• 제목/요약/키워드: Psa

검색결과 993건 처리시간 0.028초

FIRE PROPAGATION EQUATION FOR THE EXPLICIT IDENTIFICATION OF FIRE SCENARIOS IN A FIRE PSA

  • Lim, Ho-Gon;Han, Sang-Hoon;Moon, Joo-Hyun
    • Nuclear Engineering and Technology
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    • 제43권3호
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    • pp.271-278
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    • 2011
  • When performing fire PSA in a nuclear power plant, an event mapping method, using an internal event PSA model, is widely used to reduce the resources used by fire PSA model development. Feasible initiating events and component failure events due to fire are identified to transform the fault tree (FT) for an internal event PSA into one for a fire PSA using the event mapping method. A surrogate event or damage term method is used to condition the FT of the internal PSA. The surrogate event or the damage term plays the role of flagging whether the system/component in a fire compartment is damaged or not, depending on the fire being initiated from a specified compartment. These methods usually require explicit states of all compartments to be modeled in a fire area. Fire event scenarios, when using explicit identification, such as surrogate or damage terms, have two problems: (1) there is no consideration of multiple fire propagation beyond a single propagation to an adjacent compartment, and (2) there is no consideration of simultaneous fire propagations in which an initiating fire event is propagated to multiple paths simultaneously. The present paper suggests a fire propagation equation to identify all possible fire event scenarios for an explicitly treated fire event scenario in the fire PSA. Also, a method for separating fire events was developed to make all fire events a set of mutually exclusive events, which can facilitate arithmetic summation in fire risk quantification. A simple example is given to confirm the applicability of the present method for a $2{\times}3$ rectangular fire area. Also, a feasible asymptotic approach is discussed to reduce the computational burden for fire risk quantification.

FLOODING PSA BY CONSIDERING THE OPERATING EXPERIENCE DATA OF KOREAN PWRs

  • Choi, Sun-Yeong;Yang, Joon-Eon
    • Nuclear Engineering and Technology
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    • 제39권3호
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    • pp.215-220
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    • 2007
  • The existing flooding Probabilistic Safety Analysis(PSA) was updated to reflect the Korean plant specific operating experience data into the flooding frequency to improve the PSA quality. Both the Nuclear Power Experience(NPE) database and the Korea Nuclear Pipe Failure Database(NuPIPE) databases were used in this study, and from these databases, only the Pressurized Water Reactor(PWR) data were used for the flooding frequencies of the flooding areas in the primary auxiliary building. With these databases and a Bayesian method, the flooding frequencies for the flooding areas were estimated. Subsequently, the Core Damage Frequency(CDF) for the flooding PSA of the Ulchin(UCN) unit 3 and 4 plants based on the Korean Standard Nuclear Power Plant(KSNP) internal full-power PSA model was recalculated. The evaluation results showed that sixteen flooding events are potentially significant according to the screening criterion, while there were two flooding events exceeding the screening criterion of the existing UCN 3 and 4 flooding PSA. The result was compared with two kinds of cases: (1) the flooding frequency and CDF from the method of the existing flooding PSA with the PWR and Boiled Water Reactor(BWR) data of the NPE database and the Maximum Likelihood Estimate(MLE) method and (2) the flooding frequency and CDF with the NPE database(PWR and BWR data), NuPIPE database, and a Bayesian method. From the comparison, a difference in CDF results was revealed more clearly between the CDF from this study and case (2) than between case (1) and case (2). That is, the number of flooding events exceeding the screen criterion further increased when only the PWR data were used for the primary auxiliary building than when the Korean specific data were used.

Evaluation of the posterior superior alveolar artery canal by cone-beam computed tomography in a sample of the Egyptian population

  • Fayek, Marco Malak;Amer, Maha Eshak;Bakry, Ahmed Mohamed
    • Imaging Science in Dentistry
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    • 제51권1호
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    • pp.35-40
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    • 2021
  • Purpose: This study was conducted to evaluate the accuracy of cone-beam computed tomography (CBCT) in detecting the posterior superior alveolar(PSA) artery canal in a sample of the Egyptian population. Materials and Methods: CBCT images of 600 maxillary sinuses of patients were examined for the presence or absence of the PSA artery along the lateral wall of the maxillary sinus, and for the diameter and type of the canal in relation to age and sex. The distances from the canal to the alveolar crest and sinus floor were also measured. Each canal was assessed to determine whether it was bifid. Results: The PSA artery canal could be detected in 92.0% of the sinuses. The mean distance from the inferior border of the PSA artery canal to the sinus floor was 8.2±2.2 mm (range, 3.2-13.6 mm) in males and 7.3±2.1 mm (range, 3.0-13.1 mm) in females. The mean distance from the inferior border of the PSA artery canal to the alveolar crest was 18.2±2.7 mm (range, 11.0-23.9 mm) in males and 17.4±2.3 mm (range, 10.8-23.5 mm) in females. The mean diameter of the PSA artery canal was larger in male subjects. The PSA artery canal was bifid in 8.7% of cases. The most frequently observed location of the PSA artery canal was intraosseous(82.2%). Conclusion: CBCT was confirmed to be a valuable tool for evaluation and localization of the PSA artery before maxillary sinus lift surgery to avoid intraoperative bleeding.

