Welding is one of representative manufacturing processes in the industrial field. Cryogenic storage containers are also manufactured through welding, and conversion to laser welding is issue in the field due to many advantages. Since welding causes thermal-elastic deformation, design considering distortion is required. Prediction of distortion through FEM is essential, but laser welding has difficulties in the field because there is no representative heat source model. The author presented the model that can cover various models using a multi-layer heat source model in previous studies. However the previous study has a limitation which is a welding heat source model must be derived after performing bead on plate welding. Thus this study was attempted to estimate the welding heat source parameters by comparing the shape of bead under various conditions. First, the difference between penetration shape and welding heat source parameters according to welding power was analyzed. The radius of the welding heat source increased according to the welding power, and the depth of the welding heat source also increased. The correlation between the penetration shape and the welding heat source parameter appears at a similar rate, however the follow-up research is necessary with more model data.

Among the test categories of the personal dosimetry performance test in Korea, the reference neutron radiation field used for the mixed neutron-photon radiation field is generated by a D2Omoderated 252Cf source. There are some differences depending on the standards, D2O-moderated 252Cf source consists of the 252Cf source surrounded by the D2O sphere with a diameter of 30 cm, covered with a Cd shell of thickness approximately 0.051 cm ~ 0.1 cm. In order to optimize the design of the D2O sphere and establish the neutron radiation field for the personal dosimetry performance test in Central Research Institute of KHNP, the neutron spectra have been simulated by MCNP 6.2 code by design conditions and evaluated dose conversion coefficients. In the consideration of neutron irradiation facility, the basic design structure was determined a D2O sphere with a diameter of covered with a Cd shell and a cylindrical well is in the middle of sphere. Neutron source transfer tube is inserted into this well-shaped structure and neutron source was withdrawn from the tube. And by changing the following design conditions in detail, the neutron spectra were evaluated; 1) the entire diameter of the D2O sphere (with or without the diameter of 7.5 cm of well-shaped structure) 2) the location of the neutron source (distance from D2O) 3) thickness of Cd shell 4) purity of D2O. As a source spectrum, the spectrum of bare- 252Cf recommended by ISO 8529-1 was adopted and spectra were tallied using F4 tally at a distance of 120 cm from the neutron source. Finally, the fluence to dose conversion coefficients were calculated using the simulated spectra. As a result of the evaluation, in case that an entire diameter of the D2O sphere with a diameter of the source tube is 37.5 cm, the fluence to dose conversion coefficient was evaluated to about 4.4% lower than an entire diameter of the D2O sphere is 30 cm. And in case that the distance between the D2O and the top of the neutron source was about 3.75 cm which is a radius of well-type structure, it was evaluated to about 1.4% larger than the distance was about 1 cm, and when the thickness of Cd was 0.1 cm, it was evaluated to 0.8% larger than when it was 0.051 cm. Finally, when the purity of D2O was 99.99%, it was evaluated 1.5% lower than when it was 99%. Except for the diameter of D2O sphere, the differences on the other conditions are acceptable considering the uncertainty of the simulation. Therefore, the design of D2O-moderated 252Cf source was determined by considering source integrity, economic perspectives, and dose conversion coefficient given in ISO 8529: a D2O sphere with an entire diameter of 37.5 cm, filled with above 99% purity of D2O, and covered with a cadmium thickness of 0.1 cm. The fluence to dose conversion efficient was evaluated as 110.10 pSv cm2 for ambient dose H*(10), 115.21 pSv cm2 for personal dose Hp(10) respectively.

