• Title/Summary/Keyword: Regulatory Pressure

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Study on Relationship between Five Su Points and Glomus (오수혈(五輸穴)과 글로뮈의 상관성에 대한 연구)

  • Lee, Kwang Gye;Lee, Chang Hyun;Kim, Jun Ho;Lee, Sang Ryong
    • Journal of Physiology & Pathology in Korean Medicine
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    • v.26 no.5
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    • pp.650-656
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    • 2012
  • This study was to investigate the origin of meridian through the relationship between Five Su Points and arteriovenous anastomosis. We searched traditional studies about origin of merdian and papers on relationship origin of merdian and blood vessels. As bibliographic search results, we got the conclusion that it is funtion of arteriovenous anastomosis and its anatomical position. Next we compared relationship between it and merdian. We found that Jeong-Acupuncture Points of Five-Su Points and Geun-Acupuncture Points of merdian have close relate to anatomical position(similarities). When we compared relationship between arteriovenous anastomosis and hypertension, we found that Biao Acupuncture Points and Geun Acupuncture Points of merdian have close relate to regulation of blood pressure and blood circulation. According to this results, Five Su Points and arteriovenous anastomosis have close relationship in anatomical position and regulatory function of blood pressure.

Numerical Analysis on Feedback Mechanism of Supersonic Impinging Jet using LES (LES를 이용한 초음속 충돌제트의 피드백 메커니즘에 대한 수치해석 연구)

  • Oh, Se-Hong;Choi, Dae Kyung;Kim, Won Tae;Chang, Yoon-Suk;Choi, Choengryul
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.13 no.2
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    • pp.51-59
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    • 2017
  • Steam jets ejected from a rupture zone of high energy pipes may cause damage to adjacent structures. This event could lead to more serious accidents in nuclear power plants. Therefore, to prevent serious accidents, high energy pipes of nuclear power plants are designed according to the ANSI / ANS 58.2 technical standard. However, the US Nuclear Regulatory Commission (USNRC) has recently pointed out non-conservatism in existing high energy pipe fracture evaluation methods, and required the assessment of the unsteady load of the jet caused by a potential feedback mechanism as well as the impact range of steam jet, the jet impact loads and the blast wave effects at the initial breakage stage. The potential feedback mechanism refers to a phenomenon in which a vortex formed by impingement jets amplifies vortex itself and induces jet vibration in a shear layer. In this study, CFD methodology using the LES turbulence model is established and numerical analysis is carried out to evaluate the dynamic behavior of impingement jets and the potential feedback mechanism during jet impingement. Obtained results have been compared with an empirical correlation and experiment.

Thermal Cycling Screening Criteria to RCS Branch Lines in Domestic Nuclear Power Plant (국내 원전 RCS 분기배관에 대한 열피로 선정기준)

  • Park, Jeong Soon;Choi, Young Hwan;Lim, Kuk Hee;Kim, Sun Hye
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.6 no.2
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    • pp.54-60
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    • 2010
  • Piping failures due to thermal fatigue have been widely reported in normally stagnant non-isolable reactor coolant branch lines. Since the thermal fatigue due to thermal stratification was not considered in the piping fatigue design in old NPPs, it is important to evaluate the effect of thermal stratification on the integrity of branch lines. In this study, geometrical screening criteria for Up-horizontal branch lines in MRP-132 were applied to SI(Safety Injection) lines of KSNP 2-loop and WH 3-loop. Some computational fluid dynamic(CFD) analyses on the Reactor Coolant System(RCS) branch lines were also performed to develop the regulatory guidelines for screening criteria. As a result of applying MRP-132 screening criteria, KSNP 2-loop and WH 3-loop SI lines are determined to need further detailed evaluation. Results of CFD analyses show that both valve isolation and amount of leakage through valve can be used as technical bases for the screening criteria on the thermal fatigue analysis.

