• 한국압력기기공학회 논문집
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• 제10권1호
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• pp.107-112
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• 2014

The Code of Federal Regulations, Title 10, Part 50, Appendix H requires surveillance program for reactor pressure vessel(RPV) that the peak neutron fluence at the end of the design life of the vessel will exceed $1.0E+17n/cm^2$ (E>1.0MeV). 2D/1D Synthesis method based on DORT 3.1 transport calculation code has been widely used to determine fast neutron(E>1.0MeV) fluence exposure to RPV in the beltline region. RAPTOR-M3G(RApid Parallel Transport Of Radiation-Multiple 3D Geometries) performing full 3D transport calculation was developed by Westinghouse and KRIST(Korea Reactor Integrity Surveillance Technology) and applied for the evaluations of In-Vessel and Ex-Vessel neutron dosimetry. The reaction rates from measurement and calculation were compared and the results show good agreements each other.

• 한국해양공학회지
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• 제27권1호
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• pp.51-58
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• 2013

Recently, there has been an increase in the demand for natural gas as a source of clean energy, which has increased the demand for LNG carriers. However, LNG carriers require a capital investment to obtain equipment for the regasification process, which prevents fires and explosions. Thus, on account of NIMBY, a CNG carrier is suggested that eliminates the need for regasification equipment. Meanwhile, carbon dioxide emissions are more and more regulated by international conventions such as the Kyoto Protocol. Because of this, $CO_2$ carriers have also received international attention as a methodology to transport and store $CO_2$ cargoes. Several vessels or tanks to transport and store $CO_2$ gas have been studied in various countries. This paper proposes a conceptual design for a 20ft container shaped tank to effectively transport small cargoes of $CO_2$ and CNG. The proposed pressure vessel or tank will be carried by a conventional containership or special cargo ship. The influences of the design parameters for proposed pressure vessel or tank. Including the materials, scantlings, and shape of the pressure vessel, are studied theoretically and computationally.

• Journal of Radiation Protection and Research
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• 제32권4호
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• pp.168-177
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• 2007

본 논문에서는 노심설계 단계에서 선정된 다양한 노심 장전모형 중에서 압력용기 중성자 조사취화 관점에서 가장 최적의 노심 장전모형을 선정할 수 있도록 신속하게 압력용기 취약위치에 대한 속중성자속을 예측할 수 있는 방법을 제시하였다. 인공신경회로망 기법을 통해 노심 반경방향 및 축방향 출력분포만을 이용하여 압력용기내벽 취약위치에서의 중성자 스펙트럼을 신속하게 평가할 수 있도록 중성자속 가중치를 생산하였고 데이터베이스를 구축하였다. 이 방법은 중성자 수송코드를 이용한 수송계산을 직접 수행하지 않고도 신속하게 압력용기 위치에서의 중성자 조사환경을 평가할 수 있으며 소송코드 결과와 비교하여 상대오차 3.4%이내의 정확도를 보였다.

• 한국중재학회지:중재연구
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• 제21권3호
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• pp.189-211
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• 2011

This article aims at analysing the practical problems of FOB and CIF terms relating to Incoterms$^{(R)}$2010 in case of L/C transactions and presenting the defending measures against them. According to Incoterms$^{(R)}$2010, FOB and CIF terms are to be used only for sea or inland waterway transport and require the seller deliver the goods on board the vessel nominated by the buyer at named port of shipment. So if FOB and CIF terms will be used in sea transport under L/C transaction, the seller should ship the goods on the nominated vessel and present the shipping document indicating "on board vessel" to the issuing bank but the parties agree to present the received bill of lading according to special condition on L/C which is" received bill of lading are acceptable". In practical transaction, FOB and CIF terms are usually used in aircraft cargo, container cargo or multimodal transport. these facts are a violation of Incoterms. Incoterms$^{(R)}$2010 which regulated that FOB and CIF terms may not be appropriate where goods are handed over the carrier before they are on board the vessel for example goods in container. These transactions are a temporary expedient and breach of Incoterms in the international trade which must be corrected as soon as possible.

• 방사성폐기물학회지
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• 제5권2호
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• pp.155-169
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• 2007

월성 원자력 발전소의 TRF 시설에서 수집된 트리튬을 metal hydride 형태로 보관하고 있는 500 kCi급 트리튬 1차 저장용기를 발전소 밖의 폐기물 저장고로 안전하게 운반하기 위하여 트리튬 운반용기를 개발하였다. B형 운반용기의 기술기준을 적용하여 구조평가, 열평가, 방사선차폐평가, 격납평가 등을 수행하여 운반용기의 안전성을 분석하였다. 트리튬 운반용기는 정상운반조건 및 사고운반조건에서도 격납 경계가 손상되지 않는다고 평가되었다. 붕괴열로 인한 운반용기 내부 저장용기의 온도상승은 수치해석 결과, 원통형 모델에서는 $134.8^{\circ}C$로 나타났다. 운반사고 조건에 대한 열 평가로서 $800^{\circ}C$ 외부환경에 30분간 노출되었을 경우에는 단열재만의 열차폐를 고려하여 계산한 결과, 약 $405^{\circ}C$로 나타났으며, 내부 온도 상승은 1차 격납 경계인 1차 저장용기의 허용 온도인 $550^{\circ}C$에도 미치지 못하였다. 격납 차폐 평가에서도 사고조건인 $800^{\circ}C$의 외부 환경에 노출된 경우에서도 충분히 운반용기의 격납 성능을 유지할 수 있다고 판단되었다. 방사선에 대한 차폐 특성을 조사한 결과, 트리튬에서 발생된 ${\beta}-ray$ 선량은 1차 저장용기 외부 표면에서 0으로 계산되었다. 이상과 같이 500 kCi 급 트리튬 운반용기에 대한 안전성을 평가한 결과, 운반사고조건에서도 트리튬 운반용기는 전혀 이상이 없는 것으로 나타났다.

