• 제목/요약/키워드: Nuclear damage

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Application of Low Voltage High Resistance Grounding in Nuclear Power Plants

  • Chang, Choong-Koo;Hassan, Mostafa Ahmed Fouad
    • Nuclear Engineering and Technology
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    • 제48권1호
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    • pp.211-217
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    • 2016
  • Most nuclear power plants now utilize solid grounded low voltage systems. For safety and reliability reasons, the low voltage (LV) high resistance grounding (HRG) system is also increasingly used in the pulp and paper, petroleum and chemical, and semiconductor industries. Fault detection is easiest and fastest with a solidly grounded system. However, a solidly grounded system has many limitations such as severe fault damage, poor reliability on essential circuits, and electrical noise caused by the high magnitude of ground fault currents. This paper will briefly address the strengths and weaknesses of LV grounding systems. An example of a low voltage HRG system in the LV system of a nuclear power plant will be presented. The HRG system is highly recommended for LV systems of nuclear power plants if sufficient considerations are provided to prevent nuisance tripping of ground fault relays and to avoid the deterioration of system reliability.

A DEVELOPMENT FRAMEWORK FOR SOFTWARE SECURITY IN NUCLEAR SAFETY SYSTEMS: INTEGRATING SECURE DEVELOPMENT AND SYSTEM SECURITY ACTIVITIES

  • Park, Jaekwan;Suh, Yongsuk
    • Nuclear Engineering and Technology
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    • 제46권1호
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    • pp.47-54
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    • 2014
  • The protection of nuclear safety software is essential in that a failure can result in significant economic loss and physical damage to the public. However, software security has often been ignored in nuclear safety software development. To enforce security considerations, nuclear regulator commission recently issued and revised the security regulations for nuclear computer-based systems. It is a great challenge for nuclear developers to comply with the security requirements. However, there is still no clear software development process regarding security activities. This paper proposes an integrated development process suitable for the secure development requirements and system security requirements described by various regulatory bodies. It provides a three-stage framework with eight security activities as the software development process. Detailed descriptions are useful for software developers and licensees to understand the regulatory requirements and to establish a detailed activity plan for software design and engineering.

A numerical study on the damage of projectile impact on concrete targets

  • Lu, Gang;Li, Xibing;Wang, Kejin
    • Computers and Concrete
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    • 제9권1호
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    • pp.21-33
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    • 2012
  • This paper presents the numerical simulation of the rigid 12.6 mm diameter kinetic energy ogive-nosed projectile impact on plain and fiber reinforced concrete (FRC) targets with compressive strengths from 45 to 235 MPa, using a three-dimensional finite element code LS-DYNA. A combined dynamic constitutive model, describing the compressive and tensile damage of concrete, is implemented. A modified Johnson_Holmquist_Cook (MJHC) constitutive relationship and damage model are incorporated to simulate the concrete behavior under compression. A tensile damage model is added to the MJHC model to analyze the dynamic fracture behavior of concrete in tension, due to blast loading. As a consequence, the impact damage in targets made of plain and fiber reinforced concrete with same matrix material under same impact velocities (650 m/s) are obtained. Moreover, the damage distribution of concrete after penetration is procured to compare with the experimental results. Numerical simulations provide a reasonable prediction on concrete damage in both compression and tension.

신뢰도지수 및 몬데카를로 시뮬레이션을 이용한 원전 감육배관의 확률론적 손상역학 평가 (Probabilistic Damage Mechanics Assessment of Wall-Thinned Nuclear Piping Using Reliability Method and Monte-Carlo Simulation)

  • 이상민;윤강옥;장윤석;최재붕;김영진
    • 대한기계학회논문집A
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    • 제29권8호
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    • pp.1102-1108
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    • 2005
  • The integrity of nuclear piping systems has to be maintained sufficiently all the times during operation. In order to maintain the integrity, reliable assessment procedures including fracture mechanics analysis, etc, are required. Up to now, the integrity assessment has been performed using conventional deterministic approach even though there are lots of uncertainties to hinder a rational evaluation. In this respect, probabilistic approach is considered as an appropriate method for piping system evaluation. The objectives of this paper are to develop a probabilistic assessment program using reliability index and simulation technique and to estimate the damage probability of wall-thinned pipes in secondary systems. The probabilistic assessment program consists of three evaluation modules which are first order reliability method, second order reliability method and Monte Carlo simulation method. The developed program has been applied to evaluate damage probabilities of wall-thinned pipes subjected to internal pressure, global bending moment and combined loading. The sensitivity analysis results as well as prototypal evaluation results showed a promising applicability of the probabilistic integrity assessment program.

