• 제목/요약/키워드: Break test

검색결과 556건 처리시간 0.025초

REVIEW OF DYNAMIC LOADING J-R TEST METHOD FOR LEAK BEFORE BREAK OF NUCLEAR PIPING

  • Oh, Young-Jin;Hwang, Il-Soon
    • Nuclear Engineering and Technology
    • /
    • 제38권7호
    • /
    • pp.639-656
    • /
    • 2006
  • In order to apply the leak before break (LBB) concept to nuclear piping systems, the dynamic strain aging effect of low carbon steel materials has to be taken into account, in compliance with the requirements of the Korean Standard Review Guide (KSRG) 3.6.3-1. For this goal, J-R tests are needed for a range of various temperatures and loading rates, including dynamic loading conditions. In the dynamic loading J-R test, the unloading compliance method can not be applied to measure the crack growth and direct current potential drop (DCPD) method; this method also has a problem defining the crack initiation point. The normalization method is known as a very useful method to determine the J-R curve under dynamic loading because it does not need additional equipment or complicated loading sequences such as electric current or unloading. This method was accepted by the American Society for Testing and Materials (ASTM) as a standard test method E1820 A15 in 2001. However, it has not yet been clearly verified yet if the normalization method is sufficiently reliable to be applied to LBB. In this study, the basic background of the J-integral, LBB and dynamic loading J-R test are explained, and the current status for dynamic loading J-R test methods are reviewed from the view point of LBB for nuclear piping. In particular, the theoretical and historical background of the normalization method which has received attention recently, is summarized. Recent studies for this method are introduced and future works are suggested that may improve the reliability of LBB for nuclear piping.

흰 광폭평판 시험을 이용한 원자력 배관의 파괴거동예측 (Prediction of Failure Behavior for Nuclear Piping Using Curved Wide-Plate Test)

  • 허남수;김윤재;최재붕;김영진;임혁순;정대율
    • 대한기계학회논문집A
    • /
    • 제28권4호
    • /
    • pp.352-361
    • /
    • 2004
  • One important element of the Leak-Before-Break analysis of nuclear piping is how to determine relevant fracture toughness (or the J-resistance curve) for nonlinear fracture mechanics analysis. The practice to use fracture toughness from a standard C(T) specimen is known to often give conservative estimates of toughness. To improve the accuracy, this paper proposes a new method to determine fracture toughness using a nonstandard testing specimen, curved wide-plate in tension. To show validity of the proposed curved wide-plate test, the J-resistance curve from the full-scale pipe test is compared with that from the curved wide-plate test and that from the C(T) specimen. It is shown that the J-resistance curve form the curved wide-plate tension test is similar to, but that from the C(T) specimen is lower than, the J-resistance curve from the full-scale pipe test. Further validation is performed by investigating crack-tip constraint conditions via detailed 3-D FE analyses, which shows that the crack-tip constraint condition in the curved wide-plate tension specimen is indeed similar to that in the full-scale pipe under bending.

초고강도 콘크리트의 인발하중과 압축강도와의 관계 (The Relation between Pullout Load and Compressive Strength of Ultra-High-Strength Concrete)