• 한국기계연구소 소보
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• 통권14호
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• pp.145-155
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• 1985

The recent trend in shipbuilding technology is toward development of highly economical vessels of which construction and operation costs are minimized, whereas cargo transport capacity is maximized. But, most of the vessel which are now operated by some of the nation's shipping companies are uneconomical ones built before oil crisis and consequently the companies are suffering from long-lasted deficit problem. In this paper, derivation study of optimum vessel for multi purpose cargo vessel on south-East Asian trade route is carried out to solve this problem. The Required Freight Rate is used as a measure of merits.

• Nuclear Engineering and Technology
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• 제52권2호
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• pp.448-455
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• 2020

The H.B. Robinson Unit 2 (HBR-2) pressure vessel dosimetry benchmark is an in- and ex-Reactor Pressure Vessel (RPV) neutron dosimetry benchmark based on experimental data from the HBR-2 reactor, a 2300-MW PWR designed by Westinghouse and put in operation in March 1971, openly available through the SINBAD Database at OECD/NEA data Bank. The goals of the present work were to carry out three-dimensional (3D) fixed source transport calculations in both Cartesian (X,Y,Z) and cylindrical (R,θ,Z) geometries by using the TORT-3.2 discrete ordinates code on very detailed 3D HBR-2 geometrical models and to test the latest broad-group coupled (47 neutron groups + 20 photon groups) working cross section libraries in FIDO-ANISN format with same structure as BUGLE-96, such as BUGJEFF311.BOLIB, BUGENDF70.BOLIB and BUGLE-B7. The results obtained with all the cited libraries were satisfactory and are here reported and compared.

• Nuclear Engineering and Technology
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• 제52권11호
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• pp.2620-2629
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• 2020

As an early stage in the development of a water calorimeter, this study established a computer simulation methodology for analyzing the thermal behavior of a water calorimeter based on radiation transport and energy deposition. As a result, this study developed a method wherein the energy deposition distribution, which is obtained by applying Monte Carlo methods in water calorimeters, is directly used as a heat source for the thermal analysis model. Based on the proposed method, heat transfer in a water vessel and the effect of thermistor self-heating were analyzed. Through an analysis of the water velocities with and without a water vessel, it was found that a water vessel can serve as a convection barrier. Furthermore, it was confirmed that when considering thermistor self-heating, the water temperature change at the thermistor location is 0.219 mK higher compared to that when the thermistor was not considered. Therefore, thermistor self-heating must be considered to analyze the thermal behavior of a water calorimeter more accurately.

• Ocean Systems Engineering
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• 제5권3호
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• pp.181-198
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• 2015

An OSV (Offshore Support Vessel) is being used to install a structure which is laid on its deck or an adjacent transport barge by lifting off the structure with its own crane, lifting in the air, crossing splash zone, deeply submerging, and lastly landing it. There are some major considerations during these operations. Especially, when lifting off the structure, if operating conditions such as ocean environmental loads and lifting off velocity are not suitable, the collision can be occurred due to the relative motion between the structure and the OSV or the transport barge. To solve this problem, this study performs the physics-based simulation of the lifting off step while the OSV installs the structure. The simulation includes the calculation of dynamic responses of the OSV and the structure, including the collision detection between the transport barge and the structure. To check the applicability of the physics-based simulation, it is applied to a problem of the lifting off step by varying the ocean environmental loads and the lifting off velocity. As a result, it is confirmed that the operability of the lifting off step are affected by the conditions.

• Journal of Radiation Protection and Research
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• 제20권4호
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• pp.285-296
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• 1995

각 원자력 발전소에서 발생되는 방사성폐기물을 한 곳에 모아 집중관리하기 위한 방사성폐기물 처분장의 부지선정이 국가적 과제로 부각되어 있으며, 충분한 검토를 거친 후 임해부지로 선정될 것이다. 이로 인하여 현재 각 원전부지내에 임시로 보관되어 있는 방사성폐기물에 대하여 전용선박에 의한 해상수송을 하여야 하면, 한국원자력연구소의 원자력환경관리센터(NEMAC)에서는 원전부지로부터 처 분장까지 안전하고 효율적으로 방사성폐기물을 수송할 수 있는 종합해상 수송체계를 개발중에 있다. 이 글은 해상수송체계가 갖추어야 할 수송선박의 기술기준을 설정하기 위한 것으로, 원자력 선진국의 진보된 방사성폐기물 해상수송기술에 관한 현황을 조사, 분석하고 국내의 제반여건을 고려하여 우리나라에서 사용될 수송선박의 설계 및 건조추진방향을 제시하였다. 따라서, 만일의 사고에도 방사성물질이 선박의 외부로 누출되지 않는 개념의 선박을 설계, 건조하여 방사성폐기물을 안전하게 해상수송하게 될 것이다.