• Journal of Plant Biology
• /
• 제27권3호
• /
• pp.173-178
• /
• 1984

Callus culture of Phaseolus vulgaris L. was carried out to examine the ability to grow on cytokinin-free medium. Of the sixteen cultivars of P. vulgaris, eight were classified as completely cytokinin-autonomous phenotype and five were found to be cytokinin-dependent phenotype. Intermediate phenotype was shown in three cultivars. Using cv. Palgong and ca 21 as cytokinin-dependent genotypes, the genotype responses to the cytokinin requirements of callus tissue were studied in detail. The callus tissue of cv. Palgong and ca 21 were never habituated in cytokinin-free medium, regardless tissue origin and cytokinin concentration in previous passages. The result suggests that cytokinin dependency of callus tissue of P. vulgaris cv. Palgong and ca 21 may be due to inactivation of cytokinin biosynthetic pathway.

• 산업경영시스템학회지
• /
• 제34권3호
• /
• pp.79-89
• /
• 2011

Since commercial operation of Kori-1 nuclear power plant in 1978, twenty units are under operation and six units are under construction at 2011 present. Nuclear power become a main energy source in our country. However, the plant was constructed by a USA vendor in its beginning period, the Quality Assurance requirements of USA was applied. Even though Quality Assurance requirements were newly established to the Korea Atomic Energy Act, its contents are quite similar to those of USA. And 10 CFR 50 App.B, ASME NQA-1 apply to most of nuclear industries as a quality assurance plan. In this paper, Quality Assurance requirement of domestic nuclear industries has been investigated and applicable method of ISO Quality Assurance application to the nuclear industries is suggested by a comparison ISO 9000 and nuclear quality assurance specification.

• Nuclear Engineering and Technology
• /
• 제51권5호
• /
• pp.1289-1296
• /
• 2019

Non-functional requirements plays a critical role in designing variety of applications domain ranges from safety-critical systems to simple gaming applications. Performance is one of the crucial non-functional requirement, especially in control and safety systems, that validates the design. System risk can be quantified as a product of probability of system failure and severity of its impact. In this paper, we devise a technique to do the performance analysis of safety critical and control systems and to estimate performance based risk factor. The technique elaborates Petri nets to estimate performability to ensure system dependability requirements. We illustrate the technique on a case study of Nuclear Power Plant system. The technique has been validated on 17 safety critical and control systems of Nuclear Power Plant.

• 대한전자공학회:학술대회논문집
• /
• 대한전자공학회 2001년도 The 6th International Symposium of East Asian Resources Recycling Technology
• /
• pp.387-392
• /
• 2001

Kobe Steel, LTD. and Midrex Technologies Inc. jointly developed the FASTMET$\circledR$ process as a steel mill waste recycle technology in which the DRI product meets BF feed material or BOF/EAF feed material requirements. FASTMET(R) process turns value-less wastes into valuable DRI and sellable zinc oxide, and gives the solution for the steel mill wastes recycling from both economical and environmental viewpoints. During the development of the process, Laboratory, Pilot Plant and Demonstration Plant tests were carried out from 1990 to 1998. The first FASTMET(R) commercial plant began operation in April, 2000 and the second commercial plant started in April, 2001 Both commercial plants have proceeded successfully preying that FASTMET$\circledR$ is a suitable process for recycling steel mill waste and for producing DRI as an iron source.

• 한국원자력학회:학술대회논문집
• /
• 한국원자력학회 1998년도 추계학술발표회요약집
• /
• pp.77-77
• /
• 1998

• Nuclear Engineering and Technology
• /
• 제41권8호
• /
• pp.989-994
• /
• 2009

We at Mitsubishi have lined up Gen-III+ solutions for a wide variety of global customers: ATMEA1 of the 1100MWe class, and an APWR with the largest capacity of 1700MWe. In this paper, we would like to introduce the APWR. With an increased requirement for nuclear power generation as an effective countermeasure against global warming, we have established the APWR plant, a large-capacity Mitsubishi standard reactor combining our accumulated experience and technology as an integrated PWR plant supplier. The APWR plant has achieved high reliability, safety and enhanced economy based on a technology that has been developed with the support of the government and utilities through improvement and standardization programs of light water reactors. Currently, Tsuruga Units 3 and 4, the first two APWRs, are undergoing licensing, while we are making efforts to obtain the standard design certification (DC) of US-APWR and preparing for the European Utility Requirements (EUR) compliance assessment of EU-APWR. Mitsubishi Heavy Industries, Ltd. (MHI) positions the APWR as a core technology that will contribute to the prevention of global warming and meet worldwide requirements.

