• 제목/요약/키워드: Safety system setpoint

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OPΔT 및 OTΔT트립설정치의 생산방법 (OPΔT and OTΔT Trip Setpoint Generation Methodology)

  • Ki In Han
    • Nuclear Engineering and Technology
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    • 제16권2호
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    • pp.106-115
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    • 1984
  • 원자로 안전한계 설정의 근본목적은 핵연료 및 원자료 계통의 건전성을 보장할 수 있도록 원자로 운전조건을 제한하자는 데 있다. 원자로 보호계통은 원자로 운전변수들이 트립설정치에 도달하게 되면 원자로를 긴급정지시켜 운전조건이 안전한계를 초과하지 못하도록 한다. 따라서 이들 트립설정치의 생산을 위해서는 계산과 측정오차를 충분히 고려해 주어야 한다. 본 기술보고서에서는 웨스팅하우스 원자로 보호계통 트립설정치의 생산에 따른 기본원리와 노심 안전한계의 개발방법 및 트립설정치의 생산절차를 검토하였다. 웨스팅하우스 보호계통 트립설정치의 생산원리는 노심의 안전한계를 계산하고 측정 및 계산에 따른 불확실성을 충분히 고려하여 보수적인 트립설정치를 생산함으로써 핵연료의 용융과 DNB가 발생하지 않도록 하자는 데 있다.

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A study on the uncertainty of setpoint for reactor trip system of NPPs considering rectangular distributions

  • Youngho Jin;Jae-Yong Lee;Oon-Pyo Zhu
    • Nuclear Engineering and Technology
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    • 제56권5호
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    • pp.1845-1853
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    • 2024
  • The setpoint of the reactor trip system shall be set to consider the measurement uncertainty of the instrument channel and provide a reasonable and sufficient margin between the analytical limit and the trip setpoint. A comparative analysis was conducted to find out an appropriate uncertainty combination method through an example problem. The four methods were evaluated; 1) ISA-67.04.01 method, 2) the GUM95 method, 3) the modified GUM method developed by Fotowicz, and 4) the modified IEC61888 method proposed by authors for the pressure instrument channel presented in ISA-RP67.04.02 example. The appropriateness of each method was validated by comparing it with the result of Monte Carlo simulation. As a result of the evaluation, all methods are appropriate when all measurement uncertainty elements are normally distributed as expected. But ISA-67.04 method and GUM95 method overestimated the channel uncertainty if there is a dominant input element with rectangular distribution among the uncertainty input elements. Modified GUM95 methods developed by Fotowicz and modified IEC61888 method by authors are able to produce almost the same level of channel uncertainty as the Monte Carlo method, even when there is a dominant rectangular distribution among the uncertainty components, without computer-assisted simulations.

원전 제어봉제어계통 순시변동을 방지하기위한 지상-지연회로 설정치 최적화 연구 (A Research on Optimization of Lead-lag Controller Setpoint for Rod control system to prevent fluctuation for NPP)

  • 윤덕주;이재용;김인환;김주성
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2007년도 춘계학술대회A
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    • pp.1149-1154
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    • 2007
  • Fluctuation of control rod was experienced when plant was operating in normal operation mode in WH type NPPs. In order to cope with increased control rod fluctuation, the lead-lag controller setpoint for rod control system was optimized and resulted in increasing the margin of operation and minimizing unnecessary control rod movement. By optimization of the time constant, the margin of operation was increased by $1.5^{\circ}F$ and the control rod movement was not occurred due to mitigation of temperature fluctuation in loop. According to the mitigation of time constant, the margin of operation was increased but safety margin can be affected badly, so that the influences to FSAR design reference was evaluated. As the result of this evaluation, it satisfied the design reference of the existing safety analysis and was applied to NPP after obtaining the approval.

