• 제목/요약/키워드: corrosion test loop

검색결과 25건 처리시간 0.02초

CHEMICAL EFFECTS ON PWR SUMP STRAINER BLOCKAGE AFTER A LOSS-OF-COOLANT ACCIDENT: REVIEW ON U.S. RESEARCH EFFORTS

  • Bahn, Chi Bum
    • Nuclear Engineering and Technology
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    • 제45권3호
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    • pp.295-310
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    • 2013
  • Industry- or regulatory-sponsored research activities on the resolution of Generic Safety Issue (GSI)-191 were reviewed, especially on the chemical effects. Potential chemical effects on the head loss across the debris-loaded sump strainer under a post-accident condition were experimentally evidenced by small-scale bench tests, integrated chemical effects test (ICET), and vertical loop head loss tests. Three main chemical precipitates were identified by WCAP-16530-NP: calcium phosphate, aluminum oxyhydroxide, and sodium aluminum silicate. The former two precipitates were also identified as major chemical precipitates by the ICETs. The assumption that all released calcium would form precipitates is reasonable. CalSil insulation needs to be minimized especially in a plant using trisodium phosphate buffer. The assumption that all released aluminum would form precipitates appears highly conservative because ICETs and other studies suggest substantial solubility of aluminum at high temperature and inhibition of aluminum corrosion by silicate or phosphate. The industry-proposed chemical surrogates are quite effective in increasing the head loss across the debris-loaded bed and more effective than the prototypical aluminum hydroxide precipitates generated by in-situ aluminum corrosion. There appears to be some unresolved potential issues related to GSI-191 chemical effects as identified in NUREG/CR-6988. The United States Nuclear Regulatory Commission, however, concluded that the implications of these issues are either not generically significant or are appropriately addressed, although several issues associated with downstream in-vessel effects remain.

DEPENDENCY OF SINGLE-PHASE FAC OF CARBON AND LOW-ALLOY STEELS FOR NPP SYSTEM PIPING ON PH, ORIFICE DISTANCE AND MATERIAL

  • Moon, Jeong-Ho;Chung, Hung-Ho;Sung, Ki-Woung;Kim, Uh-Chul;Rho, Jae-Seong
    • Nuclear Engineering and Technology
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    • 제37권4호
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    • pp.375-384
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    • 2005
  • To investigate the flow-accelerated corrosion (FAC) dependency of carbon steel (A106 Gr. B) and low-alloy steels (1Cr-1/2Mo, 21/4Cr-1Mo) on pH, orifice distance, and material, experiments were carried out. These experiments were performed using a flow velocity of 4 m/sec (partly 9 m/sec) at pH $8.0\~10.0$ in an oxygen-free aqueous solution re-circulated in an Erosion-Corrosion Test Loop at $130^{\circ}\;{\ldots}$ for 500 hours. The weight loss of the carbon steel specimens appeared to be positively dependent on the flow velocity. That of the carbon and low-alloy steel specimens also showed to be distinguishably dependent on the pH. At pH levels of $8.0\~9.5$ it decreased, but increased from 9.5 to 10.0. Utility water chemistry personnel should carefully consider this kind of pH dependency to control the water system pH to mitigate FAC of the piping system material. The weight loss of the specimens located further from the orifice in the distance range of $6.8\~27.2$ mm was shown to be greater, except for 21/4Cr-1Mo, which showed no orifice distance dependency. Low alloy steel specimens exhibited a factor of two times better resistance to FAC than that of the carbon steel. Based on this kind of FAC dependency of the carbon and low-alloy steels on the orifice distance and material, we conclude that it is necessary to alternate the composition of the secondary piping system material of NPPs, using low-alloy steels, such as 21/4Cr-1Mo, particularly when the system piping has to be replaced.

