• Title/Summary/Keyword: conservatism

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Experiments and MAAP4 Assessment for Core Mixture Level Depletion After Safety Injection Failure During Long-Term Cooling of a Cold Leg LB-LOCA

  • Kim, Y. S.;B. U. Bae;Park, G. C.;K. Y. Sub;Lee, U. C .
    • Nuclear Engineering and Technology
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    • v.35 no.2
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    • pp.91-107
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    • 2003
  • Since DBA(Design Basis Accidents) has been studied rather separately from SA(Severe Accidents) in the conventional nuclear reactor safety analysis, the thermal hydraulics during transition between DBA and SA has not been identified so much as each accident itself. Thus, in this study, the thermal hydraulic behavior from DBA to the commencement of SA has been experimentally and analytically investigated for the long-term cooling phase of LB-LOCA(Large-Break Loss-of-Coolant Accident). Experiments were conducted for both cases of the loop seal open and closed in an integral test loop, named as SNUF (Seoul National University Facility), which was scaled down to l/6.4 in length and 1/178 in area of the APR1400 (Advanced Power Reactor 1400MWe). The core mixture level was a main measured value since it took major role in the fuel heat-up rate, the location of fuel melting initiation and the channel blockage by melting material during SA. Experimental results were compared to MAAP4.03 to assess its model of calculating the core mixture level. MAAP4.03 overestimates the core two- phase mixture level because sweep-out and spill-over and the measures to simulate the status of loop seal are not included, which is against the conservatism. Thus, it is recommended that MAAP4.03 should be improved to simulate the thermal hydraulic phenomena, such as sweep-out, spill-over and the status of loop seal.

Comparison of Fatigue Provisions in Various Codes and Standards -Part 1: Basic Design S-N Curves of Non-Tubular Steel Members

  • Im, Sungwoo;Choung, Joonmo
    • Journal of Ocean Engineering and Technology
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    • v.35 no.2
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    • pp.161-171
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    • 2021
  • For the fatigue design of offshore structures, it is essential to understand and use the S-N curves specified in various industry standards and codes. This study compared the characteristics of the S-N curves for five major codes. The codes reviewed in this paper were DNV Classification Rules (DNV GL, 2016), ABS Classification Rules (ABS, 2003), British Standards (BSI, 2015), International Welding Association Standards (IIW, 2008), and European Standards (BSI, 2005). Types of stress, such as nominal stress, hot-spot stress, and effective notch stress, were analyzed according to the code. The basic shape of the S-N curve for each code was analyzed. A review of the survival probability of the basic design S-N curve for each code was performed. Finally, the impact on the conservatism of the design was analyzed by comparing the S-N curves of three grades D, E, and F by the five codes. The results presented in this paper are considered to be a good guideline for the fatigue design of offshore structures because the S-N curves of the five most-used codes were analyzed in depth.

Social Conservative Values and Voters in America - Focusing on Abortion Issue - (미국 사회적 보수주의 가치와 유권자 성향 - 낙태 이슈를 중심으로 -)

  • Lee, So Young
    • International Area Studies Review
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    • v.12 no.3
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    • pp.549-566
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    • 2008
  • This study examines the effect of social conservative values that have risen as an important factor in American politics. Focusing on the abortion issue, it discusses how the abortion issue has affected American voters' issue and party preferences and their ideological orientations. The empirical results demonstrate that the abortion issue has contributed to reinforce the existing ideological and partisan divisions, although it has not realigned them. As a consequence, the abortion issue has become a significant determinant for vote choice since 1980s. Particularly in 1990s, when the polarization among the political elites became clear, the political effect of the abortion issue appears to be more evident.