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선량환산인자를 이용한 기체유출물 RMS 경보설정 개선방안 (Alarm Setpoint Determination Method of Gaseous Effluent Radiation Monitoring Systems Using Dose Factors Based on ICRP-60 Recommendations)

  • 박규준;김희근;하각현;엄희문
    • 한국방사성폐기물학회:학술대회논문집
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    • 한국방사성폐기물학회 2003년도 가을 학술논문집
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    • pp.491-496
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    • 2003
  • ICRP-60의 방사선방호 신개념이 국내 법령에 도입됨에 따라 원전 방사성유출물 관리의 변경이 불가피한 실정이다. 방사성유출물 관리의 중요한 요소 중의 하나가 원전 방사선감시계통(Radiation Monitoring System)의 적절한 운용이다. RMS는 원자력법에 명시되어 있는 일반인의 선량한도와 배출관리기준을 만족하도록 운용되어야 한다. 방사성유출물을 제한하는 기준에 따른 RMS 경보설정치의 비교ㆍ분석을 통해 국내 원전에 적용 가능한 최적의 개선방안을 제시할 수 있다. 본 논문에선 선량한도 기준 중 가능한 모든 피폭경로를 고려하여 예상선량률을 계산한 선행 RMS 경보설정 개선방안과의 비교를 위해 주요 피폭경로만 고려하는 선량환산인자에 의한 예상선량률 계산과 RMS 경보설정 개선방안을 조사하였다.

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Development of Advanced Annunciator System for Nuclear Power Plants

  • Hong, Jin-Hyuk;Park, Seong-Soo;Chang, Soon-Heung
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1995년도 추계학술발표회논문집(1)
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    • pp.185-190
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    • 1995
  • Conventional alarm system has many difficulties in the operator's identifying the plant status during special situations such as design basis accidents. To solve the shortcomings, an on-line alarm annunciator system, called dynamic alarm console (DAC), was developed. In the DAC, a signal is generated as alarm by the use of an adaptive setpoint check strategy based on operating mode, and time delay technique is used not to generate nuisance alarms. After alarm generation, if activated alarm is a level precursor alarm or a consequencial alarm, it would be suppressed, and the residual alarms go through dynamic prioritization which provide the alarms with pertinent priorities to the current operating mode. Dynamic prioritization is achieved by going through the system- and mode-oriented prioritization. The DAC has the alarm hierarchical structure based on the physical and functional importance of alarms. Therefore the operator can perceive alarm impacts on the safety or performance of the plant with the alarm propagation from equipment level to plant functional level. In order to provide the operator with the most possible cause of the event and quick cognition of the plant status even without recognizing the individual alarms, reactor trip status tree (RTST) was developed. The DAC and the RTST have been simulated with on-line data obtained from the full-scope simulator for several abnormal cases. The results indicated that the system can provide the operator with useful and compact information fur the earlier termination and mitigation of an abnormal state.

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Modification of Reference Temperature Program in Reactor Regulating System

  • Yu, Sung-Sik;Lee, Byung-Jin;Kim, Se-Chang;Cheong, Jong-Sik;Kim, Ji-In;Doo, Jin-Yong
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1998년도 춘계학술발표회논문집(1)
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    • pp.404-410
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    • 1998
  • In Yonggwang nuclear units 3 and 4 currently under commercial operation, the cold leg temperature was very close to the technical specification limit of 298$^{\circ}C$ during initial startup testing, which was caused by the higher-than-expected reactor coolant system flow. Accordingly, the reference temperature (Tref) program needed to be revised to allow more flexibility for plant operations. In this study, the method of a specific test performed at Yonggwang nuclear unit 4 to revise the Tref program was described and the test results were discussed. In addition, the modified Tref program was evaluated on its potential impacts on system performance and safety. The methods of changing the Tref program and the associated pressurizer level setpoint program were also explained. Finally, for Ulchin nuclear unit 3 and 4 currently under initial startup testing, the effects of reactor coolant system flow rate on the coolant temperature were evaluated from the thermal hydraulic standpoint and an optimum Tref program was recommended.