전기화학적 방법에 의한 주조 스테인리스강 CF8M $\sigma$상 열화평가 (Evaluation of the $\sigma$-Phase Degradation for Cast Stainless Steel CF8M by the Electrochemical Method)

  • 권재도;김중형;박중철;변장환;이우호
    • 대한기계학회논문집A
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    • 제23권11호
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    • pp.2014-2021
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    • 1999
  • The present investigation is concerned with the degradation characteristics of cast stainless steel(CF8M), exposed to the $\sigma$-phase degradation at $700^{\circ}C$. In the present paper, the degradation of CF8 M at $700^{\circ}C$ is evaluated by a non-destructive test, DL-EPR(double loop electrochemical potentiokinetic reactivation). The surface of specimens is observed by using scanning electron microscopy after DL-EPR test. Also. chromium contents of matrix, grain boundary and ferrite phase are analyzed by electron probe X-ray micro analyzer. Through the experiments, the following results are obtained 1) The degree of sensitization(DOS) of CF8M aged up to 15hr at $700^{\circ}C$ is increased with acing time while that is decreased with aging time from 15hr to 150hr. 2) The impact energy decreases with increase of $\sigma$-phase while DOS increases with $\sigma$-phase until aging time reaches to 15hr. After the aging time. 15hr, the $\sigma$-phase and the rate of impact energy with respect to aging time decreases. Therefore the degradation behavior of the CF8M can be evaluated by comparing SEM micrographs and the value of DOS.

저사이클 피로하중을 받는 316L 스테인리스강의 피로수명 분석 및 예측 (Fatigue Life Analysis and Prediction of 316L Stainless Steel Under Low Cycle Fatigue Loading)

  • 오혁;명노준;최낙삼
    • 대한기계학회논문집A
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    • 제40권12호
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    • pp.1027-1035
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    • 2016
  • 내식성과 기계적 성능이 우수한 316L 스테인리스 강의 저주기 변형률제어 피로시험에서 3가지 변형률진폭과 3가지 변형률비의 조건이 피로수명에 미치는 효과를 분석하였다. 낮은 변형률범위에서 곡선이 거의 중첩되는 Masing 거동이 나타나고, 높은 변형률범위에서 비선형거동 응력범위가 서로 크게 벗어나는 non-Masing 거동과 함께 평균응력의 감소가 나타났다. 소성 변형률에너지를 이용하여 저주기 피로수명을 예측하고 non-Masing 거동을 고려한 수명예측 방법의 정확성 여부를 검토하였다. 각각의 변형률진폭과 변형률비의 조건에서 초기 수 사이클 동안 반복경화 현상 후 장시간동안 점진적으로 낮아져 연화하다가 파괴 되었다. 저사이클 피로수명을 정확히 예측하기 위해서는 변형률진폭에 따라 Masing 및 non-Masing 거동을 구분하고, 이를 반영한 수명예측식을 적용해야 함을 알았다.

증기발생기 2차측 제철화학세정액의 고온적용 (High Temperature Application of Iron Removal Chemical Cleaning Solvent in the Secondary Side of Nuclear Steam Generators)

  • 허도행;이은희;정한섭;김우철
    • Nuclear Engineering and Technology
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    • 제26권1호
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    • pp.140-148
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    • 1994
  • 원전 증기발생기 2차측 제철 화학세정을 기존의 93$^{\circ}C$ 표준공정보다 고온인 1$25^{\circ}C$에서 검증시험을 수행하였다. 원전 증기발생기를 1$25^{\circ}C$에서 화학 세정한다는 가정아래 현장세정 조건을 결정하고 이를 다시 모사하여 3l 용량의 소형 검증시험 조건을 결정하였다. 1 gallon 용량의 316 스텐레스강 압력용기를 반응용기로 사용하는 화학세정 시험장치에서 검증시험을 수행하여 스러지 용해거동, 모재 부식률, 세정제 화학조성 변화거동 등을 측정하였다. 1$25^{\circ}C$ 검증시험 결과에서 93$^{\circ}C$ 표준공정보다 세정시간을 절반이하로 단축시키고도 더 효율적인 세정효과를 얻을 수 있을 뿐만이 아니라 2차측 모재의 부식률도 감소함을 확인할 수 있었다. 그러나 고온 세정공정은 아직 현장적용 경험이 없고, 별도의 외부순환 세정 장치를 이용하는 93$^{\circ}C$ 표준공정과는 달리 주냉각재의 잠열로 2차측을 가열하므로 세정이 완료될 때까지 주냉각 펌프를 계속 가동하여야 하는 단점이 있다. 가동중인 증기발생기에 대한 화학세정을 수행할 때 93$^{\circ}C$ 표준공정과 고온공정의 장 단점을 신중히 검토하여 최적공정을 적용하여야 할 것이다.

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