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The stewards penalised the world championship leader for not having enough fuel in his car for a fuel sample to be taken.
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This research extends the MIP Monitor by characterizing a used fuel sample after initial dissolution according to the type of reactor of origin (pressurized or boiling water reactor; PWR and BWR, respectively), initial enrichment, burn up, and cooling time.
This study evaluates the efficacy of pattern modulation GC×GC by analyzing a standard mixture of 43 oxygenated organic compounds and an E85 fuel sample.
A drop of fuel sample, 10 μL, is introduced by a digital pipette (use of a disposable cheap plastic pipette is possible in field measurement conditions) over the centre of the roughened glass disk.
Characteristics and distillation temperatures of the DLF are close to those values of a typical diesel fuel sample.
Although the results followed the trends of past benchmarked codes for a UO2 PWR fuel sample from the Takahama-3 reactor, there were obvious deficiencies in the final result, likely in the nuclear data library that was used.
Direct measurement of fuel properties of biodiesel is quite complex with high cost, error in reproducibility and requiring a considerable amount of fuel sample (Tong et al.2011).2011
A focused beam from a tungsten/halogen lamp was used to ignite the center of the fuel sample while an external air flow was varied from 0 to 10 cm/s.
The results presented here were obtained with a simplified simulated nuclear spent fuel sample composed of non-radioactive isotopes of Europium and Uranium, in proportion usually found for uranium oxide nuclear spent fuel.
Fission gas release is monitored online during the experiment and volatile fission products are collected on condensation plates made of stainless steel positioned above the fuel sample on a "cold finger", which is water-cooled to approximately 100 °C.
To design the measurement station, we used a well-characterized UOX spent fuel sample of 40 cm with ∼70 MWd/kg and more than 10 years cooling time as neutron and gamma-ray sources and modeled the fast neutron efficiency of the detectors with MCNP6.1.1 in test conditions and in realistic configurations encountered in the hot-cell.
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