• Proceedings of the Korean Nuclear Society Conference
• /
• 1998.10a
• /
• pp.305-305
• /
• 1998

• Proceedings of the Korean Nuclear Society Conference
• /
• 2001.10a
• /
• pp.330.1-330
• /
• 2001

• Journal of Radiation Protection and Research
• /
• v.29 no.3
• /
• pp.187-196
• /
• 2004

The health effects resulting from severe accidents of typical 1,000MWe KSNP(Korea Standard Nuclear Plant) PWR and typical 600MWe CANDU(CANada Deuterium Uranium) plants were estimated and compared. The population distribution of the site extending to 80km for both site were considered. The releaese fraction for various source term categories(STC) and core inventories were used in the estimation of the health effects risks by using the MACCS2(MELCOR Accident Consequence Code System2) code. Individuals are assumed to evacuate beyond 16km from the site. The health effects considered in this comparative study are early and cancer fatality risk, and the results are presented as CCDF(Complementary Cumulative Distribution Function) curves considering the occurrence probability of each STC's. According to the results, the early and cancer fatality risks of PHWR plants we lower than those of PWR plants. This is attributed the fact that the amount of radioactive mateials that released to the atmosphere resulting from the postulated severe accidents of PHWR plants are smaller than that of PWR plants. And, the dominating initiating event of STC that shows maximum early and cancer fatality risk is SGTR(Steam Generator Tube Rupture) for both plants. Therefore, the appropriated actions must be taken to reduce the occurrence probability and the amounts of radioactive materials released to the environment in order to protect the public for both PWR and PHWR plants.

• Proceedings of the Korean Nuclear Society Conference
• /
• 2002.05a
• /
• pp.363.1-363
• /
• 2002

• Proceedings of the Korean Nuclear Society Conference
• /
• 2002.05a
• /
• pp.131.1-131
• /
• 2002

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2004.06a
• /
• pp.247-247
• /
• 2004

가압 중수로형 원자력발전소에서는 원자로의 감속재 및 냉각재로 사용하는 중수(heavy water)로 인한 삼중수소(tritium)의 생성이 전체 방사선 준위 상승의 가장 중요한 원인이 되고 있다. 따라서 4기의 중수로가 운전 중인 우리나라에서도 월성원자력 발전소에 삼중수소 제거 설비(Tritium Removal Facility)가 건설 중에 있다. 이 시설로부터 99% 이상의 순도인 삼중수소가 회수되며, 회수된 삼중수소는 장기적인 저장을 위하여 안전하게 포장되어야 한다.(중략)

• Proceedings of the Korean Institute of Industrial Safety Conference
• /
• 2003.05a
• /
• pp.345-353
• /
• 2003

탄소강은 가공성과 용접성이 우수하기 때문에 각종 산업설비의 배관재로 많이 사용되고 있으며, 특히 가압중수로형 원전의 1차측 배관과 가압경수로형 원전의 2차측 배관에 주로 사용되고 있다. 그러나 탄소강 배관은 부식에 취약하므로 유동가속부식(FAC, Flow Accelerated Corrosion) 현상에 의한 배관의 두께가 감소하는 감육 손상이 중요하게 대두되고 있는 실정이다. 이러한 감육현상은 다른 어떤 설비보다 안전성의 확보가 강조되고 있는 원전 배관의 경우에 있어서는 특히 중요한 건전성 저해요인으로 인식되고 있다.(중략)

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2004.06a
• /
• pp.222-222
• /
• 2004

가압 중수로형 원자력발전소에서는 중수 중의 중수소와 중성자의 반응에 의하여 수소동위원소인 삼중수소(트리튬)가 불가피하게 생성되는데 발전소의 가동 년수가 증가함에 따라 계통내 중수중의 삼중수소 농도도 증가하게 된다. 따라서 계통내 삼중수소화 중수로부터 삼중수소를 분리하여, 중수는 원자로로 순환하고 분리된 삼중수소는 별도로 저장할 필요가 있다. 이 과정에서 분리$\cdot$농축된 삼중수소는 방사성 물질일 뿐만 아니라 앞으로 핵융합 연구에 매우 중요하게 이용되어야 할 자원이기 때문에 이를 안전하게 저장하기 위한 기술(저장기술)과 경우에 따라 지정된 장소로 운반하기 위한 기술(운반기술)이 필요하다.(중략)

• Journal of the Korean Society for Nondestructive Testing
• /
• v.25 no.4
• /
• pp.294-303
• /
• 2005

This paper describes the analysis results of a series f Round-Robin test that was performed to intercompare inspection and diagnosis techniques for characterization of pressure tube f a pressurized heavy water reactor under the Coordinated Research Project(CRP) of IAEA's nuclear Power Programme. For this test, six nations, Korea, Canada, India, Argentina, Rumania, and China that currently have pressurized heavy water reactors under operation involved, and the "KOR-1" pressure tube sample prepared by Korea was used. Two kinds of NDE technique, ultrasonic and eddy current test, were applied for these tests. The "KOR-1" pressure tube sample contains total 12 artificial flaws such as crack-like EDM notches, wear that is similar to the real flaws and can be produced on the pressure tubes during plant operation. Test results showed that seven laboratories from six nations detected all twelve flaws in "KOR-1" specimen by using ultrasonic and eddy current test methods, and ultrasonic test method was more accurate than eddy current test method in flaw detectin and sizing. ID flaws in pressure tube sample were more easily detected and accurately sized than OD flaws.

• Transactions of the Korean Society of Pressure Vessels and Piping
• /
• v.6 no.1
• /
• pp.72-77
• /
• 2010

During the period of reinforcement work for the licensing renewal of CANDU NPP, the fuel channels, Calandria tubes and feeders of CANDU Reactor are replaced. The remote visual inspection of Calandria internal is also performed during the period of reinforcement work. This period is a unique opportunity to inspect the inside of the Calandria. The visual inspection for the Calandria vessel and its internals of Wolsong NPP Unit 1 was performed by Nuclear Engineering & Technology Institute(NETEC) of KHNP. To perform this inspection, NETEC developed equipment applied new technology such as the synchronization of 3D CAD, automatic alignment and control system. The inspection confirmed that the Calandria integrity of Wolsong NPP Unit 1 is perfect.