소외전력망의 태풍 동반 강풍 확률론적 안전성 평가 (Probabilistic Safety Assessment of Offsite Power System Under Typhoon-induced High Wind)

  • 김건규;곽신영;임승현;진승섭
    • 대한토목학회논문집
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    • 제44권3호
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    • pp.277-282
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    • 2024
  • 최근 기후변화로 인해 태풍의 강도와 빈도가 증가하고 있으며, 태풍은 원자력발전소의 소외전원상실(LOOP)을 발생시킬 수 있다. 따라서, 태풍 동반 강풍에 대한 소외전력망의 확률론적 안전성 평가(PSA)를 통한 대비가 필요하다. 하지만, 원자력발전소의 소외전력망에 대한 태풍 동반 강풍 PSA 연구는 미흡한 실정이다. 본 연구에서는 국내원전부지 중 소외전력망의 피해가 잦았던 고리원전부지를 대상으로 소외전력망의 태풍 동반 강풍에 의한 PSA를 수행하였다. 태풍 동반 강풍에 의한 소외전력망의 PSA를 수행하기 위해 고리원전부지의 태풍재해도를 Logic Tree와 Monte Carlo Simulation을 활용하여 도출하였다. 전력망을 구성하는 요소의 취약도를 활용하여 전력망의 취약도 분석을 수행하였다. 최종적으로 소외전력망이 원자력발전소에 전력을 공급하지 못할 확률을 정량적으로 분석하였다.

JRTR 연구용원자로에 대한 최종 확률론적 안전성평가 (A Study on the Final Probabilistic Safety Assessment for the Jordan Research and Training Reactor)

  • 이윤환
    • 한국안전학회지
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    • 제35권3호
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    • pp.86-95
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    • 2020
  • This paper describes the work and the results of the final Probabilistic Safety Assessment (PSA) for the Jordan Research and Training Reactor (JRTR). This final PSA was undertaken to assess the level of safety for the design of a research reactor and to evaluate whether it is probabilistically safe to operate and reliable to use. The scope of the PSA described here is a Level 1 PSA, which addresses the risks associated with core damage. After reviewing the documents and its conceptual design, nine typical initiating events were selected regarding internal events during the normal operation of the reactor. AIMS-PSA (Version 1.2c) was used for the accident quantification, and FTREX was used as the quantification engine. 1.0E-15/yr of the cutoff value was used to deliminate the non-effective Minimal Cut Sets (MCSs) when quantifying the JRTR PSA model. As a result, the final result indicates a point estimate of 2.02E-07/yr for the overall Core Damage Frequency (CDF) attributable to internal initiating events in the core damage state for the JRTR. A Loss of Primary Cooling System Flow (LOPCS) is the dominant contributor to the total CDF by a single initiating event (9.96E-08/yr), and provides 49.4% of the CDF. General Transients (GTRNs) are the second largest contributor, and provide 32.9% (6.65E-08/yr) of the CDF.

Elevated Level of Prostate Specific Antigen Among Prostate Cancer Patients and High Prevalence in the Gangetic Zone of Bihar, India

  • Nath, A.;Singh, J.K.;Vendan, S. Ezhil;Priyanka, Priyanka;Sinha, Shreya
    • Asian Pacific Journal of Cancer Prevention
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    • 제13권1호
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    • pp.221-223
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    • 2012
  • Prostate cancer (CaP) is a common reproductive cancer among men. This study was conducted to correlate the cancer incidence with Gangetic zone and to correlate the tumor marker prostate specific antigen (PSA) level in serum with different age groups and stage of malignancy. Patients suffering from CaP in the pathology unit of Mahavir Cancer Sansthan (Hospital and Research Centre), Patna, Bihar, India were studied from June 2009 to May 2010. PSA level in the serum of CaP patients was estimated by ELISA method. CaP incidence was highly recorded in Gangetic zone than the non-Gangetic zone. Maximum patients were in the 56 - 75 years age group with a marked predominance. Results of PSA examination showed that serum PSA level was not correlating with the age of patient and stage of malignancy. Significantly, elevated level of more than 10 ng/ml of PSA was recorded among the studied cancer patients. In this study, it is concluded that Gangetic zone habitat have high risk of CaP and elevated level of PSA was marked in Bihar, India.

