• Nuclear Engineering and Technology
• /
• 제40권1호
• /
• pp.87-92
• /
• 2008

Tokamak reactor system analysis code was developed at KAERI (Korea Atomic Energy Research Institute) and is used here for the conceptual development of a DEMO reactor. In the system analysis code, prospects of the development of plasma physics and the relevant technology are included in a simple mathematical model, i.e., the overall plant power balance equation and the plasma power balance equation. This system analysis code provides satisfactory results for developing the concept of a DEMO reactor and for identifying the necessary R&D areas, both in the physics and technology areas for the realization of the concept. With this system analysis code, the performance of a DEMO reactor with a limited extension of the plasma physics and technology adopted in the ITER design. The main requirements for the DEMO reactor were selected as: 1) demonstrate tritium self-sufficiency, 2) generate net electricity, and 3) achieve a steady-state operation. It was shown that to access an operational region for higher performance, the main restrictions are presented by the divertor heat load and the steady-state operation requirements.

• Journal of Radiation Protection and Research
• /
• 제37권2호
• /
• pp.63-69
• /
• 2012

The second phase of the national program for fusion energy development in Korea starts from 2012 for design and construction of the fusion DEMO reactor. Radiological assessment for the fusion reactor is one of the key tasks to assure its licensability and the starting point of the assessment is determination of the source terms. As the first effort, the activities of the coolant due to activated corrosion product (ACP) were estimated. Data and experiences from fission reactors were used, in part, in the calculations of the ACP concentrations because of lack of operating experience for fusion reactors. The MCNPX code was used to determine neutron spectra and intensities at the coolant locations and the FISPACT code was used to estimate the ACP activities in the coolant of the fusion DEMO reactor. The calculated specific activities of the most nuclides in the fusion DEMO reactor coolant were 2-15 times lower than those in the PWR coolant, but the specific activities of $^{57}Co$ and $^{57}Ni$ were expected to be much higher than in the PWR coolant. The preliminary results of this study can be used to figure out the approximate radiological conditions and to establish a tentative set of radiological design criteria for the systems carrying coolant in the design phase of the fusion DEMO reactor.

• 기술혁신연구
• /
• 제22권4호
• /
• pp.145-164
• /
• 2014

미래의 궁극에너지로 인식되고 있는 핵융합에너지 개발을 위해서는 DEMO라는 최종 실증 단계를 거쳐야만 한다. 특히 중국, EU, 일본 등의 주요 국가는 DEMO 건설에 대한 구체적 계획을 수립하고 이를 실행 중에 있다. 한국도 1995년부터 KSTAR 사업을 시작으로 핵융합 연구개발에 착수한 점을 감안하면, 핵융합에너지 상용화라는 최종 목표달성 뿐만 아니라, 주요 국가와 DEMO 경쟁 상황에서 주도권을 확보하기 위한 본격적 연구개발이 필요하다. 이에 본 논문에서는 DEMO 개발을 위한 핵심기술을 파악하기 위하여 준정량적 방법론을 적용, 해당 분야의 핵심기술을 도출함으로써 우선적으로 연구개발이 필요한 기술을 식별하여 향후 연구개발 추진시 기술별 우선순위를 제안하고자 한다. 이를 위한 핵융합 에너지 개발과 관련하여 핵융합의 과학적 원리, 주요국가의 DEMO 개발 동향 등을 파악한다. 다음으로 핵융합 실증로와 관련된 기술분류 체계를 검토하여 분석할 기술분류 체계를 선정한다. 선정된 기술체계에 준정량적 방법론으로 기술수준(TRL)을 파악하고 이를 보완하기 위하여 분석적 계층화 과정(AHP)을 적용한다. TRL과 AHP의 결과를 종합하여 우선적으로 확보해야 할 핵융합 실증로의 핵심기술은 실증로용 연소 플라즈마 기술, 대면재료기술, 구조재기술, 고주파 가열장치 기술, 중성입자빔 장치기술, 안전기술, 연소플라즈마 진단장치기술, 핵융합로 시뮬레이터기술 등으로 나타났다.

• 한국가스학회:학술대회논문집
• /
• 한국가스학회 2005년도 추계학술발표회 논문집
• /
• pp.141-145
• /
• 2005

DME (Di-Methyl Ether) is a new clean fuel and an environmental-friendly energy resource, also is recently increasing with an alternative interest because of the industrial use. DME has been shown to have excellent properties as a diesel fuel giving emission level better than ULEV standard. So it has been attracting considerable as an alternative diesel fuel. In this study, we carried out simulation of separation and purification process of demo plant for 101on per day DME production, which cause the effect that is important in productivity, from operation results of pilot plant for 50kg per day DME production. The liquefied stream, which was separated by gas-liquid separator after DME reactor, includes $CO_2$, DME, Methanol and $H_2O$. We established three distillation columns for separation and purification of the stream. $CO_2$ was extracted from the stream by first distillation column, DME was extracted by second column and Methanol was extracted by third column. We investigated and analyzed the effect which the actual operation variables cause in efficiency of process and optimized process, finally we got the DME of purity $100\%$.

