WH1000형 원전의 보조급수계통 유효성 연구
- Author(s)
- 이경우
- Issued Date
- 2017
- Abstract
- Nuclear power plant is a facility which produces electricity by heat from reactor, steam generator and turbine. The steam generator uses a high-pressure water system to produce steam from the reactor coolant system to operate the turbines, and forms the boundary between the reactor coolant system and the secondary system.
The high temperature of the high pressure reactor flows into the lower head of the steam generator and flows through the inside of U-tube, heating the water on the outside of the secondary water.
The auxiliary feedwater system removes heat from the reactor core by supplying feedwater to prevent core damage when feedwater system is inoperable. For this reason, the auxiliary feedwater system contributes to the safety of the reactor and ESF (Engineered Safety Facility). The function of the auxiliary feedwater system is as follows.
First, supplying feedwater to steam generator during abnormal accident
Second, supplying feedwater during the feedwater system inoperable due to the loss of offsite power.
Third, supplying feedwater during the maintaining hot stand-by condition.
Fourth, supplying feedwater to steam generator in a condition required hot shutdown condition.
Compared to the OPR1000 type plants, the WH1000 type plants have relatively small steam generators volume and tube number. Therefore, the falling rate of Tavg in the WH1000 type plants are faster and the fluctuation of steam generator level is variable. This means that the steam generation of the WH1000 type plants relatively reach to full range level faster than the OPR1000 type plants.
When it happens to the auxiliary feedwater activation signal, the auxiliary feedwater flow control valves are fully opened and the rate of flow is maximum. Steam generator level can be maintained from 7 to 50 % by operator`s controlling.
However, the steam flow rate of the steam generator by level of steam generator in the OPR1000 type can be maintained automatically to 50% level without the intervention of operator. Overall, whether the steam generator level is full or not is dependent on operator`s level control capability
The negative effects of the steam generator full level are as follows.
First, if water flows into a steam pipe, vapor condenses and the water hammer phenomenon can be triggered. This causes damage to piping hangers, supports structures, valves, and operators, and loses the integrity of the steam pipe.
Second, when significant amount of water is poured into the steam pipe, the design criteria for the spring support structure of steam pipe is exceeded stress limitation by the extra loads. it causes severe deformation of steam pipe.
Third, valves are likely to be opened and not to reopened in a steam generator full level condition because they are not designed to fit into this environment.
Fourth, if the water flows into the turbine driven auxiliary feedwater pump through the steam pipe the turbine of auxiliary feedwater pump may not be seriously damaged, causing the pressure boundary to be compromised.
Fifth, the acceleration of a liquid that is deposited inside a pipe can cause breakage of piping or equipment.
This study is to verify the problems of the WH1000 type`s facility and improvement plan about Tavg falling, plan of prevention of steam generator full level based on tests and analysis by simulator`s test.
- Alternative Title
- A study on the effectiveness of Auxiliary feedwater system in WH1000 type NPP
- Alternative Author(s)
- Lee, Kyoung Woo
- Department
- 일반대학원 원자력공학과
- Advisor
- 이경진
- Awarded Date
- 2018-02
- Table Of Contents
- ABSTRACT ⅵ
제 1 장 서 론 1
제 2 장 WH1000형 및 OPR1000형 원전의 증기발생기 비교 3
제 1 절 WH1000형 원전 증기발생기 3
1. 일반사항 3
2. 설계사양 4
3. 증기발생기 수위제어 4
제 2 절 OPR1000형 원전 증기발생기 11
1. 일반사항 11
2. 설계사양 13
3. 증기발생기 수위제어 13
제 3 장 WH1000형 및 OPR1000형 원전의 보조급수계통 비교 18
제 1 절 WH1000형 원전 보조급수계통 18
1. 보조급수펌프 사양 18
2. 계통운전 18
제 2 절 OPR1000형 원전 보조급수계통 20
1. 보조급수펌프 사양 20
2. 계통운전 20
제 4 장 증기발생기 고수위 발생시 발전소 영향검토 23
제 1 절 증기발생기 고수위의 정의와 조치절차 23
제 2 절 증기발생기 과충수의 부정적인 영향 24
1. 응축에 의한 수격현상 24
2. 과도한 중력하중 24
3. 밸브의 개방 고착 24
4. 터빈구동 보조급수펌프 터빈고장 25
5. 축척된 물의 가속 25
제 5 장 WH1000형과 OPR1000형 원전 비교분석 26
제 1 절 증기발생기 차이점 분석 26
제 2 절 보조급수계통 차이점 분석 27
1. 보조급수펌프 27
2. 보조급수제어 27
3. 보조급수 동작신호 28
제 6 장 WH1000형 원전의 보조급수계통 유효성 연구 29
제 1 절 연구 목표 29
제 2 절 연구 방법 29
1. 절차서 검증 29
2. 중점 관찰사항 30
제 3 절 연구 결과 31
1. 원자로냉각재펌프(RCP) 정지 후 원자로냉각재 온도(Tavg) 변화 31
2. 모든 교류전원 상실시 SG 수위 변화 32
3. 증기발생기 관파열시 SG 수위 변화 34
제 4 절 개선방법 36
1. RCP 한 대 정지시 Tavg 감소에 대한 개선방법 36
2. 증기발생기 만수위 대처방안 36
제 7 장 결론 38
참고문헌 39
- Degree
- Master
- Publisher
- 조선대학교 대학원
- Citation
- 이경우. (2017). WH1000형 원전의 보조급수계통 유효성 연구.
- Type
- Dissertation
- URI
- https://oak.chosun.ac.kr/handle/2020.oak/13408
http://chosun.dcollection.net/common/orgView/200000266539
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