항공, 바이오, 원자력 부품의 프레팅 마모 현상 비교 연구 (Comparative study on fretting wear of aerospace, biomedical, and nuclear components)

  • 전태성;김경목
    • 항공우주시스템공학회지
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    • 제11권2호
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    • pp.16-22
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    • 2017
  • 본 논문에서는 항공, 바이오 및 원자력 부품들에서 발생하는 프레팅 마모 현상이 비교 연구되었다. 프레팅 마모 손상에 영향을 미치는 실험적 인자들을 확인하였으며 각 부품에서 관찰된 실험 인자들의 크기들을 직접 비교하였다. 초당 진동수, 상대적 변위, 그리고 수직하중의 크기는 프레팅 마모가 발생하는 부품에 따라 다양했다. 프레팅 마모 손상을 최소화시키는 최근 해결책들이 조사되었으며 저마찰 코팅 적층, 표면 처리, 기저 재료 및 접촉 형상 최적 설계 등이 해결책으로 소개되었다. 본 연구는 프레팅 마모 손상을 분석하고 마찰 부품을 설계하는데 유용한 방법과 해결책을 제공한다.

Gamma-tocopherol ameliorates hyperglycemia-induced hepatic inflammation associated with NLRP3 inflammasome in alloxan-induced diabetic mice

  • Lee, Heaji;Lim, Yunsook
    • Nutrition Research and Practice
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    • 제13권5호
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    • pp.377-383
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    • 2019
  • BACKGROUND/OBJECTIVES: Hyperglycemia-induced hepatic damage has been recognized as one of the major cause of complications in diabetes. Hepatic complications are associated with inflammation and oxidative stress in diabetes. In this study, we investigated the hypothesis that gamma-tocopherol (GT) supplementation ameliorates NLRP3 inflammasome associated hepatic inflammation in diabetes. MATERIALS/METHODS: Diabetes was induced by the intraperitoneal injection of alloxan (150 mg/kg. BW) in ICR mice. All mice were fed with a control diet (AIN-76A). After diabetes was induced (fasting glucose level ${\geq}250mg/dL$), the mice were treated with tocopherol-stripped corn oil or GT-supplemented (35 mg/kg) corn oil, respectively, by gavage for 2 weeks. RESULTS: GT supplementation reduced fasting blood glucose levels in diabetic mice relative to non-treated diabetic mice. Moreover, GT supplementation ameliorated hyperglycemia-induced hepatic damage by regulation of NOD-like receptor protein 3 (NLRP3)-inflammasome associated inflammation represented by NLRP3, apoptosis-associated speck-like protein containing a caspase-recruitment domain, caspase-1, nuclear $factor-{\kappa}B$ pathway as well as oxidative stress demonstrated by nuclear factor erythroid 2-related factor 2, NAD(P)H dehydrogenase quinone 1, catalase and glutathione-dependent peroxidase in diabetic mice. CONCLUSION: The findings suggested that GT supplementation ameliorated hepatic damage by attenuating inflammation and oxidative stress in alloxan-induced diabetic mice. Taken together, GT could be a beneficial nutrient that can ameliorate inflammatory responses associated with NLRP3 inflammasome in hyperglycemia-induced hepatic damage.

Toughness and microscopic pore structure analysis of pasture fiber recycled concrete

  • Hailong Wang;Lei Wang;Hong Yang
    • Advances in concrete construction
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    • 제16권3호
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    • pp.141-153
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    • 2023
  • In order to develop and take full advantage of pasture fiber and waste concrete, this article studied how different amounts of pasture fiber influenced the toughness and pore structure of concrete with different replacement rates of recycled fine aggregate. Pasture fiber recycled concrete constitutive equations were established under idealized stiffness and toughness damage rate, based on fracture energy and damage mechanics theories. The relationship between pore structure and toughness was studied utilizing nuclear magnetic resonance and fractal theory. The toughness of text groups (0% (JZ), 10% (ZS10), 20% (ZS20)) first increased and then decreased with increasing amounts of pasture fiber, based on the damage rate of toughness. The toughness of concrete samples with recycled fine aggregate and pasture fiber is negatively correlated to the fractal dimension of small and medium-sized pores with a pore size of 0-500 nm. At a replacement rate of 10% of the recycled fine aggregate, the fractal dimension of the air voids (r: 500-9000 nm, i.e., Lg(r) ∈ [2.7, 3.9]) shows a gradual decrease with the increase of grass fiber dosage, indicating that with such a replacement rate of the recycled fine aggregate, the increase of pasture fiber can reduce the complexity of the pore structure of the air voids (500-9000 nm).

