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Due to the advantages of high compactness, good pressure resistance, high heat transfer efficiency and high temperature resistance, printed circuit heat exchanger (PCHE) is a promising heat exchanger in the IV generation nuclear power plant, especially for supercritical carbon dioxide Brayton cycle.
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The ages of members from the fourth (IV) generation (IV-1, IV-2, IV-3, IV-5, IV-6, IV-13, IV-14, IV-15 and IV-16) ranged from 41 to 53 years.
The 15-15Ti(stainlesslesteeleel is one of the best candidates for the nuclear reactor components of IV generation Lead-cooled fast reactor (LFR) and was tested in air and in stagnant liquid lead to simulate its behaviour in operating thermal and mechanical stress conditions and to verify its sensitivity to Liquid Metal Embrittlement (LME).
The MSR (Molten Salt Reactor) is one of the six innovative concepts of nuclear reactors envisaged by the GIF-IV (Generation IV International Forum) initiative for the long term evolution of the nuclear technology, in the direction of a more sustainable, safe, proliferation resistant, and economic power generation.
The data obtained in a study developed by Savenkova et al. [ 45] show that the development of intercurrent diseases and postoperative complications (not specifically palatal necrosis) can be prevented by the parenteral application of cephalosporins of the III and IV generations as well as by oral administration of cefixime and protected aminopenicillins.
It starts with (I) a qualitative interpretation of microsatellite data, followed by (II) a quantitative assessment of allele doses, (III) an assessment of the initial allele configuration of the mapping parents, (IV) the generation of molecular marker linkage maps, and (V) the final characterisation of the parental haplotypes, including homozygous loci.
(iv) The generation of the M-TR motif in P. cornutus provides evidence for the origin of mtTRs by PMM mechanisms.
The development of the Generation IV (Gen-IV) nuclear reactors has presented social, technical, and economical challenges to nuclear engineering design and research.
It then identifies five relevant methodological issues for a more detailed discussion: (i) the selection of participants; (ii) the means to visualise long-term futures; (iii) the visualisation of desired futures; (iv) the generation of multiple future visions; (v) the combination of multiple participatory techniques.
Within the framework of the generation IV Sodium Fast Reactors, the safety in case of severe accidents is assessed.
The gas-cooled fast reactor (GFR) is one of the six reactor concepts selected in the frame of the Generation IV initiative.
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