• Corrosion Science and Technology
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• v.7 no.2
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• pp.77-84
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• 2008

Based upon the good compatibility to neutron irradiation and high temperature water environment, austenitic stainless steels are widely used for core internal structural materials of light water reactors. But, recently, intergranular cracking was detected in the stainless steels for the core applications in some commercial PWR plants. Authors studied on the root cause of the intergranular cracking and developed the countermeasure including the alternative materials for these core applications. The intergranular cracking in these core applications are defined as an irradiation assisted mechanical cracking and irradiation assisted stress corrosion cracking. In this paper, the root cause of the intergranular cracking and its countermeasure are summarized and discussed.

• Nuclear Engineering and Technology
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• v.54 no.8
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• pp.2783-2791
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• 2022

Molecular dynamics simulations were performed to predict the behavior of graphite atoms under neutron irradiation using large-scale atomic/molecular massively parallel simulator (LAMMPS) package with adaptive intermolecular reactive empirical bond order (AIREBOM) potential. Defect structures of graphite were compared with results from previous studies by means of density functional theory (DFT) calculations. The quantitative relation between primary knock-on atom (PKA) energy and irradiation damage on graphite was calculated. and the effect of PKA direction on the amount of defects is estimated by counting displaced atoms. Defects are classified into four groups: structural defects, energy defects, vacancies, and near-defect structures, where a structural defect is further subdivided into six types by decision tree method which is one of the supervised machine learning techniques.

• Nuclear Engineering and Technology
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• v.54 no.1
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• pp.244-254
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• 2022

For tensile tests, Vickers hardness tests and microstructure tests, plate-type and box-type specimens of austenitic 316L stainless steels were produced by a conventional machining (CM) process as well as two additive manufacturing processes such as direct metal laser sintering (DMLS) and direct metal tooling (DMT). The specimens were irradiated up to a fast neutron fluence of 3.3 × 10⁹ n/cm² at a neutron irradiation facility. Mechanical performance of the unirradiated and irradiated specimens were investigated at room temperature and 300 ℃, respectively. The tensile strengths of the DMLS, DMT and CM 316L specimens are in descending order but the elongations are in reverse order, regardless of irradiation and temperature. The ratio of Vickers hardness to ultimate tensile strength was derived to be between 3.21 and 4.01. The additive manufacturing processes exhibit suitable mechanical performance, comparing the tensile strengths and elongations of the conventional machining process.

• Journal of Radiation Protection and Research
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• v.14 no.1
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• pp.66-70
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• 1989

In routine testing, the radioactive neutron sources are particularly suitable for producing standard. neutron fields. The ISO TC-85 has proposed neutron reference radiation for the calibration of neutron measuring devices used for radiation protection purposes. Radiation laboratory of KSRI has installed a standard irradiation facility using $^{252}Cf$ and $^{241}Am-Be$ sources for calibrating personal dosimeters according to the recommendations given in ISO TC-85. In this study, correction factors for calibration related to neutron scattering and anisotropy are obtained by experiments with commercial rem meter for demonstration purposes.

• Nuclear Engineering and Technology
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• v.55 no.1
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• pp.209-214
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• 2023

The effect of thermal annealing on defect recovery of in-core neutron-irradiated 4H-SiC was investigated. Au/SiC Schottky diodes were manufactured using a 4H-SiC epitaxial wafer that was neutron-irradiated at the HANARO research reactor. The electrical characteristics of their epitaxial layers were analyzed under various conditions, including different neutron fluences (1.3 × 10¹⁷ and 2.7 × 10¹⁷ neutrons/cm²) and annealing times (up to 2 h at 1700 ℃). Capacity-voltage measurements showed high carrier compensation in the neutron-irradiated samples and a recovery tendency that increased with annealing time. The carrier density could be recovered up to 77% of the bare sample. Deep-level-transient spectroscopy revealed intrinsic defects of 4H-SiC with energy levels 0.47 and 0.68 eV below the conduction-band edge, which were significantly increased by in-core neutron irradiation. A previously unknown defect with a high electron-capture cross-section was discovered at 0.36 eV below the conduction-band edge. All defect concentrations decreased with 1700 ℃ annealing; the decrease was faster when the defect level was shallow.