  • 고훈범;김기태
    • 한국건축시공학회지
    • /
    • 제18권1호
    • /
    • pp.17-24
    • /
    • 2018
  • 비파괴 시험 중 선 매입 인발시험법은 아마도 현장의 콘크리트 압축강도를 평가하기 위해 널리 사용되는 기술이라고 할 수 있다. 인발시험은 콘크리트 타설 전에 특별히 계획된 형태의 철재 봉을 설치하여 콘크리트가 굳은 다음 그 봉을 인발하여 그때의 하중을 측정하여 콘크리트 강도를 평가하는 방법으로 미국과 캐나다에서는 콘크리트 구조물 공사중에 콘크리트 강도를 결정하는 신뢰할 만한 시험법으로 각각 ASTM C 900과 CSA A23.2에 규격화 되어 있다. 직경 12mm볼트에 홈이 파인 파단형 인발 볼트와 인발너트, 그리고 로드셀이 필요 없는 오일유압펌프로 구성된 간이인발시험법을 초고강도 콘크리트 강도를 추정하기 위하여 제안되었다. 인발시험과 간이인발시험의 이점을 검증하기 위하여, 80MPa 및 100MPa 급 두 가지 유형의 콘크리트로 제작된 4개의 시험벽체와 2개의 슬래브를 대상으로 로드셀을 장착한 간이인발시험을 사용하여 인발시험을 실시하였다. 인발하중과 콘크리트 압축강도, 파단형 인발볼트의 파단 여부를 재령 7일까지는 매일, 그리고 14일, 21일, 28일, 90일에 측정하였다. 인발하중과 콘크리트 압축강도의 상관곡선은 매우 높은 신뢰도를 보여주었으며, 따라서 인발시험이 현장에서 구조물의 초고강도 콘크리트 강도를 평가할 수 있다는 것을 확인할 수 있었다. 파단형 인발볼트 직경과 콘크리트 강도와의 관계식으로 y=0.0184+5.4(x=콘크리트 압축강도(MPa), y=파단형 인발볼트 직경(mm))를 제안하였다. 본 연구에서 얻은 결과로 간이인발시험은 유용하며 저비용, 간편성 및 편의성에 대한 가능성이 검증되었다.

K-ToBI (Korean ToBI) Labelling Conventions (Version 3.0)

  • Juo, Suo-Ah
    • 음성과학
    • /
    • 제7권1호
    • /
    • pp.143-169
    • /
    • 2000
  • This chapter presents an overview of Korean intonational structure and proposes a revised version of K -ToBI (Korean TOnes and Break Indices), a prosodic transcription convention for Seoul Korean. In the new version of K-ToBI, a tone tier is separated into two tiers: a phonological tone tier and a phonetic tone tier. A phonological tone tier labels tones marking the prosodic structure of an utterance, and a phonetic tone tier labels individual tones of an AP and an IP conforming to the surface pitch contour. Labelling surface tonal patterns will provide us data to test the underlying tonal patterns and to build phonetic implementation rules.

  • PDF

국어 낭독체 발화의 운율경계 예측 (Prediction of Break Indices in Korean Read Speech)

  • 김효숙;김정원;김선주;김선철;김삼진;권철홍
    • 대한음성학회지:말소리
    • /
    • 제43호
    • /
    • pp.1-9
    • /
    • 2002
  • This study aims to model Korean prosodic phrasing using CART(classification and regression tree) method. Our data are limited to Korean read speech. We used 400 sentences made up of editorials, essays, novels and news scripts. Professional radio actress read 400sentences for about two hours. We used K-ToBI transcription system. For technical reason, original break indices 1,2 are merged into AP. Differ from original K-ToBI, we have three break index Zero, AP and IP. Linguistic information selected for this study is as follows: the number of syllables in ‘Eojeol’, the location of ‘Eojeol’ in sentence and part-of-speech(POS) of adjacent ‘Eojeol’s. We trained CART tree using above information as variables. Average accuracy of predicting NonIP(Zero and AP) and IP was 90.4% in training data and 88.5% in test data. Average prediction accuracy of Zero and AP was 79.7% in training data and 78.7% in test data.

  • PDF

소맥의 등숙에 따른 제분특성의 변화 (Changes in Mining Properties During Maturation of Wheat Kernel)

  • 김경제;장학길
    • 한국작물학회지
    • /
    • 제30권4호
    • /
    • pp.381-387
    • /
    • 1985
  • 밀의 등숙에 따른 종실의 품질과 제분특성에 대하여 검토하였다. 천립중과 용적중은 등숙이 진행됨에 따라 그리고 수분함량이 감소함에 따라 증가하였으며 출수후 40일이 성숙기로 추정되었다. 종실의 수분함량과 천립중 및 용적중은 각각 -0.877** 및 -0.761**의 부의 상관이 있었으며, Pearling index와는 0.915**의 정의 상관이 있었다. 제분특성과 관련된 배유는 등숙초기에도 종실의 많은 부분을 차지하고 있었으나 제분평점은 출수후 40일이 되어서야 일정수준에 도달하였다. Break-Reduction flour ratio는 품종에 따라 큰 차이가 있었으며, 특히 조광은 높은 Break-Reduction flour ratio를 보였다. 천립중과 제분율, 회분함량 및 제분평점과는 0.603**, -0.958** 및 0.956**의 고도의 상관이 있었다.

