• 한국해양공학회지
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• 제13권4호통권35호
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• pp.82-97
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• 1999

A deep sea vehicle must be designed to ensure its safety under ultra-high pressure circumstances. If a pressure housing of a deepsea vehicle is collapsed by ultra-high pressure, the deepsea vehicle may be lost. The objective of this paper is to introduce a design collapse pressure for the deep sea pressure vessel which is composed of one cylinder and two hemispheres. Especially the collapse pressure of hemispherical shell with a hole at top is analyzed by a variational approach (weighted residual method). And for the purpose of design, the salty factor of collapse pressure is presented which is analyzed by interpolation method.

• 대한한의진단학회지
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• 제15권2호
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• pp.159-168
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• 2011

Objectives: The purpose of this study is to develop the pulse wave analysis model with the palpation pressure and the skin effect. Methods: The position of pulse diagnosis was modeled with elastic string system. The skin was modeled with the elastic string, the palpation pressure with tension in the string, and the blood vessel pressure with external force on the string. Using the wave equation in the physics, the simplified pulse model was transformed to the mathematical model. Results: To the verification of the model, the effects of the palpation pressure and the skin effect were tested. Conclusions: There was optimal palpation pressure, describing the exact vessel pressure pattern and maximizing the amplitude of the skin displacement. For the optimal condition, the increased palpation pressure was needed with the increased skin thickness. Therefore, the developed pulse wave analysis model showed the good results.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2000년도 추계학술대회논문집B
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• pp.228-233
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• 2000

The Korean Next Generation Reactor(KNGR) is a Pressurized Water Reactor adopting direct vessel injection(DVI) to optimize the performance of emergency core cooling system(ECCS). In a certain accident, however, pressurized thermal shock(PTS) of the vessel due to the sudden contact with the injected cold water is expected. In this paper, an accident of Main Steam Line Break(MSLB) has been numerically investigated with direct vessel injections and an increased volume flow rate in some cold legs. Using FLUENT code, temperature distributions of the fluid in the downcomer and of reactor vessel including the core region have been calculated, together with the distribution of convective heat transfer coefficient(CHTC) at the cladding surface of the reactor vessel. The result shows that some parts of the core region of the reactor vessel have higher temperature gradient expressing higher thermal stress.

• 한국소성가공학회:학술대회논문집
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• 한국소성가공학회 2007년도 춘계학술대회 논문집
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• pp.38-41
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• 2007

The increase of $CO_2$ emission by increasing of fossil fuel usage has been understood a major cause of global warming. The supply of electric energy is heavily dependent on the massive thermal power and nuclear power plant before developing the renewable energy to supply the electric energy stably at a low price. The large and sound forged components of pressure vessel, turbine and generator are widely used in power plant such as wind power, hydroelectric power generation, nuclear power and thermal power plant. This paper is discussed the trend of manufacturing technology for pressure vessel and turbine to satisfy the required condition of utility company. It is also introduced a strategy of forging industry to cope with carbon tax.

• 전기저널
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• 통권323호
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• pp.53-59
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• 2003

미국 일리노이주의 발전설비 기술기준 체계의 근간을 이루는 것은 ''보일러 및 압력용기안전법(Boiler and Pressure Vessel Safety Act)''(이하 ''법'')으로 일리노이주 의회의 표결이 의한 통과와 주지사의 재가에 의해 법률로 제정된다. State of Fire Marshal(이하 ''소방청'') Dvision of Boiler and Pressure Vessel Safety(이하 ''보일러 및 압력용기안전본부'') 그리고 Board of Boiler and Pressure Vessel Rules(보일러 및 압력용기법위원회)가 법의 제정, 대체 및 개정의 권한을 갖고 있다. 보일러 및 압력용기안전법은 1951년 제정되었으며, 법에서 규정한 예외사항을 제외한 보일러 및 압력용기의 건조$\cdot$설치$\cdot$수리$\cdot$유지$\cdot$교체$\cdot$사용$\cdot$운영에 대한 것을 규정하고 있다. 또한 ''보일러 및 압력용기법위원회''(이하 ''위원회'')를 설립하도록 하고 있다. 위원회는 법의 개정$\cdot$관리, 각종 수수료 책정 등 일리노이주의 보일러 및 압력용기에 대한 전반적인 사항을 관장한다. 보일러 및 압력용기안전법 2002년도 판의 내용을 기초로 하여 미국 일리노이주 발전설비 기술기준의 최근 체계에 대해 소개한다.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2005년도 춘계학술대회 논문집
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• pp.1803-1807
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• 2005

The pipe which it uses from the nuclear power plant or factory by a long period use and a corrosive action the inside defect occurs on the inside. abstract here. The ESPI method is in order to investigate the laser light in the measurement object it will be able to measure the wide territory whole in once, does not receive an effect in direction of defect not to be, has the strong point it will be able to measure a change of place arrowhead real-time defect. It measured a inside defect of pressure vessel by using Out of plane ESPI and In plane of ESPI. It compared a each method result.

• 한국응용약물학회:학술대회논문집
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• 한국응용약물학회 1996년도 춘계학술대회
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• pp.194-194
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• 1996

Pathogenesis of experimental allergic encephalomyelitis was involved with infection, inflammatory reaction, immune reaction etc. We studied on relation of blood vessel system and EAE. So, we measured blood pressure, heart rate and relaxation of isolated blood vessel in control and EAE-induced lewis rats. Blood pressure was decreased before EAE clinical sign (0-20day), but was increased from 23day. In isolated blood vessel, acetylcholine-treated relaxation was different on control, maximum EAE stage, recovery stage. Acetylcholine-treated relaxation was reduced 30% in recovery stage. but, sodium nitroprusside had similar relaxation reaction.

• 소성∙가공
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• 제14권7호
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• pp.613-618
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• 2005

The paper is concerned with the process design and the die design for manufacturing the preform of a large pressure vessel. The cold-working processes are introduced to improve the fatigue strength and to simplify the manufacturing process. By the finite element simulation, the parameter design is carried out, which is subjected to constraints such as the blank sire, press capacity and other minor limitations. The proposed design results are verified by the model experiments, in which the model is scaled down to one tenth of the original size.

• Journal of Radiation Protection and Research
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• 제26권3호
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• pp.237-241
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• 2001

The uncertainties associated with fluence calculation at the pressure vessel have been evaluated for the Korean Next Generation Reactor, APR1400. To obtain uncertainties, sensitivity analyses were performed for each of the parameters important to calculated fast neutron fluence. Among the important parameters to the overall uncertainties, reactor modeling and core neutron source were examined. Mechanical tolerances, composition and density variations in the reactor materials as well as application of $r-{\theta}$ geometry in rectilinear region contribute to uncertainty in the reactor modeling. Depletion and buildup of fissile nuclides, instrument error related to core power level, uncertainty of fuel pin burnup, and variation of long-term axial peaking factors are main contributors to the core neutron source uncertainty. The sensitivity analyses have shown that the uncertainty in the fluence calculation at the reactor pressure vessel is +12%.

• 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.