• Journal of Energy Engineering
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• v.24 no.2
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• pp.40-44
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• 2015

Sensitivity on the reactor safety was evaluated for the safety margin and time delay applied to the opening pressure of liquid relief valve(LRV) of the primary heat transport system(PHTS) in the pressurized heavy water reactor(PHWR) type nuclear power plant. Since the LRV is the pressure boundary for the PHTS in the safety analysis, the operating of LRV has a significant effect on the safety analysis results. Therefore it is required during the regulatory review of Wolsong Unit 1 safety analysis to find the safety effect of the application of safety margin and time delay to the LRV opening pressure for the safety analysis of PHTS pressurizing events.

• Proceedings of the Korean Nuclear Society Conference
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• 2001.05a
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• pp.248.2-248
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• 2001

• Journal of Energy Engineering
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• v.25 no.1
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• pp.15-22
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• 2016

The heat transport system transients of Wolsong 2,3,4 nuclear power plants were analysed during abnormal operating conditions. The compliance with requirements of AECB Regulatory Document R-77 for CANDU reactor was estimated. The analysis results showed that for each postulated accident the peak pressure values in the reactor headers are within the acceptance criteria given in ASME code requirements. The effect of LRV that is one of the overpressure protection device was very minor.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05b
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• pp.160-165
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• 1996

중수로형 원전에서 일차측 냉각수를 순환시키는 주연수송펌프가 정상운전중 갑자기 정지하는 사고를 강제순환 상실사고라 한다. 강제순환 상실사고는 주열수송계통을 과도압력상태로 만들며, 일반적으로 펌프에 공급되는 IV등급전원 상실사고와 기계적 손상에 의한 주열수송펌프 고착사고로 분류할 수 있다. 본 논문에서는 강제순환 상실사고에 대하여 중수로계통설계의 열수력 해석코드인 SOPHT를 이용하여 주열수송계통의 과도압력상태를 해석하였다. 카나다 원자력 규제위원회(AECB)의 과압 방지조건인 R-77 요구조건에 적절한 유효트립변수를 결정하기 위한 해석이 수행되었으며, 증기발생기 오염상태와 액체방출밸브 작동여부가 고도압력상태에 미치는 영향을 고찰하여 보수적 조건을 제시하였다. 또한 위와같이 결정된 보수적 조건을 근거로 ASME 코드에 명시된 과압 한계치에 대한 만족여부와 과도압력상태에 따른 주열수송계통의 열수력학적 거동을 고찰하여 보았다. 해석결과, 강제순환상실사고시 주열수송계통은 R-77 요구조건에 적합한 원자로트립변수에 따라 안정화되었으며, 계통의 최대압력은 ASME 코드가 규정한 한계치내에 있음을 알 수 있었다.

• Journal of the Korean Institute of Gas
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• v.13 no.4
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• pp.33-39
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• 2009

This study is intended to experiment performance of pressure relief device and to extend the effective ways to prevent cylinders of NGV from bursting when they are exposed to local fire intensively or when they are overcharged under ambient temperature at fueling stations in summer. In the results of thermal cycling experiments, all products of three companies met the requirements for gas leakage in the qualification criteria between $82^{\circ}C$ and $-40^{\circ}C$. But the o-rings of two companies' specimens among the three companies' specimens got damaged under the accelerated conditions between $135^{\circ}C$ and $-45^{\circ}C$. It took one minute and thirty nine seconds for a glass bulb type of a thermal sensitive type PRD to activate and it took two minutes and thirty one seconds for a fusible plug type of a thermal sensitive type PRD to activate. These results indicated that a glass bulb type of a thermal sensitive type PRD was one minute faster than a fusible plug type of a thermal sensitive type PRD. Under the accelerated condition $135^{\circ}C$, the activation pressure of a pressure sensitive type PRD burst at 32.1 MPa and, under the condition of qualification criteria, it burst from 30.7 MPa to 32.1 MPa.. As a result of the experiment for performance of pressure relief device, in the case of the thermal sensitive type PRD, a glass bulb type is more effective to flame than a fusible plug type. we confirmed that the rupture pressure of a pressure sensitive type PRD could not be affected by temperature and pressure cycling.