• Radiation Oncology Journal
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• v.17 no.1
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• pp.65-69
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• 1999

Purpose : It has been well established that the response of cells and tissues to low LET radiations (X- or gamma-ray) can be enhanced by combining with hyperthermia. However, there has been relatively little work of hyperthermia on the possible modification of either cellular or tissue responses to other types of radiation. So, we investigated the combined effect of fast neutron irradiation and hyperthermia according to the sequence and time interval of the two. Materials and Methods : In MKN-45 cells, a human stomach cancer ceil line, suwiving fractions were measured according to the sequential treatment of 0, 4, 2, 0 hour-intewal for fast neutron irradiation (1.5 Gy) combined with hyperthermia (41 $^{\circ}C$ for 30 min or 43$^{\circ}C$ for 30 min). Results : D$_{0}$ and n of MKN-45 for neutron were 0.8 Gy and 2.5, respectively. The surviving fraction by 1.5 Gy of neutron was 0.36$\pm$0.34. Interacting powers were mostly ranged between 1 and 2, but they were 3.0 and 2.7, respectively for hyperthermia (41 $^{\circ}C$ for 30 min) fellowed by neutron irradiation 6 and 4 hours later. Conclusion : The combined effect of fast neutron (1.5 Gy) and hyperthermia (41 $^{\circ}C$ or 43$^{\circ}C$ for 30min) is largely independently additive. Preceding mild hyperthermia (41 $^{\circ}C$ for 30 min) 4 or 6 hours before neutron may cause decreased sensitivity to subsequent neutron irradiation.

• Journal of the Korean Magnetics Society
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• v.10 no.2
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• pp.49-52
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• 2000

The changes of magnetic properties in neutron irradiated F $e_{81}$ $B_{13.5}$S $i_{3.5}$ $C_2$ amorphous ribbon were studied by X-ray diffraction, hysteresis loop, temperature dependence of magnetization and complex permeability. The fluences of thermal ( $n_{th}$) and fast ( $n_{f}$) neutron were 6.95$\times$10$^{18}$ $n_{th}$ c $m^{-2}$ and 4.56$\times$10$^{16}$ $n_{f}$c $m^{-2}$ , respectively. The changes of XRD Profiles were not observable at the neutron irradiated sample. The complex permeability spectra showed that the permeability from domain wall motion decreased due to the increase of pinning force against domain motion by the neutron irradiation, and the relaxation frequency of rotational magnetization moved to higher frequency region. The measurement of hysteresis loop showed the increase of magnetic softness, related to rotational magnetization, but saturation magnetization was decreased in neutron irradiation sample. The Curie temperature was decreased in the neutron irradiated sample.e.e.e.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.15 no.2
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• pp.9-18
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• 2019

The objective of this study is to investigate the feasibility of simulating the mechanical properties of irradiatied austenitic stainless steels by cold-working. In this study, the tensile properties, cyclic hardening behaviors and fracture toughness of cold-worked TP316L stainless steel were compared with those of austenitic stainless steels irradiated by neutrons. It showed that cold-working can properly simulate the increase in strength and the decrease in ductility and fracture resistance of austenitic stainless steels by neutron irradiation, even though it could not perfectly simulate the microstructures of irradiated austenitic stainless steels. Also, cold-working can appropriately simulate the hardening behaviors of neutron irradiated austenitic stainless steels under monotonic and cyclic loading conditions.

• Korean Journal of Veterinary Research
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• v.10 no.2
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• pp.21-51
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• 1970

Series of experiments were conducted to determine lethal does of X-ray and Neutron on Toxoplasma gondii. strain RH and IRI. As well morphological changes of Toxoplasma gondii irradiated or not were compared by use of electron microscope. The pathogenicity test of the irradiated and nonirradiated Toxoplasma gondii was made in mice guinea-pigs, rabbits and pigs: The letahl dose of X-ray and Neutron on RH and IRI strain and the growth rate between two strains after irradiation were shown little differences. Morphological changes were not observed until 18th passage was made. After then, the growth rate was decreased apparently, and atrophied forms were frequently observed in electron microscope. Survival time of animals inoculated with irradiated strain was longer than that of animals giving non-irradiated strain, and Toxoplasma gondii were isolated from all the dead animals. But it is of interest that pigs survived after injection of Toxoplasma gondii remained health and much attempts were failed toisolate Toxplasma gondii remained health and much attempts were slaughtered them. Animals were succumbed after injection of Toxoplasma gondii without any relationship with serum titers. (HA antibody).

• Proceedings of the Korean Society of Medical Physics Conference
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• 1999.11a
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• pp.62-65
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• 1999