Radioactive source terms are important factor in design, licensing and operation of SMR (Small Modular Reactor). In this study, regulatory requirements and evaluation methodology for normal operation on NuScale SMR, which received standard design certification approval on September 11, 2020 from US NRC, are reviewed. The radioactive waste management system of nuclear power reactor should be designed to limit radionuclide concentration in effluents and keep radioactive effluents at restricted area boundary ALARA according to 10 CFR 20 and 10 CFR 50 Appendix I. Also, in general, the coolant source term to calculate the off-site radiological consequences for normal operation of SMR should be determined by using models and parameters that are consistent with regulatory guide 1.112, NUREG- 0017 and the guidance provided in ANSI/ANS-18.1-1999, and the result should be corrected by reflecting the design characteristics of SMR. The coolant source term of NuScale, unlike the case of large NPPs, cannot rely solely on empirical source term data, because the NuScale source term is based on first principle physics, operational experience from recent industry, and lessons learned from large PWR operation. Fission products in reactor coolant are conservatively calculated using first principle physics in SCALE Code assuming 60 GWD/MTU. The release of fission products from fuel to primary coolant based on industry operational experience is determined as fuel failure fraction of 0.0066% for normal operation source term and 0.066% for design basis source term while coolant source term of large NPP is calculated by using ANSI/ANS-18.1 for normal operation and fuel failure fraction of 1% for design basis source term. Water activation products in reactor coolant are calculated from first principles physics and corrosion activation products are calculated by utilizing current large PWR operating data (ANSI/ANS 18.1- 1999) and adjusted to NuScale plant parameters. Also, because ANSI/ANS 18.1-1999 is not based on first principle physics models for CRUD generation, buildup, transport, plate-out, or solubility, NuScale has incorporated lessons learned by using ERPI’s primary water chemistry and steam generator guidelines to ensure source term is conservative and design of materials used cobalt reduction philosophy to help ensure the coolant source term are conservative. Based on the coolant source term calculated according to the above-described method, the annual releases of radioactive materials in gaseous and liquid effluents from NuScale reactor are evaluated. Currently, Small Modular Reactors such as ARA, SMART 100 are under review for licensing in Korea. This study will be helpful to understand how the reactor coolant system source terms are defined and evaluated for SMR.

In Korea, the NUREG-0017 methodology based on realistic model for reactor coolant concentrations are used to estimate the annual radioactive effluent releases for normal operation of nuclear power plant. The realistic model to estimate the radionuclide concentrations in reactor coolant is formulated as a standard, ANSI/ANS-18.1. This standard has provided a set of the reference radionuclide concentrations and adjustment factors for estimating the radioactivity in the principal fluid systems of target plant. Since ANSI/ANS-18.1 was first published in 1976, it was revised in 1984, 1999, 2016, and most recently in 2020. Therefore, this study analyzed revision history of assessment methodology of radioactive source term of light water reactors, which is ANSI/ANS-18.1. Assessment methodology of radioactive source term given ANSI/ANS-18.1 is by using radionuclide concentrations for reactor coolant and steam generator fluid of the reference plant and adjustment factors, which is modifying radioactive source term according to differences in design parameters between reference plant and target plant. There are three type of reference plant: PWR with u-tube steam generator, PWR with once-through steam generator, and BWR. This study analyzed for PWR with u-tube steam generator. Although the standard was revised, evaluation methodology and formula of adjustment factor have been retained, but some of items have been revised. First revision item is reduction of the number of radionuclides and decrease of radioactive concentration in reactor coolant. In the 1976 version of the standard, there were 71 target radionuclides, but the target nuclides have reduced to 57 in 1984 and 56 after 1999. In the case of radioactive concentration in reactor coolant, as the version of standard was updated, the radioactive concentration of 18 nuclides in 1984, 14 nuclides in 1999, and 25 radionuclides in 2016 was decreased. Most of the radionuclides with decrease radioactivity concentration were fission product, it is resulted from improvement of nuclear fuel performance. Second revision item is change of adjustment factors. After the revision in 2016, the adjustment factors for zinc addition plants using natural or depleted zinc are changed. This study analyzed revision history of evaluation methodology of radioactive source term of light water reactors. Furthermore, result of this study will be contributed to the improvement of understanding of assessment methodology and revision history for the radioactive source term.

In order to dispose of spent nuclear fuel (SNF) in deep geological repository, source term evaluation considering its specification, enrichment, burnup, cooling time should be performed. In this study, the measured values of Takahama-3 pressurized water reactor SNF (WH 17×17) samples were analyzed with SCALE 6.1/ORIGEN-S and TRITON code calculation results for validation. Unlike the ORIGENS code, TRITON code calculations differed from two-dimensional neutron flux distribution by using the multi-group cross-section library. Both calculation results from ORIGEN-S and TRITON code showed higher errors in 234U, 239Pu, and 241Pu compared to other actinide nuclides. In the case of axial locations of fuel rods in fuel assembly, fuel rods located at the edge of the fuel assembly presented increased errors due to nuclear reaction cross-section. Overall, the ORIGEN-S predictions informed more accurate agreement with the measured results compared with TRITON results. Especially to 235U, 239Pu, and 240Pu radionuclides, ORIGEN-S errors were denoted more than twice as low as the TRITON results. Comparing the calculation results with experimental results implied that the ORIGENS code was more accurate code than the TRITON code for source term evaluation.

