Water temperature records from corals near the nuclear power plant in southern Taiwan

2001 ◽  
Vol 44 (4) ◽  
pp. 356-362 ◽  
Author(s):  
Chen-Tung Chen ◽  
Chung-Ho Wang ◽  
Ker-Yea Soong ◽  
Bing-Jye Wang
2020 ◽  
Vol 329 ◽  
pp. 03049
Author(s):  
Aleksey Babushkin ◽  
Sergey Skubienko ◽  
Ludmila Kinash

In this study, the influence of the cooling water temperature on the thermal efficiency of a conceptual pressurized-water reactor nuclear- power plant is studied. The change in the cooling water temperature can be experienced due to the seasonal changes in climatic conditions at plant site. The article presents the results of technical and economic parameters study of nuclear power unit’s operation under increased vacuum value. Investigated seasonal variations of cooling water temperature, cooling water temperature influence on the vacuum temperature in the turbine condenser, and changing the basic technical and economic performance of nuclear power station. The mathematical model of calculation the nuclear power plant operation for a 1000 MW power unit was developed.


Author(s):  
Ching-Hui Wu ◽  
Tsu-Jen Lin ◽  
Tsu-Mu Kao

On March 18, 2001, a PWR nuclear power plant located in the Southern Taiwan occurred a Station BlackOut (SBO) event. Monsoon seawater mist caused the instability of offsite power grids. High salt-contained mist caused offsite power supply to the nuclear power plant very unstable, and forced the plant to be shutdown. Around 24 hours later, when both units in the plant were shutdown, several inadequate high cycles of bus transfer between 345 kV and 161 kV startup transformers degraded the emergency 4.16 kV switchgears. Then, in the Train-A switchgear room of Unit 1 occurred a fire explosion, when the degraded switchgear was hot shorted at the in-coming 345 kV breaker. Inadequate configuration arrangement of the offsite power supply to the emergency 4.16 kV switchgears led to loss of offsite power (LOOP) events to both units in the plant. Both emergency diesel generators (EDG) of Unit 1 could not be in service in time, but those of Unit 2 were running well. The SBO event of Unit 1 lasted for about two hours till the fifth EDG (DG-5) was lined-up to the Train-B switchgear. This study investigated the scenario of the SBO event and evaluated a risk profile for the SBO period. Guidelines in the SBO event, suggested by probabilistic risk assessment (PRA) procedures were also reviewed. Many related topics such as the re-configuration of offsite power supply, the addition of isolation breakers of the emergency 4.16 kV switchgears, the betterment of DG-5 lineup design, and enhancement of the reliability of offsite power supply to the PWR plant, etc., will be in further studies.


Author(s):  
Yng-Ruey Yuann ◽  
Yen-Shu Chen ◽  
Ansheng Lin

The Chinshan Nuclear Power Plant owned and operated by the Taiwan Power Company is a twin-unit BWR-4 plant. Unit 1 and unit 2 began their commercial operation in 1978 and 1979, respectively. Since commercial operation, all the fuels discharged from reactor core at each cycle are stored in the spent fuel pool (SFP). An engineering analysis is performed to predict the SFP water temperature and pool water level during a postulated loss of forced cooling accident. A full-core discharged loading is considered, and the fuel assemblies are moved to the SFP just after 7 days of cooling. The pool temperature and level are calculated using lumped energy and mass balances. Calculation results show that the water temperature reaches the saturation temperature at 9.4 hours after the onset of the accident, and the pool level drops to the top of the active fuels at 76.8 hours. After the pool level drops to the top of the active fuels, the cladding temperature increases dramatically because the convective heat transfer of steam is much weaker than that of liquid water. The peak cladding temperature after fuel uncovery is calculated by detailed CFD simulations, and the results show that the peak cladding temperature reaches 600°C in 3 hours and 1200°C in 9.5 hours after the fuels are uncovered. Additionally, the check-board arrangement for fuels is also investigated. Through enhanced the radiation heat transfer, the check-board fuel arrangement can have slower heating rate for the fuels. For the Chinshan SFP, extra 2.5 hours can be gained by employing such an arrangement for necessary actions.


1981 ◽  
Vol 38 (4) ◽  
pp. 441-448 ◽  
Author(s):  
Marlene S. Evans

Zooplankton distributions in the 1-m stratum differed between ambient waters and the thermal plume of the Donald C. Cook Nuclear Power Plant. Zooplankton were most abundant in the warmest waters of the plume with the region of high densities extending over an approximate area of 0.2 to 0.3 km2. Water temperature was not a reliable indicator of alterations in zooplankton populations. Alterations were primarily due to upward vertical displacement of deep-living zooplankton. Large horizontal variability in zooplankton densities and use of conventional sampling procedures (vertically hauled nets, widely spaced stations) prevent traditionally designed monitoring programs from detecting such alterations. Zooplankton may experience indirect mortality losses in the plume if transfer of deep-living zooplankton to the surface layers makes them more visible to visual-feeding fish predators, and turbulences in the plume reduce zooplankters' ability to detect and avoid such predators.Key words: zooplankton, thermal plume, planktivorous fish, predation


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