-A

The stability region of the helical textures in³He-A in thev _s-H phase diagram is theoretically determined. Herev _sis the superflow velocity andH (v _s) is the external magnetic field. The pitch of the helixk ^–1 that minimizes the Gibbs free energy and the corresponding inclination angles ofl andd are determined numerically as functions ofv _sandH. The NMR frequencies (two longitudinal and four transverse frequencies) associated with the helical texture are obtained.Work supported by the National Science Foundation under Grant No. DMR 76-21032.     

Effect of addition of corrosion inhibitors on corrosion behaviors of PCV material under diluted artificial seawater environment

ABSTRACT

Fukushima Daiichi nuclear power plants (1F) were damaged by unprecedented severe accident in the great east Japan earthquake, and seawater and freshwater had been injected as an emergency countermeasure for the core cooling. Although, the primary containment vessel (PCV) was not supposed to be exposed to diluted seawater, the PCV will be exposed to diluted seawater environment until fuel debris removal is completed. Therefore, it is necessary to establish a countermeasure of corrosion for the PCVs made of carbon steel. In this study, the effect of the addition of corrosion inhibitor, which is one of the corrosion countermeasures, was investigated by two types of corrosion tests. As a result of the immersion corrosion test, it was found that any of the three kinds of corrosion inhibitor could suppress corrosion of carbon steel. In addition, as a result of the inhibitor interim addition test, it was found that corrosion of carbon steel covered with corrosion products could be suppressed by optimizing the additive amount of corrosion inhibitor in the cooling water.     

Use of residual voltage for diagnosis of electrical power cables used in nuclear power stations

This paper describes the fundamental characteristics of the residual voltage and the relationship between irradiation dose and residual voltage in electric power cable used in nuclear power generating stations. The residual voltage of unirradiated cable increases with time, tending to saturate. The saturated value of residual voltage is nearly proportional to bias voltage. This result supports the residual voltage of cable being caused by depolarization. From theoretical and experimental investigations we found that the residual voltage is not influenced by cable size or length. This is an important merit of residual voltage as the nondestructive diagnosis. When dose is more than 500 kGy, the residual voltages exhibit a peak. As the irradiation dose is increased, the peak moves to shorter time. Therefore, we can determine the degree of radiation degradation from the location of the peak. © 1997 Scripta Technica, Inc. Electr Eng Jpn 119(2): 18–25, 1997     

Molecular and Genetic Interactions between CCN2 and CCN3 behind Their Yin–Yang Collaboration

Cellular communication network factor (CCN) 2 and 3 are the members of the CCN family that conduct the harmonized development of a variety of tissues and organs under interaction with multiple biomolecules in the microenvironment. Despite their striking structural similarities, these two members show contrastive molecular functions as well as temporospatial emergence in living tissues. Typically, CCN2 promotes cell growth, whereas CCN3 restrains it. Where CCN2 is produced, CCN3 disappears. Nevertheless, these two proteins collaborate together to execute their mission in a yin–yang fashion. The apparent functional counteractions of CCN2 and CCN3 can be ascribed to their direct molecular interaction and interference over the cofactors that are shared by the two. Recent studies have revealed the mutual negative regulation systems between CCN2 and CCN3. Moreover, the simultaneous and bidirectional regulatory system of CCN2 and CCN3 is also being clarified. It is of particular note that these regulations were found to be closely associated with glycolysis, a fundamental procedure of energy metabolism. Here, the molecular interplay and metabolic gene regulation that enable the yin–yang collaboration of CCN2 and CCN3 typically found in cartilage development/regeneration and fibrosis are described.