Looking through Others' Eyes: A Double Perspective in Literary and Film Studies

  • Kim, Seong-Kon
    • Journal of English Language & Literature
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    • v.60 no.2
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    • pp.249-267
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    • 2014
  • An outsider's perspective is often illuminating and enlightening, as he or she perceives the world differently from us, and sees things that insiders tend to miss. While an outsider's views are fresh and penetrating, an insider's vision is often banal and myopic. Although outsiders' perspectives may not be quite right at times, they always shed light and provide insight, allowing us to reevaluate the conventional interpretations of our literature and folktales. In order to prevent our own understanding and knowledge from growing stale and narrow-minded, we should endeavor to consider outsiders' opinions and view all things from multiple angles. When reading literary or cultural texts, therefore, we need to read through others' eyes because it provides alternative perspectives. And we should learn to co-exist with others and see things from others' eyes. In his celebrated novel, My Name Is Red, Orhan Pamuk, the Turkish Nobel Laureate, explores the themes of clashes between the East and the West, the young and the old, and conservatism and radicalism. The confrontation between the stubborn defenders of tradition and the self-righteous innovators ultimately results in bigotry, hatred and murder. As Pamuk aptly perceives in his novel, the inevitable outcome of such uncompromising conflict is degradation of humanity and annihilation of human civilization. That is precisely why we need to embrace others who are different from us and learn to look through others' eyes. Sometimes, we fear other voices and different perspectives. As the movie "The Others" suggests, however, there is no reason for us to be afraid of others.

Uncertainty, Corporate Investment and the Role of Conservative Financial Reporting: Empirical Evidence from Pakistan

  • FATIMA, Huma;RANA, Sahar Latif;HAFEEZ, Abida
    • The Journal of Asian Finance, Economics and Business
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    • v.9 no.6
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    • pp.231-243
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    • 2022
  • The objective of this study is to analyze the impact of conservative financial reporting on investment during uncertainty. It was assumed that during uncertainty conservative financial reporting can play an important role to improve investment decision-making. For our analysis, data sets from 2005-2020 of nonfinancial companies are used. To measure the impact of conservative financial reporting in the non-financial sector of Pakistan, Khan and Watts' (2009) model is applied. "Prospector" and "Defender" Business strategy is applied for measuring firm-level uncertainty. Investment is measured by adding the change in fixed assets (property, plant, and equipment). To check the robustness of conservative financial reporting, Givoly and Hayn's (2000) Negative Accruals measure is applied. To measure the robustness of uncertainty, environmental scanning and alertness technique is applied. According to environmental scanning and alertness technique, companies are divided into two groups named 'inert' and 'alert'. 'Inert' are those firms that are not scanning their environment, and 'alert' are those firms who continuously analyze their environment. The empirical estimations support our hypothesis. The empirical findings provide the proof that in the wake of uncertainty conservative financial reporting may facilitate to take optimal investment decisions in the developing economy of Pakistan. Our results provide critical and practical implications for investors, researchers, and standard setters.

Effect of strain rate and stress triaxiality on fracture strain of 304 stainless steels for canister impact simulation

  • Seo, Jun-Min;Kim, Hune-Tae;Kim, Yun-Jae;Yamada, Hiroyuki;Kumagai, Tomohisa;Tokunaga, Hayato;Miura, Naoki
    • Nuclear Engineering and Technology
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    • v.54 no.7
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    • pp.2386-2394
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    • 2022
  • In this paper, smooth and notched bar tensile tests of austenitic stainless steel 304 are performed, covering four different multi-axial stress states and six different strain rate conditions, to investigate the effect of the stress triaxiality and strain rate on fracture strain. Test data show that the measured true fracture strain tends to decrease with increasing stress triaxiality and strain rate. The test data are then quantified using the Johnson-Cook (J-C) fracture strain model incorporating combined effects of the stress triaxiality and strain rate. The determined J-C model can predict true fracture strain overall conservatively with the difference less than 20%. The conservatism in the strain-based acceptance criteria in ASME B&PV Code, Section III, Appendix FF is also discussed.

Application of a combined safety approach for the evaluation of safety margin during a Loss of Condenser Vacuum event