Due to environmental pollution, regulations on fossil fuels are required. There is a movement for the regulations by using LNG fueled propulsion ships. LNG is an eco-friendly fuel that does not emit NOx or SOx during combustion, but its boiling point is -163°C. Under that condition, the use of metal is restricted, and IMO defined applicable materials through IGC code. Among the metals, 9% nickel steel is one of excellent mechanical properties such as yield strength and tensile strength in cryogenic condition. Thus 9% nickel steel is widely used in cryogenic storage containers for ships. In addition, laser welding, which minimizes thermoelastic distortion by applying a concentrated heat source to a narrow area for a short period of time, is in the spotlight. So, this study is a basic research to predict and respond to thermal distortion during laser welding. Secondary version of the representative heat source model was derived through the author's previous research with STS304L, and the heat source model was derived by applying the heat source model to 9% nickel steel in this study. 9% nickel steel is a material that is in high demand and is widely used in the manufacture of cryogenic containers, so this study is expected to be able to respond immediately to the field.

9% nickel steel has remarkable mechanical properties in a cryogenic condition and is widely used in storage containers for LNG fueled ships. Demand for laser welding rather than conventional arc welding has grown to increase manufacturing efficiency. However there are various types of heat sources which are suggested by other researchers. With that, it is difficult to select a proper heat source shape for welding conditions. The author proposed a representative heat source model that can cover most of suggested heat source models through previous studies. Welding power was fixed at 4kW and the speed was changed to 1.0m/min, 1.5m/min, and 2.0m/min respectively. The shapes of the welding heat sources were derived, and the tendency of the main parameters was also deducted. It was observed that the width and depth of the weld bead decreased as the welding speed increased through welding experiment, parameters of welding heat source are changed linearly. Based on this study, it is expected that it will be possible to estimate the shape of the heat source under untested welding conditions.

Laser welding is used in various industries due to fast welding speed, and prediction with FEM is needed to design. The multi-layered heat source model that can cover various models has been recently proposed to analyze laser welding, but it takes a lot of time because more than 2,000 cases are compared to derive the results. In order to reduce the time, the simplified model should be suggested. In order to derive a simplified model, laser welding heat transfer analysis was performed using the welding direction length and the convection coefficient of the welding direction surface as parameters. As a result, the model whose difference is less than 0.1% compared to reference model is deducted. The analysis time was reduced by about 90% from 48 hours to 5 hours. Also difference of convection coefficient on the welding direction surface does not affect the temperature distribution much.

As laser welding has low thermal distortion and fast welding speed, the needs in the field is increasing in varous industries. Prediction of distortion and design with that prediction are very important for using welding process in the field. However many types of heat source models for laser welding are suggested, field engineers feels difffucult for using a proper model for a specific case. Thus I, author, suggested a representative model which can cover most of existing models with multi-layered heat source model. This method is very powerful, but there are much time consumption with analysis and comparision among more than 1,000 candidates. To solve these shortcomings, this study focused on to find the simplified model. In order to construct the simplified model, the length of the orthogonal direction to the welding direction was reduced from 300mm to 35mm, which makes time reduction of 75% with sustaining the quality of the original model. That can cover the disadvantage of multi-layered heat source model for laser welding, enhance the prediction of welding distortion after laser welding

