[en] The yield, gas production rates, He/dpa ratio, spectral distribution and DPA (Displacement per Atom) of transmutation-induced Alpha and Proton particles were calculated for the fusion reactor's structure materials (316S.S., SiC, Graphite and included elements in them). The electronic energy loss of transmutation-induced Alpha particle in 316S.S. is also calculated. The calculated results show that the DPA is very small caused by them, but the synergistic action of high-energy cascades and helium should influence seriously the radiation-induced swelling, with large electronic energy loss about 10 keV/nm. The effect of the electronic energy loss on material's properties is considerable. The spectral distribution depends mainly on reaction energy and atomic weight of target elements. The more reaction energy and atomic weight of target element are, the higher energy of transmutation-induced Alpha and Proton particles are. Their spectral distributions localized much about 9-14 MeV for the materials containing heavy nuclide. In the materials containing light nuclide the spectral distribution are localized much about 1-9 MeV for Alpha. The projected poloidal angle distribution is much about 80 degree-100 degree for materials containing heavy nuclide and 70 degree-110 degree for Graphite, material containing light nuclide. The calculated results provided parameter-basis for simulation of irradiated damage by high energy-neutrons used ions beam irradiation

[en] In the fusion-fission hybrid reactor, the alternating thermal stresses of fuel element cladding are much more serious than steady operating fission reactor, because of the D-T periodic burning. The thermal stresses are directly proportional to the temperature cycling region and thickness of cladding. The key to the safe and reliable operation is reasonable design of temperature cycling region

[en] A Monte-Carlo computer simulation code is presented for materials irradiation damage caused by fusion-neutron. The code can be applied to static multi-compound amorphous targets included both light elements and heavy elements. the incident neutron is limited with the energy less than 15 MeV, but charged-particle energy is not limited. The code can calculate the DPA cross sections and gas production cross sections, the displacement and gas production rates after irradiation. The code may present energy spectrum and angular distribution of PKA and Alpha-particle and proton. The DPA cross sections, PKA energy spectrum, angular distributions, displacement and gas production rates of some elements (Fe, Cr, Ni, Mo, W Si and C) in materials such as 316 ss, tungsten, graphite and silicon-carbon are given for the first wall of fusion-fission reactor

[en] A program DNWLMC by Monte-Carlo calculation is compiled, and used it to calculate neutron wall load distribution and neutron current distribution with the cosine of incident angle in the first wall of TOKAMAK. The result indicates that neutron wall load distribution and neutron current distribution are complicated. The first wall cross section and the relative position between the first wall and the plasma have significant effect on the distributions. In general, neutron wall load distribution is far from being uniform. Most neutrons enter the first wall perpendicularly or nearly perpendicularly, only a few enter the first wall at small incident angles

[en] Boroncoating was deposited on the plasma facing surface of HT-7 superconducting tokamak using carborane mixtures (C₂B₁₀H₁₂) by glow discharge. A direct result of this surface modification showed that the impurity content was substantially reduced, particularly oxygen containing gases such as CO and H₂O, and that Z_eff of impurities decreased from 4∼5 before boronization to ∼1.5 in duration of the plasma discharge. Boronization reduces the particles recycling obviously and provides good wall conduction for LHCD experiments. Some problems in the boronization experiments were discussed in detail, and some improvements on the boronization process have been considered

[en] The Monte-Carlo Neutron Transport Program and Neutron Radiation Damage Program are presented for studying radiation damage in the First Wall. The programs are used to static multi-component amorphous target. With the average wall load 1 MW/m², the following calculating results for EHR first wall (type 316 stainless steel) have been performed by using designed neutron spectrums at EHR first wall: the PKA energy spectrums (30 eV to 1 MeV), average displacement per atom rate (20.6 dpa/a) and average helium and hydrogen production rates (247.18 appm/a and 721.15 appm/a). It shows that Hybrid Reactor's radiation damage is more serious than pure Fusion reactor's by comparison of above results and EHP's calculated results in the same wall load. the cross-section data from MC (87) n library is used in the calculation

[en] By means of the monte-carlo method based on the binary collision approximation, this paper investigates sputtering caused by fusion α-particles at the first wall of stainless steel. The parameters adjusted in accordance with a comparison of the calculated and measured sputtering yields of the elements Fe, Cr and Ni were used to study the partial sputtering yields, energy distribution, angular distribution and depth distribution of origin of the sputtered particles, as well as the dependence of those quantities with the angles of incidence. The results show that by taking into account the energy and incidence angle distribution, the average sputtering yield of α-particles in stainless steel is about 0.375, and the higher energy component of α-particle plays minor role so far as sputtering is concerned

[en] The spectra of fusion α-particle leaking out from the plasma boundary and bombarding first wall in a Tokamak fusion reactor were investigated. The loss mechanisms of α-particle were studied, and the slowing down-diffusion equations describing the α-particle transport in plasma were set up. The contributions from banana-trapped particles, transit particles and superbanana ripple trapped particles to the diffusion coefficient were considered. The equations were numerically solved for Tokamak reactors with typical parameters to obtain the required α-particle spectra. The physical significance of the results is discussed finally

[en] Bi₂Sr₂CaCu₂O_x tapes were irradiated with 230MeV Au¹⁴⁺ and 120MeV O⁷⁺ ions. Columnar defects and point-like defects were produced by the former and latter ions respectively. The increase in remanent magnetization due to Au¹⁴⁺ irradiation showed strong pinning effects caused by the columnar defects. The critical current density obtained from the hysteresis loops was enhanced, especially in high fields and at high temperatures. Irreversibility lines were also enhanced due to irradiation. The effective activation energy for vortex motion was obtained from the measurement of magnetization relaxation. The results of the columnar defects were compared with those of point defects caused by 120MeV O⁷⁺ irradiation and also prior to irradiation. Magnetization relaxation experiments indicated that the introduction of columnar defects changed the vortex motion from two-dimensional to three-dimensional vortex creep. (orig.)

[en] Highlights: • The study introduces the meta-model to aid building calibration with optimization. . • Gaussian process outperforms Multiple Linear Regression as the meta-model. . • A case study is presented to show the proposed approach performance. . • The new approach helps overcome optimization complexity and hyperparameter setting. . • The involvement of engineering judgement and recalibration is helpful . -- Abstract: Building energy model calibration with optimization aims to bridge the gap between simulated energy consumption and measurement, thus aiding building retrofit and operation. However, the difficulty of the optimization in calibration including both optimization hyperparameter settings and problem complexity (multi-modal and under-determined) make the calibration with optimization approach difficult to be applied in practice with full reliability. Meanwhile, current calibration with optimization treats building calibration as a purely mathematical problem while neglecting the importance of engineering judgment in the calibration practice. In this paper, we introduced meta-models into the calibration with optimization approach with an auto-correction mechanism to improve calibration performance with respect to time and reliability. To better illustrate the approach, we presented a case study with validation. The proposed method was demonstrated to alleviate difficulty of optimization while improving calibration time and reliability in the study. Comparing two types of meta-models, we found that using the GP (Gaussian Process) achieved better performance with less computation time and higher accuracy compared to the MLR (Multiple Linear Regression). To efficiently train emulators, we can start with generating only a small amount of white-box simulation results. It is also important to generate enough initial starts to ensure robustness of calibration.