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On the Negative Feedback Control Mechanism of the Renin Release in Kidney Slices (신성고혈압 백서의 신장절편에서 Renin 유리의 Negative Feedback 조절기전의 변조)

  • Kim, Hyun-J.;Cho, Kyung-W.
    • The Korean Journal of Physiology
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    • v.20 no.2
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    • pp.236-248
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    • 1986
  • Alterations of renin-angiotensin system have been suggested as one of the mechanisms increasing arterial blood pressure in experimental and clinical hypertension. But the exact nature of high blood pressure in the early and late phase of renal hypertension is still controversial. To clarify the nature of renin release in both unclipped and clipped kidney of two kidney one clip Goldblatt lypertensive rat, experiments have been done in kidney slices, which were obtained from the rats of 3 and 7 days of operation. Basal rate of renin release was suppressed in unclipped kidney slices compared to clipped kidney Norepinephrine increased renin release from unclipped kidney slices, but not from clipped kidney slices. Suppressions by angiotensin Il and arginine vasopressin of renin release were attenuated in the clipped kidney slices compared to unclipped and sham-operated kidney slices. Increases by verapamil and trifluoperazine of renin release were attenuated in the clipped kidney slices compared to unclipped and sham-operated kidney slices. These results suggest that the negative feedback control mechanism of the renin-angiotensin system by angiotensin Il and arginine vasopressin is attenuated in the clipped kidney of two kidney one clip Goldblatt hypertensive rat, and that one of the altered mechanisms may be caused by certain regulatory changes of intracellular calcium and/or calcium-calmodulin complex in the juxtaglomerular cells.

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Risk and Sensitivity Analysis during the Low Power and Shutdown Operation of the 1,500MW Advanced Power Reactor (1,500MW대형원전 정지/저출력 안전성향상을 위한 설계개선안 및 민감도 분석)

  • Moon, Ho Rim;Han, Deok Sung;Kim, Jae Kab;Lee, Sang Won;Lim, Hak Kyu
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.15 no.1
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    • pp.33-39
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    • 2019
  • An 1,500MW advanced power reactor required the standard design approval by a Korean regulatory body in 2014. The reactor has been designed to have a 4-train independent safety concept and a passive auxiliary feedwater system (PAFS). The full power risk or core damage frequency (CDF) of 1,500MW advanced power reactor has been reduced more than that of APR1400. However, the risk during the low power and shutdown (LPSD) operation should be reduced because CDF of LPSD is about 4.7 times higher than that of internal full power. The purpose of paper is to analysis design alternatives to reduce risk during the LPSD. This paper suggests design alternatives to reduce risk and presents sensitivity analysis results.

A New Approach to Selection of Inspection Items using Risk Insight of Probabilistic Safety Assessment for Nuclear Power Plants

  • Park, Younwon;Kim, Hyungjin;Lim, Jihan;Choi, Seongsoo
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.14 no.2
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    • pp.49-58
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    • 2018
  • The regulatory periodic inspection program (PSI) conducted at every overhaul period is the most important process for confirming the safety of nuclear power plants. The PSI for operating nuclear power plants in Korea mainly consist of component level performance check that had been developed based on deterministic approach putting the same degree of importance to all the inspection items. This inspection methodology is likely to be effective for preoperational inspection. However, once the plant is put into service, the PSI must be focused on whether to minimize the risk of accident using defense-in-depth concept and risk insight. The incorporation of defense-in-depth concept and risk insight into the deterministic based safety inspection has not been well studied so far. In this study, two track approaches are proposed to make sure that core damage be avoided: one is to secure success path and the other to block the failure path in a specific event tree of PSA. The investigation shows how to select safety important components and how to set up inspection group to ensure that core damage would not occur for a given initiating event, which results in strengthening defense-in-depth level 3.

Reevaluation of failure criteria location and novel improvement of 1/4 PCCV high fidelity simulation model under material uncertainty quantifications