고품질의 작물을 재배하기 위해 광은 필수적인 환경조건이 다. 겨울철에는 다른 계절에 비해 일사량이 저조하므로 보광 처리를 이용해 작물의 생육과 수확량을 증대시킬 수 있다. 본 연구는 약광기 동안 고추 온실재배를 위한 경제적인 보광 광 원을 선발하기 위해 수행되었다. 풋고추(Capsicum annuum ‘Super Cheongyang’)는 2019년 9월 5일에 정식하였다. 보광 처리는 2020년 1월 1일부터 2020년 3월 31일까지 수행되었 다. White LED(R:G:B = 5:3:2, W LED), RB LED(red:blue = 7:3, RB LED), 고압나트륨등(high pressure sodium lamp, HPS)을 광원으로 사용하였다. 무처리를 대조구로 사용하였 다. 고추의 초장, SPAD, 마디 수는 보광 광원에 따른 유의적인 차이가 없었다. 그러나 분지 수는 RB LED 광원에서 가장 많 았다. 또한 보광은 고추의 광합성을 증가시켰으며, 특히 RB LED에서 보광기간 동안 가장 높은 광합성률을 보였다. 또한 고추의 수확량은 보광처리에서 증가하였고, RB LED는 다른 광원에 비해 가장 높은 수확량을 보였다. 소비전력은 W LED 가 가장 높았고 HPS 조명이 가장 낮았다. 경제적인 측면에서 RB LED를 이용한 보광처리는 다른 광원에 비해 높은 경제성 을 가졌다. 결론적으로 이러한 결과는 고추 온실에서 약광기 동안 보광 광원으로 RB LED를 사용하는 것이 수확량과 경제 성을 향상시킬 수 있을 것으로 판단된다.

지구온난화 완화를 위한 노력이 전 세계적으로 계속되고 있는 가운데 우리나라는 2030년 온실가스 배출량을 Business As Usual (BAU) 대비 37% 감축하는 목표를 설정하고 이산화탄소 순 배출 제로 달성을 목표로 하는 ‘2050탄소중립 시나리오’를 발표하였다. 이러한 상황에서 케나프 (Kenaf)는 높은 탄소흡수율과 빠른 성장으로 인해 대체 해결방안으로 제안된다. 시료선정에 대한 분석결과, 케나프 잎은 질소 함량이 높아 적합하지 않은 것으로 나타났고, 줄기와 잎-줄기 혼합 케나프는 Biomass-Solid Refuse Fuel (Bio-SRF) 등급을 충족했다. Bio-SRF 등급을 만족하였지만, Bio-SRF 등급으로 이용할 수 있는 활용처가 뚜렷하지 않다. 따라서 케나프의 연료품질을 반탄화 공정을 통해 개선하여 보다 효율적으로 활용하고자 한다. 반탄화 공정의 공시재료로 줄기만 사용하는 것보다 시료 이용률이 높은 잎-줄기 혼합 케나프를 선택하였다. 반탄화 공정은 여섯가지의 공정 온도 (200·210·220·230·240·250℃)와 다른 세 가지 공정 시간(20·30·40 min)에서 수행되었다. 반탄화 공정결과, 공정시간이 길수록 230℃, 240℃, 250℃ 온도에서 질량감소가 크기 때문에 에너지수율이 낮았다. 따라서 본 연구에서는 200℃·20 min, 200℃·30 min, 210℃·20 min, 220℃·20 min의 에너지 수율이 높고 질량감소가 작아 최적 반탄화 공정 조건으로 선정하였다.

We investigated physicochemical properties and isotopic compositions of organic matter (δ13CTOC and δ15NTN) in the old fish farming (OFF) site after the cessation of aquaculture farming. Based on this approach, our objective is to determine the organic matter origin and their relative contributions preserved at sediments of fish farming. Temporal and spatial distribution of particulate and sinking organic matter (OFF sites: 2.0 to 3.3 mg L-1 for particulate matter concentration, 18.8 to 246.6 g m-2 day-1 for sinking organic matter rate, control sites: 2.0 to 3.5 mg L-1 for particulate matter concentration, 25.5 to 129.4 g m-2 day-1 for sinking organic matter rate) between both sites showed significant difference along seasonal precipitations. In contrast to variations of δ13CTOC and δ15NTN values at water columns, these isotopic compositions (OFF sites: -21.5‰ to - 20.4‰ for δ13CTOC, 6.0‰ to 7.6‰ for δ15NTN, control sites: - 21.6‰ to - 21.0‰ for δ13CTOC, 6.6‰ to 8.0‰ for δ15NTN) investigated at sediments have distinctive isotopic patterns (p<0.05) for seawater-derived nitrogen sources, indicating the increased input of aquaculture-derived sources (e.g., fish fecal). With respect to past fish farming activities, representative sources (e.g., fish fecal and algae) between both sites showed significant difference (p<0.05), confirming predominant contribution (55.9±4.6%) of fish fecal within OFF sites. Thus, our results may determine specific controlling factor for sustainable use of fish farming sites by estimating the discriminative contributions of organic matter between both sites.