• 대한전기학회논문지
• /
• 제35권6호
• /
• pp.237-245
• /
• 1986

대부분 화력 발전소는 기저부하(base load)운전용으로 설계되어 있어 극심한 부하 변동이 계속되는 부하에 대하여는 일반적으로 적합하지 못하다. 특히 전기로와 압연기가 설치된 제철소에 전력을 공급하는 발전소의 경우 연속적인 심한 부하변동으로 일반적으로 발전소 제어 시스템으로는 적당치 않다. 이 논문에서는 이와 같이 연속적으로 급변하는 부하에 대응할 수 있는 화력 발전소 예상 제어 앨고리즘을 제시 하였다. 상헤한 제어 앨고리즘과 모델 계통에 대한 사례 연구를 첨부하였다.

• International Journal of Fuzzy Logic and Intelligent Systems
• /
• 제3권1호
• /
• pp.112-120
• /
• 2003

This paper reports the development work carried out in respect of a proposed application of Neural Network approach for the Korean Next generation Reactor (KNGR) now referred as APR-1400. The emphasis is on establishing the methodology and the approach to be adopted towards realizing this application in the next generation reactors. Keeping in view the advantages and limitation of Artificial Neural Network Approach, the role of ANN has been limited to plant status or to be more precise plant transient monitoring. The simulation work carried out so far and the results obtained shows that artificial neural network approach caters to the requirements of plant status monitoring and qualifies to be incorporated as a part of proposed operator support systems of the referenced nuclear power plant.

• Nuclear Engineering and Technology
• /
• 제45권5호
• /
• pp.625-636
• /
• 2013

Pressing demands of economic competitiveness, the need for large-scale deployment, minimizing the need of human intervention, and experience from the past events and incidents at operating reactors have guided the evolution and innovations in reactor technologies. Indian innovative reactor 'AHWR' is a pressure-tube type natural circulation based boiling water reactor that is designed to meet such requirements, which essentially reflect the needs of next generation reactors. The reactor employs various passive features to prevent and mitigate accidental conditions, like a slightly negative void reactivity coefficient, passive poison injection to scram the reactor in event of failure of the wired shutdown systems, a large elevated pool of water as a heat sink inside the containment, passive decay heat removal based on natural circulation and passive valves, passive ECC injection, etc. It is designed to meet the fundamental safety requirements of safe shutdown, safe decay heat removal and confinement of activity with no impact in public domain, and hence, no need for emergency planning under all conceivable scenarios. This paper examines the role of the various passive safety systems in prevention and mitigation of severe plant conditions that may arise in event of multiple failures. For the purpose of demonstration of the effectiveness of its passive features, postulated scenarios on the lines of three major severe accidents in the history of nuclear power reactors are considered, namely; the Three Mile Island (TMI), Chernobyl and Fukushima accidents. Severe plant conditions along the lines of these scenarios are postulated to the extent conceivable in the reactor under consideration and analyzed using best estimate system thermal-hydraulics code RELAP5/Mod3.2. It is found that the various passive systems incorporated enable the reactor to tolerate the postulated accident conditions without causing severe plant conditions and core degradation.

• 대한전기학회논문지
• /
• 제34권5호
• /
• pp.193-200
• /
• 1985

Increased attention has been given in recent years to the use of pumped hydrostorage plant to meet the requirements for peak generation and bottom pumping. Once a pumped hydrostorage plant is installed, its economic operation as an integral component of a steam generating system requires the selection of a pumping and generating schedule which will result in the most effective use of the hydro generating capacity. The general object of coordination of pumped hydrostorage plants with electric power system is the minimization of the overall procduction cost and the maximization of generation reserves. This paper presents a method for the optimal scheduling of pumped hydrostorage plant and a computer program which determines weekly operating schedules for a pumped hydrostorage plant by dynamic programming method.