  • PDF

원전 배관 파단전누설 평가를 위한 탄소성 파괴역학 평가 프로그램 개발 (Development of Elastic-Plastic Fracture Mechanics Evaluation Program for Leak-Before-Break Analysis of Nuclear Piping)

  • 박준근;허남수;김예지;이상민
    • 한국압력기기공학회 논문집
    • /
    • 제16권2호
    • /
    • pp.35-46
    • /
    • 2020
  • In this paper, a fracture mechanics evaluation system which can be used to assess the leak-before-break (LBB) of nuclear piping is developed. Existing solutions for calculating the fracture mechanics parameters (J-integral and crack opening displacement) required for LBB evaluation were firstly presented. Then a module for calculating J-integral and COD was developed, with an additional module for predicting the critical load based on the crack driving force diagram to finally develop a fracture mechanics evaluation system. To confirm the validity of the proposed evaluation system, finite element (FE) analysis was performed, and the FE J-integral and COD results were compared with prediction results using the J-integral and COD estimations program. Furthermore, the critical load assessment module was verified by comparing the actual pipe test results (Battelle test data) with prediction results using the proposed program.

중의적 문장 인지에 있어서의 구경계의 영향 (The Influence of Phrasing on the Perception of Ambiguous Sentences)

  • 강선미;김기호;이주경
    • 음성과학
    • /
    • 제14권4호
    • /
    • pp.65-80
    • /
    • 2007
  • This experimental study is designed to investigate the acoustic cues produced by English native speakers in order to disambiguate the ambiguous sentences. This study also investigates whether Korean learners of English and English native speakers can perceive the appropriate meanings from the sentences produced with those acoustic cues. In the perception test, English native speakers successfully found out the proper meaning, utilizing the intonational cues, while Korean learners had difficulties in distinguishing the differences in meaning. The break interval was manipulated in order to see whether the pause duration facilitates or interferes with disambiguation. Though phrasing played an important role in disambiguation, the break interval itself did not have influence on it. The result, therefore, suggests that the tonal realization of phrasal accents and boundary tones seem to be more significant than the break interval in the perception of phrasing.

  • PDF

DEVELOPMENT OF 2D DAM BREAK FLOW ANALYSIS MODEL USING FRACTIONAL STEP METHOD

  • Kim, Dae-hong;Kim, Woo-gu;Chae, Hyo-sok;Park, Sang-geun
    • Water Engineering Research
    • /
    • 제3권1호
    • /
    • pp.23-30
    • /
    • 2002
  • A numerical model for the solution of two-dimensional dam break problems using fractional step method is developed on unstructured grid. The model is based on second-order Weighted Averaged Flux(WAF) scheme with HLLC approximate Riemann solver. To control the nonphysical oscillations associated with second-order accuracy, TVD scheme with SUPERBEE limiter is used. The developed model is verified by comparing the computational solutions with analytic solutions in idealized test cases. Very good agreements have been achieved in the verifications.

  • PDF

LBLOCA AND DVI LINE BREAK TESTS WITH THE ATLAS INTEGRAL FACILITY

  • Baek, Won-Pil;Kim, Yeon-Sik;Choi, Ki-Yong
    • Nuclear Engineering and Technology
    • /
    • 제41권6호
    • /
    • pp.775-784
    • /
    • 2009
  • This paper summarizes the tests performed in the ATLAS facility during its first two years of operation (2007${\sim}$2008). Two categories of tests have been performed successfully: (a) the reflood phase of the large-break loss-of-coolant accidents in a cold leg, and (b) the breaks in one of four direct vessel injection lines. Those tests contributed to understanding the unique thermal-hydraulic behavior, resolving the safety-related concerns and providing an evaluation of the safety analysis codes and methodology for the advanced pressurized water reactor, APR1400. Several important and interesting phenomena have been observed during the tests. In most cases, the ATLAS shows reasonable accident characteristics and conservative results compared with those predicted by one-dimensional safety analysis codes. A wide variety of small-break LOCA tests will be performed in 2009.