[en] R-matrix theory is used to calculate proton elastic recoil cross sections. The Los Alamos R-matrix parameters which are based upon the proton elastic scattering cross section, are used in the calculation, and the center-of-mass energy is extended down to 0.12 MeV. The normalization is adjusted by minimizing the χ² value between the experimental and calculated cross sections. By comparison it is hence confirmed that our recent experimental data are consistent with the calculated results, at the measured energy range and recoil angles. The proton elastic recoil cross sections obtained by R-matrix analysis are suggested for practical ERD application since they are quite consistent with the published proton scattering cross sections for proton laboratory energy range of 0.2-17.8 MeV

[en] The ITER (International Thermonuclear Experimental Reactor) tokamak has 18 toroidal magnetic field (TF) coils, and the discreteness of these TF coils causes toroidally non-axisymmetric perturbations of the magnetic field. It is called a TF ripple and could lead to losses of high-energy particles, and an unfavorable heat load on the plasma facing components. In the ITER design, a ferromagnetic insert (FI) is employed to reduce the TF ripple, and an optimization of the FI design is ongoing. Also, since test blanket modules (TBMs) will be installed in the ITER, which are made of a ferromagnetic material, they also affect the TF ripple. We assessed the effects of the thickness of the FIs on the TF ripple in order to optimize the FI. And we analyzed how the TBMs distort the TF, and calculated the TF ripple for various amounts of a ferromagnetic material and the positions of the TBMs. A simple correction coil was adopted in order to reduce the TBM induced TF ripple to the required value of 0.3 %. We proposed technically available measures to reduce the TF ripple to the required value

[en] The cross sections for proton elastic recoil of 0.6-5.0 MeV ⁴He ions have been measured at recoil angles of 10 deg., 15 deg., 20 deg., 25 deg., 30 deg., 35 deg. and 40 deg. with the target set for transmission geometry. Thin melamine (C₃H₆N₆) foils (10-25 μg/cm²) were used as the hydrogen target. By bombarding the ⁴He ions normal to the target, backscattered ⁴He ions from nitrogen and recoil protons at forward angles were detected. Hence the proton recoil cross section was determined by normalizing to the scattering cross section of ⁴He ions backscattered from nitrogen to 165 deg. [Y. Feng, Z. Zhou, G. Zhao, F. Yang, Nucl. Instr. and Meth. B 94 (1994) 11]. The measured cross sectional data are reviewed and compared with calculations for the kinematic inverse reaction ⁴He(p,p)⁴He, and with the measured results of the proton recoil cross section reported up to now. In order to simplify the application of these results for ERD analysis, an arbitrary polynomial is derived by fitting the cross sectional data from this study

[en] Recently, many therapeutic techniques by using radioisotopes have been developed, and the demands of radioisotopes are increased, in the medical application. The researches for production of radioisotopes are widely performed. In this study, the requirement of neutron generator for producing the therapeutic radioisotopes ⁸⁹Sr was studied and the production rate was calculated

[en] As a party of the ITER, especially as a procurement party of the ITER blanket, we have designed the First Wall Qualification Mockup (FWQM) and fabricated five FWQMs. Two of them have been tested up to 12,690/12,020 cycles at a heat flux higher than 0.625 MW/m² at the KoHLT-1 facility established in the Korea Atomic Energy Research Institute (KAERI). Two KO FWQMs successfully passed the normal heat flux tests, and there was no indication of defect in the Be-to-CuCrZr joints

[en] A high heat flux test facility using a graphite heating panel was constructed and is presently in operation at Korea Atomic Energy Research Institute, which is called KoHLT-1. Its major purpose is to carry out a thermal cycle test to verify the integrity of a HIP (hot isostatic pressing) bonded Be mockups which were fabricated for developing HIP joining technology to bond different metals, i.e., Be-to-CuCrZr and CuCrZr-to-SS316L, for the ITER (International Thermonuclear Experimental Reactor) first wall. The KoHLT-1 consists of a graphite heating panel, a box-type test chamber with water-cooling jackets, an electrical DC power supply, a water-cooling system, an evacuation system, an He gas system, and some diagnostics, which are equipped in an authorized laboratory with a special ventilation system for the Be treatment. The graphite heater is placed between two mockups, and the gap distance between the heater and the mockup is adjusted to 2≥3 mm. We designed and fabricated several graphite heating panels to have various heating areas depending on the tested mockups, and to have the electrical resistances of 0.2∼0.5 ohms during high temperature operation. The heat fluxes on the two mockups are deduced from the flow rate and the coolant inlet/outlet temperatures by a calorimetric method. We have carried out the thermal cycle tests of various Be mockups, including two FWQMs (First Wall Qualification Mockups) which have three Be-tiles of 80x80 mm², six single tile mockups (80x80x1) with an identical cross-section to the FWQM, and six small mockups (35x35x3) with three Be-tiles of 35x35 mm² bonded to a CuCrZr block. Nominal heat flux was 0.625 MW/m² or 1.5 MW/m² depending on the mockup sizes. For the FWQMs, we performed the thermal fatigue tests up to 12,690 and 12,020 cycles at a heat flux higher than 0.625 MW/m2. During the tests, there was no remarkable change in the thermal response of two FWQMs, which demonstrated that the FWQMs had an acceptable bonding quality and an acceptable thermal performance. Some Be tiles of the 80x80x1 mockups and 35x35x3 mockups were detached during a thermal cycle test at the heat-up or cool-down phase. Four of six 35x35x3 mockups passed thermal fatigue testing of 1,100 cycles at a heat flux higher than 1.5 MW/m² with no change in thermal response. These results indicated no degradation in the Be-CuCrZr joint. Through this study, the reliability of the KoHLT-1 for long time operation at a high heat flux was verified, and its broad applicability is promising