X-Ray Diffraction line profile analysis of defects and precipitates in high displacement damage neutron-irradiated austenitic stainless steels

  • Shreevalli M.;Ran Vijay Kumar;Divakar R.;Ashish K.;Padmaprabu C.;Karthik V.;Archna Sagdeo
    • Nuclear Engineering and Technology
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    • 제56권1호
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    • pp.114-122
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    • 2024
  • Irradiation-induced defects and the precipitates in the wrapper material of the Indian Fast Breeder Test Reactor (FBTR), SS 316 are analyzed using the synchrotron source-based Angle Dispersive X-Ray Diffraction (ADXRD) technique with X-rays of energy 17.185 keV (wavelength ~0.72146 Å). The differences and similarities in the high displacement damage samples as a function of dpa (displacement per atom) and dpa rate in the range of 2.9 × 10-7- 9 × 10-7 dpa/s are studied. Ferrite and M23C6 are commonly observed in the present set of high displacement damage 40-74 dpa SS 316 samples irradiated at temperatures in the range of 400-483 ℃. Also, the dislocation density has increased as a function of the irradiation dose. The X-ray diffraction peak profile parameters quantified such as peak shift and asymmetry show that the irradiation-induced defects are sensitive to the dpa rate-irradiation temperature combinations. The increase in yield strength as a function of displacement damage is also correlated to the dislocation density.

EFFECT OF HEAT CURING METHODS ON THE TEMPERATURE HISTORY AND STRENGTH DEVELOPMENT OF SLAB CONCRETE FOR NUCLEAR POWER PLANT STRUCTURES IN COLD CLIMATES

  • Lee, Gun-Che;Han, Min-Cheol;Baek, Dae-Hyun;Koh, Kyung-Taek
    • Nuclear Engineering and Technology
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    • 제44권5호
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    • pp.523-534
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    • 2012
  • The objective of this study was to experimentally investigate the effect of heat curing methods on the temperature history and strength development of slab concrete exposed to $-10^{\circ}C$. The goal was to determine proper heat curing methods for the protection of nuclear power plant structures against early-age frost damage under adverse (cold) conditions. Two types of methods were studied: heat insulation alone and in combination with a heating cable. For heat curing with heat insulation alone, either sawdust or a double layer bubble sheet (2-BS) was applied. For curing with a combination of heat insulation and a heating cable, an embedded heating cable was used with either a sawdust cover, a 2-BS cover, or a quadruple layer bubble sheet (4-BS) cover. Seven different slab specimens with dimensions of $1200{\times}600{\times}200$ mm and a design strength of 27 MPa were fabricated and cured at $-10^{\circ}C$ for 7 d. The application of sawdust and 2-BS allowed the concrete temperature to fall below $0^{\circ}C$ within 40 h after exposure to $-10^{\circ}C$, and then, the temperature dropped to $-10^{\circ}C$ and remained there for 7 d owing to insufficient thermal resistance. However, the combination of a heating cable plus sawdust or 2-BS maintained the concrete temperature around $5^{\circ}C$ for 7 d. Moreover, the combination of the heating cable and 4-BS maintained the concrete temperature around $10^{\circ}C$ for 7 d. This was due to the continuous heat supply from the heating cable and the prevention of heat loss by the 4-BS. For maturity development, which is an index of early-age frost damage, the application of heat insulation materials alone did not allow the concrete to meet the minimum maturity required to protect against early-age frost damage after 7 d, owing to poor thermal resistance. However, the combination of the heating cable and the heat insulating materials allowed the concrete to attain the minimum maturity level after just 3 d. In the case of strength development, the heat insulation materials alone were insufficient to achieve the minimum 7-d strength required to prevent early-age frost damage. However, the combination of a heating cable and heat insulating materials met both the minimum 7-d strength and the 28-d design strength owing to the heat supply and thermal resistance. Therefore, it is believed that by combining a heating cable and 4-BS, concrete exposed to $-10^{\circ}C$ can be effectively protected from early-age frost damage and can attain the required 28-d compressive strength.

레이저 스캐닝 및 정상파를 이용한 평판 구조물의 손상탐지 (Damage Detection on Thin-walled Structures Utilizing Laser Scanning and Standing Waves)

  • 강세혁;전준영;김두환;박규해;강토;한순우
    • 대한기계학회논문집A
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    • 제41권5호
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    • pp.401-407
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    • 2017
  • 본 연구에서는 레이저 스캐닝 및 단일 주파수 정상파 가진과 파수 분석을 통해 구조물의 손상을 탐지하는 기법을 개발하였다. 구조물에 부착된 압전소자를 통해 단일 주파수로 가진하고, 이때 발생한 구조물의 정상상태 응답을 레이저 도플러 속도계와 거울 방향조절 장치를 통해 측정하였다. 구조물의 결함을 탐지하기 위해 정상상태 응답에서 파수 필터링을 이용한 손상 탐지 기법을 개발 및 적용하였다. 부식결함이 발생한 알루미늄 평판과 층간 분리가 발생한 복합재료 구조물에 대한 손상 탐지를 수행하여 손상의 위치와 크기를 정확히 파악할 수 있었다.