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Detailed analyses have shown that allowable limits to the maximum fuel rod power and maximum cladding temperature can be determined to assure the fuel integrities.
It is found that for a single central absorber rod of radius 9 cm, the maximum fuel rod radius is 6 mm for hafnium and 6.2 mm for B4C.
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The results show that in the most conservative conditions, the maximum temperature of the fuel rod and MDNBR were 2167.4 °C and 1.08, respectively.
The safety analysis is carried out and the results are checked against the acceptance criteria which are the possibility of using water inventory in the emergency core cooling system (ECCS) accumulators and the KWU tanks for core cooling and the available time to operators before the maximum design limit of fuel rod cladding damage is reached.
Considering the uncertainties of assembly inlet flow rate, inlet coolant temperature and system pressure, the 95% probability values (with 95% confidence) of fuel rod maximum and MDNBR calculated using response surface methodology were 2144.0 °C and 1.6, while they were 2137 °C and 1.74 calculated by Wilks' approach.
The paper shows the elaborated hot channel calculation methodology by analyzing an ATWS event of a Russian designed pressurized water reactor (VVER-440) and the results of conservative vs. uncertainty analysis are compared with regard to the number of failed fuel rods, the maximum clad surface temperature and the maximum fuel temperature.
TRANSURANUS yielded the maximum rod discharge burnups of the several design combinations, under the condition that specific thermal-mechanical fuel rod constraints were not violated.
A typical fuel rod assembly has roughly 380 pounds of uranium.
In Tamworth, Staffordshire, over the weekend a uranium fuel rod was found in a scrapyard.
Finally the improved fuel rod design is proposed.
The code is modified by adding fuel rod behavior models.
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