Adult Worm Exclusion and Histological Data of Dogs Repeatedly Infected with the Cestode \u3ci\u3eEchinococcus multilocularis\u3c/i\u3e

The data presented in this article are related to a previously published research article titled The timing of worm exclusion in dogs repeatedly infected with the cestode Echinococcus multilocularis (Kouguchi et al. 2016). This data describe a comparison of worm exclusion in the early stage of infection (1 day and 6 days post-infection) between dogs infected for the first time (control group) and dogs repeatedly infected with the parasite 4 times (repeated infection groups). We observed that 6 days post reinfection, the number of adult worms in repeated-infection groups decreased by 88.7% compared with the control group. Histological analysis comparison of the small intestinal mucosa from healthy, first infected, and repeatedly infected dogs are also reported. We observed no clear pathological abnormality, except the shortening of microvillus in reinfected dogs. However, eosinophil accumulation and eosinophilic ulcers were observed in some reinfected dogs. This data could be useful as preliminary data to develop a final host vaccine for this parasite

Phase Transformation by 100 keV Electron Irradiation in Partially Stabilized Zirconia

Partially stabilized zirconia (PSZ) is considered for use as an oxygen-sensor material in liquid lead-bismuth eutectic (LBE) alloys in the radiation environment of an acceleration-driven system (ADS). To predict its lifetime for operating in an ADS, the effects of radiation on the PSZ were clarified in this study. A tetragonal PSZ was irradiated with 100 keV electrons and analyzed by X-ray diffraction (XRD). The results indicate that the phase transition in the PSZ, from the tetragonal to the monoclinic phase, was caused after the irradiation. The deposition energy of the lattice and the deposition energy for the displacement damage of a 100 keV electron in the PSZ are estimated using the particle and heavy ion transport code system and the non-ionizing energy loss, respectively. The results suggest that conventional radiation effects, such as stopping power, are not the main mechanism behind the phase transition. The phase transition is known to be caused by the low-temperature degradation of the PSZ and is attributed to the shift of oxygen ions to oxygen sites. When the electron beam is incident to the material, the kinetic energy deposition and excitation-related processes are caused, and it is suggested to be a factor of the phase transition

Effect of Irradiation on Corrosion Behavior of 316L Steel in Lead-Bismuth Eutectic with Different Oxygen Concentrations

In an accelerator-driven system (ADS), the beam window material of the spallation neutron target is heavily irradiated under severe conditions, in which the radiation damage and corrosion co-occur because of high-energy neutron and/or proton irradiation in the lead–bismuth flow. The materials used in ADSs must be compatible with the liquid metal (lead–bismuth eutectic (LBE)) to prevent issues such as liquid metal embrittlement (LME) and liquid metal corrosion (LMC). This study considers the LMC behavior after ion irradiation of 316L austenitic steel for self-ion irradiations followed by the corrosion tests in LBE with critical oxygen concentration. The 316L samples were irradiated by 10.5 MeV-Fe3+ ions at a temperature of 450 °C, up to 50 displacements per atom (dpa). After the corrosion test performed at 450 °C in LBE with low oxygen concentration, a surface of the nonirradiated area was not oxidized but appeared with locally corrosive morphology, Ni depletion, whereas an iron/chromium oxide layer fully covered the irradiated area. In the case of the corrosion surface with high oxygen concentration in LBE, the surface of the nonirradiated area was covered by an iron oxide layer only, whereas the irradiated area was covered by the duplex layers comprising iron and iron/chromium oxides. It is suggested that irradiation can enhance the oxide layer formation because of the enhancement of Fe and/or oxygen diffusion induced by the radiation defects in 316L steel

Matrix-material dependence on the elongation of embedded gold nanoparticles induced by 4 MeV C60 and 200 MeV Xe ion irradiation

異方性光学素子等への応用が期待されている、SiO2中に形成された金ナノ粒子が数百MeV高エネルギー重イオンを照射するとビーム方向に延びる現象を、電子的阻止能が同程度になる１MeV-6MeVのC60イオン照射でも同様のナノ粒子の変形を起こすことを見出している。しかしC60の場合、スパッタにより表面が削り取られてナノ粒子が露出しまうことで、変形の度合いが制限される問題があった。これに対して、スパッタを低減して、よりナノ粒子が変形する物質を探索した。その結果、酸化インジウムスズ(ITO)中にナノ粒子を形成することにより、スパッタによる表面の削り度合が緩和され、ナノ粒子の変形をより大きくできることを見出した

Japanese activities of the R&D on silicon carbide composites in the broader approach period and beyond

The R&D on SiC/SiC composites under the broader approach (BA) activities between Japan and the EU for fusion DEMO developed a fundamental database of mechanical (Task-1) and physical/chemical (Task-2) properties, with a primary target of the application of SiC/SiC composites as functional structure to be used in the dual coolant breeding blanket concept. This paper aims to summarize previous 10-years activities of the R&D of Japan and to provide the key deliverables toward the DEMO design. In Task-1, good creep and fatigue durability were first demonstrated. Besides, in-plane and inter-laminar strength anisotropy maps at elevated temperatures were comprehensively identified. In parallel, the irradiation effects of SiC materials were specifically determined as input parameters of the analytical model to provide for the irradiation-induced residual stresses. In Task-2, the apparent dose-dependence of the radiation-induced electrical conductivity and the indicative radiation-induced electrical degradation was identified by various irradiation sources. In addition, good gas confinement was identified. Furthermore, no accelerated corrosion for duration of 3000 h at below 1173 K was first demonstrated. With these achievements, it is suggested that the in-vessel component technology, e.g., material corrosion database development, activated corrosion product evaluation code development, compact module tests for validation of the key functions of the components, technology integration assessment for fusion nuclear tests, etc., should be further developed toward DEMO in near-term