  • Shin, Dong-Hun;Jeong, Hae-Yong;Park, Moon-Ghu;Sohn, Jung-Uk
    • Nuclear Engineering and Technology
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    • v.54 no.5
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    • pp.1698-1711
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    • 2022
  • A combined safety approach, which uses a best-estimate computer code and adopts conservative assumptions for safety systems availability, is developed and applied to the safety margin evaluation for the Loss of Condenser Vacuum (LOCV) of the 1000 MWe Korean Nuclear Power Plant. The Multi-dimensional Analysis of Reactor Safety-KINS standard (MARS-KS) code is selected as a best-estimate code and the PAPIRUS program is used to obtain different initial operational conditions through random sampling of control variables. During an LOCV event, fuel integrity is not threatened by the increase in Departure from Nuclear Boiling Ratio (DNBR). However, the high pressure in the primary coolant system and the secondary system might affect the system integrity. Thus, the peak pressure becomes a major safety concern. Transient analyses are performed for 124 cases of different initial conditions and the most conservative case, which results in the highest system pressure is selected. It is found the suggested methodology gives similar peak pressures when compared to those predicted from existing methodologies. The proposed approach is expected to minimize the time and efforts required to identify the conservative plant conditions in the existing conservative safety methodologies.

Debris transport visualization to analyze the flow characteristics in reactor vessel for nuclear power plants

  • Song, Yong Jae;Lim, Dong Seok;Heo, Min Beom;Kim, Beom Kyu;Lee, Doo Yong;Jo, Daeseong
    • Nuclear Engineering and Technology
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    • v.53 no.12
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    • pp.4003-4013
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    • 2021
  • During the long-term cooling (LTC) phase of a loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR), water is supplied from the containment sump to the reactor coolant system (RCS) by the flooded sump water to the Reactor Vessel (RV) through the broken pipes. As part of the technical efforts for resolving GSI-191 [( Reid and Crytzer, May. 2007) 1, consideration is needed for the consequences of debris penetrating the sump screen and propagating downstream into the RV. Injection of debris (fiberglass) into the RV during the LTC recirculation phase needs special attention to assure that reactor core cooling is maintained. The point of concern is the potential for debris to adversely affect the reactor core flow paths or heat transfer [2]. However, all the experiments for proving the coolability of RV have been done with the assumption of the most of debris would be transferred to the RV and the bottom nozzle of the FAs. The purpose of the tests is to quantify the amount of the debris that would be accumulated at the lower plenum and the debris that passes through the FAs since non-conservatism of other researches assumptions that have been used in the past experimental or analytical programs.

Numerical study on steel plate-concrete composite walls subjected to projectile impacts

  • Lee, Kyungkoo;Shin, Jinwon;Lee, Jungwhee;Kim, Kapsun
    • Steel and Composite Structures
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    • v.44 no.2
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    • pp.225-240
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    • 2022
  • Local responses of steel plate-concrete composite (SC) walls under impact loads are typically evaluated using design equations available in the AISC N690s1-15. These equations enable design of impact-resistant SC walls, but some essential parts such as the effects of wall size and shear reinforcement ratio have not been addressed. Also, since they were developed for design basis events, improved equations are required for accurate prediction of the impact behaviors of SC walls for beyond design basis impact evaluation. This paper presents a numerical study to construct a robust numerical model of SC walls subjected to impact loads to reasonably predict the SC-wall impact behavior, to evaluate the findings observed from the impact tests including the effects of the key design parameters, and to assess the actual responses of full-scale SC walls. The numerical calculations are validated using intermediate-scale impact tests performed previously. The influences of the fracture energy of concrete and the conservative aspects of the current design equations are discussed carefully. Recommendations are made for design practice.

Seismic Analysis Methodology for Non-Nuclear Safety Piping in Nuclear Power Plants (원자력발전소 비안전등급 배관의 내진해석 방법론 연구)

  • Keon Chang Seo;Chi Bum Bahn
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.18 no.1
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    • pp.1-10
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    • 2022
  • Currently, there is no technical standard and regulation for seismic analysis of non-nuclear safety piping. Accordingly, ASME Sec.III ND, a standards applied to safety class 3 piping, is applied. However, the technical standard applied for other than seismic analysis is ASME B31, which leads to controversy. In this study, the feasibility of applying ASME B31E was confirmed by reviewing rulescomparing technical standards, and evaluating piping allowable stress margins. The evaluation revealed that applying ASME B31.1 as a technical standard is too conservative compared to ASME Sec.III ND. On the other hand, ASME B31E (issued at the request of the industry) clearly presents the technical standards for seismic analysis of ASME B31 piping, and shows a similar level of conservatism compared to ASME Sec.III ND. It is expected to reduce the controversy over technical standards for seismic analysis of non-nuclear safety piping by applying ASME B31E.