[en] Korea (KO) has developed and participated in the Test Blanket Module (TBM) program in the ITER, in which Ferritic martensitic (FM) steel was used as the structural material for the TBM first wall (FW). To develop the fabrication method for the TBM FW and verify its integrity, a half scale sub module mock up was fabricated and integrity test has been prepared. Two manifolds for connecting with the water supplying system in high heat flux (HHF) test were fabricated and welded with the mock up. Pressure and He leak tests were successfully performed without any leak and failure. The flow rates in each channel were measured with the conventional ultrasonic sensor but it shows non uniform flow distribution at each channel differently from the estimation by ANSYS CFX. HHF test conditions were evaluated through the ANSYS CFX analysis considering the above measured flow rates in each channel and it shows non uniform temperature distribution of the FW surface. Now a new manifold design or modification of the fabricated one is being considered for a uniform flow distribution at each channel of the mock up

[en] Korea had responsibility for the procurement of the International Thermonuclear Experimental Reactor (ITER) blanket modules 1, 2 and 6 as a ITER participant. Now, our responsibility was changed from the procurement to only the development of fabrication technology including the international qualification. Each blanket module is composed of first wall (FW) panel and shield block. Especially for the FW, it is an important component which faces the plasma directly and it is subjected to high heat and neutron loads. The FW is composed of a beryllium(Be) layer as a plasma facing material, a copper alloy(CuCrZr) layer as a heat sink and type 316L authentic stainless steel(SS316L) as a structure material. For the joining of the above three metals, Hot Isostatic Pressing(HIP) has been developed including the Post HIP Heat Treatment(PHHT) in Korea. For the verification of the joining integrity, high heat flux(HHF) test for loading the cyclic heat load has been performed with foreign and domestic facilities. In the present paper, the development procedure and future plan was introduced

[en] The Korea (KO) has developed liquid a breeder blanket and participated in the Test Blanket Module (TBM) program within the International Thermonuclear Experimental Reactor (ITER) with a Helium Cooled Molten Lithium (HCML) concept. Ferritic Martensitic Steel material is used as structural material for the TBM first wall (FW). In order to develop the fabrication method for the TBM FW, the various manufacturing and joining methods have been developed. In this study, three mock-ups were fabricated to verify the manufacturing of a 1/6-scale mock-up of the TBM FW and preliminary analyses were performed to design a manifold of a 1/6-scale mock-up for uniform flow in the channels. Using Ferritic Martensite Steel material, three kinds of small mock-ups were fabricated such as a cooling channel shape of straight, two cooling channels shape of straight, and a cooling channel shape of U-type. The small mock-ups were manufactured by wire cutting and machining for components of the mock-ups and a welding and HIP, at 1050 .deg. C and 100 MPa for two hours, were performed for bonding. The fabricated small mock-ups were performed pressure tests between the joints to evaluate bonding of the mock-ups

[en] Korea has developed and participated in the Test Blanket Module (TBM) program of the International Thermo-nuclear Experimental Reactor (ITER). The first wall (FW) of the TBM is an important component that faces the plasma directly and therefore it is subjected to high heat and neutron loads. To fabricate the TBM FW, the Hot Isostatic Pressing (HIP) bonding method has been investigated. In the present study, the manufacturing method of the TBM FW is introduced through the fabrication and testing of a 1/6-scale mockup. To distribute fluid uniformly in the mock-up, a manifold was designed and fabricated using the ANSYS-CFX analysis. After the mock-up was fabricated and its fluid distribution tests performed, we compared the results of tests with the simulated results