  • Bu-Seog Ju;Ho-Young Son
    • Nuclear Engineering and Technology
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    • v.55 no.9
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    • pp.3493-3505
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    • 2023
  • Reactor containment buildings serve as the last barrier to prevent radioactive leakage due to accidents and their safety is crucial in overpressurization conditions. Thus, the Regulatory Guide (RG) 1.216 has mentioned the global strain as one of failure criteria in the free-field for cylindrical prestressed concrete containment vessels (PCCV) subject to internal pressure. However, there is a limit that RG 1.216 shows the free-field without the specific locations of failure criteria and also the global strain corresponding to only azimuth 135° has been mentioned in NUREG/CR-6685, regardless of the elevations of the structure. Therefore, in order to reevaluate the failure criteria of the 1:4 scaled PCCV, the high fidelity simulation model based on the experimental test was significantly validated in this study, and it was interesting to find that the experimental and numerical result was very close to each other. In addition, for the consideration of the material uncertainties, the Latin hypercube method was used as a statistical approach. Consequently, it was revealed that the radial displacements of various azimuth area such as 120°, 135°, 150°, 180° and 210° at elevations 4680 mm and 6,200 mm can represent as the global deformation at the free-field, obtained from the statistical approach.

Influencing Factors on Sensitivity of Pressure Decay Test for Membrane Damage Assessment (막 손상 측정을 위한 압력손실시험의 감도에 영향을 미치는 인자)

  • Lee, Yong-Soo;Kim, Hyung-Soo;Kim, Jong-Oh
    • Membrane Journal
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    • v.27 no.4
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    • pp.367-373
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    • 2017
  • Pressurized membrane module systems, including hollow fiber type of Microfiltration (MF) and Ultrafiltration (UF) membranes are being increasingly used in drinking water treatment due to their high removal efficiency of pathogen. However, when fibers are damaged in pressurized membrane system, the pathogen will be able to penetrate the membrane. Therefore, it is essential to guarantee the regulatory requirements for water quality by an effective on-line or off-line condition integrity monitoring methods. Recently, pressure decay test (PDT) which is one of membrane integrity tests has been reflected to drinking water treatment plants using pressurized membrane module. In this paper, three different method were used to perform PDT and three different sensitivity values were analyzed through experiments. Three types of direct integrity test methods were applied to pressure feed side, filtrate side and bidirectional pressure decay test. The results of these experiments show that the sensitivity was increasing when the volume of pressurized gas was decreasing. The sensitivity is inversely proportional to the gas volume. Furthermore, it is desirable to increase pressure difference between feed side and permeate side in order to achieve higher sensitivity in the PDT by membrane damage.

Comparison of Immuno-Modulatory Regulatory Activities of Rubus coreanus Miquel by Ultra High Pressure Extracts Process (초고압 공정에 의한 복분자의 면역조절효능 비교)

  • Kwon, Min-Chul;Kim, Cheol-Hee;Na, Chun-Soo;Kwak, Hyeong-Geun;Kim, Jin-Chul;Lee, Hyeon-Yong
    • Korean Journal of Medicinal Crop Science
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    • v.15 no.6
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    • pp.398-404
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    • 2007
  • This study was performed to investigate the enhancement of anticancer activities and immuno modulatary activities from R. coreanus. by ultra high pressure extracts process. The cytotoxicity on human kidney cell (HEK293) was showed below 19.5% in adding 1.0 $mg/m{\ell}$ concentration. The anticancer activity was increased over 10% by high pressure processing in AGS and A549 cells. The immune cell growth using human immune B and T cells was improved by the high pressure extracts of Rubus coreanus in adding 1.0 $mg/m{\ell}$ concentration. The secretion of two kinds of cytokine, the IL-6 and $TNF-{\alpha}$ from human immune B and T cells were also enhanced in adding extracts by high pressure process of R. coreanus. The ultra high pressure extraction technique showed high efficiency in extracting of bioactive compound. The ultra high pressure technique could be used combined with other technique to improve the extracting rate and extracting efficiency.

Abnormal Operation Analysis of the Wolsong 2,3,4 Heat Transport System (월성 2,3,4호기 열수송계통의 비정상 운전 해석)

  • Shin, J.C.
    • Journal of Energy Engineering
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    • v.25 no.1
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    • pp.15-22
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    • 2016
  • The heat transport system transients of Wolsong 2,3,4 nuclear power plants were analysed during abnormal operating conditions. The compliance with requirements of AECB Regulatory Document R-77 for CANDU reactor was estimated. The analysis results showed that for each postulated accident the peak pressure values in the reactor headers are within the acceptance criteria given in ASME code requirements. The effect of LRV that is one of the overpressure protection device was very minor.