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FLB Event Analysis with regard to the Fuel Failure

  • Baek, Seung-Su;Lee, Byung-Il;Lee, Gyu-Cheon;Kim, Hee-Cheol;Lee, Sang-Keun
    • 한국원자력학회:학술대회논문집
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    • 한국원자력학회 1996년도 춘계학술발표회논문집(2)
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    • pp.622-627
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    • 1996
  • Detailed analysis of Feedwater Line Break (FLB) event for the fuel failure point of view are lack because the event was characterized as the increase in reactor coolant system (RCS) pressure. Up to now, the potential of the rapid system heatup case has been emphasized and comprehensively studied. The cooldown effects of FLB event is considered to be bounded by the Steam Line Break (SLB) event since the cooldown effect of SLB event is larger than that of the FLB event. This analysis provides a new possible path which can cause the fuel failure. The new path means that the fuel failure can occur under the heatup scenario because the Pressurizer Safety Valves (PSVs) open before the reactor trips. The 1000 MWe typical C-E plant FLB event assuming Loss of Offsite Power (LOOP) at the turbine trip has been analyzed as an example and the results show less than 1% of the fuel failure. The result is well within the acceptance criteria. In addition to that, a study was accomplished to prevent the fuel failure for the heatup scenario case as an example. It is found that giving the proper pressure gap between High Pressurizer Pressure Trip (HPPT) analysis setpoint and the minimum PSV opening pressure could prevent the fuel failure.

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Feasibility study of the beating cancellation during the satellite vibration test

  • Bettacchioli, Alain
    • Advances in aircraft and spacecraft science
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    • 제5권2호
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    • pp.225-237
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    • 2018
  • The difficulties of satellite vibration testing are due to the commonly expressed qualification requirements being incompatible with the limited performance of the entire controlled system (satellite + interface + shaker + controller). Two features cause the problem: firstly, the main satellite modes (i.e., the first structural mode and the high and low tank modes) are very weakly damped; secondly, the controller is just too basic to achieve the expected performance in such cases. The combination of these two issues results in oscillations around the notching levels and high amplitude beating immediately after the mode. The beating overshoots are a major risk source because they can result in the test being aborted if the qualification upper limit is exceeded. Although the abort is, in itself, a safety measure protecting the tested satellite, it increases the risk of structural fatigue, firstly because the abort threshold has been already reached, and secondly, because the test must restart at the same close-resonance frequency and remain there until the qualification level is reached and the sweep frequency can continue. The beat minimum relates only to small successive frequency ranges in which the qualification level is not reached. Although they are less problematic because they do not cause an inadvertent test shutdown, such situations inevitably result in waiver requests from the client. A controlled-system analysis indicates an operating principle that cannot provide sufficient stability: the drive calculation (which controls the process) simply multiplies the frequency reference (usually called cola) and a function of the following setpoint, the ratio between the amplitude already reached and the previous setpoint, and the compression factor. This function value changes at each cola interval, but it never takes into account the sensor signal phase. Because of these limitations, we firstly examined whether it was possible to empirically determine, using a series of tests with a very simple dummy, a controller setting process that significantly improves the results. As the attempt failed, we have performed simulations seeking an optimum adjustment by finding the Least Mean Square of the difference between the reference and response signal. The simulations showed a significant improvement during the notch beat and a small reduction in the beat amplitude. However, the small improvement in this process was not useful because it highlighted the need to change the reference at each cola interval, sometimes with instructions almost twice the qualification level. Another uncertainty regarding the consequences of such an approach involves the impact of differences between the estimated model (used in the simulation) and the actual system. As limitations in the current controller were identified in different approaches, we considered the feasibility of a new controller that takes into account an estimated single-input multi-output (SIMO) model. Its parameters were estimated from a very low-level throughput. Against this backdrop, we analyzed the feasibility of an LQG control in cancelling beating, and this article highlights the relevance of such an approach.