PSA 알고리즘에 의한 태양광 추적시스템의 효율분석 (Efficiency Analysis of PV Tracking System with PSA Algorithm)

  • 최정식;고재섭;정동화
    • 조명전기설비학회논문지
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    • 제23권10호
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    • pp.36-44
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    • 2009
  • 본 논문에서는 PSA(position solar algorithm)을 이용하여 태양광 추적시스템의 발전 효율을 분석하였다. 태양의 위치 추적시스템은 자연환경 조건에 무관한 태양광 발전시스템에 매우 효과적으로 필요하다. 프로그램 방식의 태양광 추적시스템은 구름이나 대기 조건에 의해 일사량이 급하게 변할 경우에도 오동작 없이 정확하게 태양을 추적을 할 수 있다. 따라서, 본 논문에서는 더욱 정확하게 태양의 위치를 추적하기 위한 PSA 알고리즘을 제시하고, 제시한 알고리즘을 이용하여 태양광 발전시스템의 효율을 분석한다. 또한 적용된 알고리즘에 의해 제어된 고도각 및 방위각을 한국 천문연구원에서 제공된 데이터와 비교한다. 본 논문에서는 고도각 및 방위각 제어의 오차와 적용된 알고리즘의 발전효율을 분석하고 결과를 통하여 적용된 알고리즘의 타당성을 입증한다.

PSA기법을 이용한 원자력시설의 핵심구역 파악 (Vital Area Identification of Nuclear Facilities by using PSA)

  • 이윤환;정우식;황미정;양준언
    • 한국안전학회지
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    • 제24권5호
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    • pp.63-68
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    • 2009
  • The urgent VAI method development is required since "The Act of Physical Protection and Radiological Emergency that is established in 2003" requires an evaluation of physical threats in nuclear facilities and an establishment of physical protection in Korea. The VAI methodology is developed to (1) make a sabotage model by reusing existing fire/flooding/pipe break PSA models, (2) calculate MCSs and TEPSs, (3) select the most cost-effective TEPS among many TEPSs, (4) determine the compartments in a selected TEPS as vital areas, and (5) provide protection measures to the vital areas. The developed VAI methodology contains four steps, (1) collecting the internal level 1 PSA model and information, (2) developing the fire/flood/pipe rupture model based on level 1 PSA model, (3) integrating the fire/flood/pipe rupture model into the sabotage model by JSTAR, and (4) calculating MCSs and TEPS. The VAT process is performed through the VIPEX that was developed in KAERI. This methodology serves as a guide to develop a sabotage model by using existing internal and external PSA models. When this methodology is used to identify the vital areas, it provides the most cost-effective method to save the VAI and physical protection costs.

Development of a Fully-Coupled, All States, All Hazards Level 2 PSA at Leibstadt Nuclear Power Plant

  • Zvoncek, Pavol;Nusbaumer, Olivier;Torri, Alfred
    • Nuclear Engineering and Technology
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    • 제49권2호
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    • pp.426-433
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    • 2017
  • This paper describes the development process, the innovative techniques used and insights gained from the latest integrated, full scope, multistate Level 2 PSA analysis conducted at the Leibstadt Nuclear Power Plant (KKL), Switzerland. KKL is a modern single-unit General Electric Boiling Water Reactor (BWR/6) with Mark III Containment, and a power output of $3600MW_{th}/1200MW_e$, the highest among the five operating reactors in Switzerland. A Level 2 Probabilistic Safety Assessment (PSA) analyses accident phenomena in nuclear power plants, identifies ways in which radioactive releases from plants can occur and estimates release pathways, magnitude and frequency. This paper attempts to give an overview of the advanced modeling techniques that have been developed and implemented for the recent KKL Level 2 PSA update, with the aim of systematizing the analysis and modeling processes, as well as complying with the relatively prescriptive Swiss requirements for PSA. The analysis provides significant insights into the absolute and relative importances of risk contributors and accident prevention and mitigation measures. Thanks to several newly developed techniques and an integrated approach, the KKL Level 2 PSA report exhibits a high degree of reviewability and maintainability, and transparently highlights the most important risk contributors to Large Early Release Frequency (LERF) with respect to initiating events, components, operator actions or seismic component failure probabilities (fragilities).

차전자약침(車前子藥鍼)이 Glycerol로 유발(誘發)된 급성신불전(急性腎不全) 백서(白鼠)에 미치는 영향(影響) (The Effect of Plantaginis Semen Herbal Acupuncture on Rat by Glycerol-Induced Acute Renal Failure)

  • 조시용;송춘호
    • 대한약침학회지
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    • 제3권2호
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    • pp.41-54
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    • 2000
  • This study was undertaken to determine if Plantaginis Semen Herbal Acupuncture(PSA) has a protective effect against glycerol-induced acute renal failure in rats. Rats were dehydrated for 24hr and then injected with 8 ml/kg of $50\%$ glycerol, one-half of dose in each hindlimb muscle. In experiments for PSA effect, rats received 0.1 ml of PSA extraction in both sides of corresponding Shenso($BL_{23}$) of human body for 3 days after injection of glycerol. The experimental group were di vided into the Normal group, the Control group, the PSA group. Glycerol injection decreased glomerular filtration rate and increased urine volume, serum creatinine, BUN level and fractional excretion of glucose, $Na^+$, $K^+$ and $CI^-$. These result show that glycerol injection result in acute renal failure. PSA significantly increased glomerular filtration rate and significantly decreased serum creatinine, BUN level and fractional excretion of glucose, $Na^+$ and $CI^-$ as compared Control group. This suggests that PSA could be used in prevention and treatment of acute renalfailure. However, the precise mechanisms of PSA protection remain to be determined.