• 한국신재생에너지학회:학술대회논문집
• /
• 한국신재생에너지학회 2010년도 추계학술대회 초록집
• /
• pp.131.2-131.2
• /
• 2010

서부 발전 태안화력발전소에 건설 예정인 IGCC Demo plant의 설계 자료를 근거로 석탄 가스화기의 정상 상태 전산모사를 PRO/II를 사용하여 수행하였다. 석탄을 PRO/II가 받아들일 수 있는 성분으로 바꾼 후 가스화기를 버너와 가스화기 본체의 두 부분으로 나누어 모델링하였다. 버너는 단열조건의 Gibbs Reactor로 모델링하였다. 모사 결과 산소가 완전 소진될 때까지 반응이 진행되는 것을 확인하였다. 가스화기는 char gasification 반응은 kinetic reaction equation으로, gas phase reaction은 equilibrium reactor로 모사하는 알고리듬을 개발 하였으나 PRO/II의 기능에 한계가 있어 간단한 Gibbs Reactor로 모사하였다. 가스화기는 membrane wall에 의하여 냉각되는 것을 고려하여 $1550^{\circ}C$의 균일한 온도에서 반응이 일어나는 것으로 고려하였다. 전산 모사 결과 주요 성분의 조성이 실제 syngas의 조성과 5% 정도 오차가 있는 것으로 나타났다.

• Nuclear Engineering and Technology
• /
• 제52권2호
• /
• pp.323-327
• /
• 2020

In this study, the neutronic calculation to obtain tritium breeding ratio (TBR) in a deuterium-tritium (D-T) fusion power reactor using Monte Carlo MCNPX is done. In addition, by using COMSOL software, an efficient cooling system is designed. In the proposed design, it is adequate to enrich up to 40% ⁶Li. Total tritium breeding ratio of 1.12 is achieved. The temperature of helium as coolant gas never exceed 687℃. As regards the tolerable temperature of beryllium (650℃), the design of blanket module is done in the way that beryllium temperature never exceed 600℃. The main feature of this design indicates the temperature of helium coolant is higher than other proposed models for blanket module, therefore power of electricity generation will increase.

• 한국입자에어로졸학회지
• /
• 제9권4호
• /
• pp.239-246
• /
• 2013

The purpose of this study is to determine the feasibility of dry-type desulfurization process for actual application to coal-fired power plant. We used actual exhaust gas from Facility Y, Plant #2 to fabricate a demo-scale testing device to attempt to improve the efficiency of desulfurization. A spout-bed circulating dry scrubber convergence system connecting turbo reactor with bag filter was devised, then analyzed for performance characteristics of $SO_2$ removal for Ca/S mole ratio, superficial gas velocity, and ammonia injection, and for secondary reaction characteristics of the non-reactive sorbent at the bag filter. As a result, the installation of spout-bed circulating dry scrubber convergence system showed better economy and efficiency for removing sulfur than the existing wet/semidry-type desulfurization process. In addition, the best efficiency for desulfurization occurred when connected to the bag filter, with differential pressure maintained at 150 $mmH_2O$.

• Korean Chemical Engineering Research
• /
• 제56권2호
• /
• pp.169-175
• /
• 2018

본 연구는 핵융합 배가스 중 삼중수소가 포함된 화합물인 메탄($CQ_4$) 및 물($Q_2O$)로부터 수소동위원소를 회수하기 위한 공정에 관한 것이다(Q는 수소, 중수소, 삼중수소). 수증기-메탄 개질반응과 수성가스 전환반응을 이용하여 $CQ_4$와 $Q_2O$를 $Q_2$로 변환시키고, 후속하는 팔라듐 분리막으로 생성된 $Q_2$를 회수한다. 본 연구에서는 $CQ_4$ 및 $Q_2O$ 중 하나의 물질인 $CH_4$ 및 $H_2O$로부터 수소 회수를 위해 촉매반응기, 팔라듐 분리막, 순환펌프로 구성된 순환루프를 적용하였다. 촉매반응온도 및 순환유량을 변화시켜가며 $CH_4$ 및 $H_2O$의 전환율을 측정하였다. $CH_4$ 중 수소 회수는 촉매반응온도 $650^{\circ}C$, 순환유량 2.0 L/min 조건에서 99% 이상의 $CH_4$ 전환율을확인하였고, $H_2O$ 중수소 회수는촉매반응온도 $375^{\circ}C$, 순환유량 1.8 L/min 조건에서 96% 이상의 $H_2O$ 전환율을 확인하였다. 이와 더불어, 향후 핵융합 실증로(K-DEMO)에서의 $CQ_4$ 발생량을 예측하고, 이에 대한 처리공정을 제안하였으며, HAZOP (Hazard and Operability) 분석을 실시하여 공정의 위험요소와 운전상의 문제점을 도출하고 해결방안을 제시하였다.

• Nuclear Engineering and Technology
• /
• 제41권4호
• /
• pp.455-476
• /
• 2009

The history of nuclear fusion research in Korea is rather short compared to that of advanced countries. However, since the mid-1990s, at which time the construction of KSTAR was about to commence, fusion research in Korea has been actively carried out in a wide range of areas, from basic plasma physics to fusion reactor design. The flourishing of fusion research partly owes to the fact that industrial technologies in Korea including those related to the nuclear field have been fully matured, with their quality being highly ranked in the world. Successive pivotal programs such as KSTAR and ITER have provided diverse opportunities to address new scientific and technological problems in fusion as well as to draw young researchers into related fields. The frame of the Korean nuclear fusion program is now changing from a small laboratory scale to a large national agenda. Coordinated strategies from different views and a holistic approach are necessary in order to achieve optimal efficiency and effectiveness. Upon this background, the present paper reflects upon the road taken to arrive at this point and looks ahead at the coming future in nuclear fusion research activities in Korea.