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Revisiting Stainless Steel as PWR Fuel Rod Cladding after Fukushima Daiichi Accident
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作者 alfredo abe Claudia Giovedi +1 位作者 Daniel de Souza Gomes Antonio Teixeira e Silva 《Journal of Energy and Power Engineering》 2014年第6期973-980,共8页
In the past, stainless steel was utilized as cladding in many PWRs (pressurized water reactors), and its performance under irradiation was excellent. However, stainless steel was replaced by zirconium-based alloy as... In the past, stainless steel was utilized as cladding in many PWRs (pressurized water reactors), and its performance under irradiation was excellent. However, stainless steel was replaced by zirconium-based alloy as cladding material mainly due to its lower neutron absorption cross section. Now, stainless steel cladding appears as a possible solution for safety problems related to hydrogen production and explosion as occurred in Fukushima Daiichi accident. The aim of this paper is to discuss the steady-state irradiation performance using stainless steel as cladding. The results show that stainless steel rods display higher fuel temperatures and wider pellet-cladding gaps than Zircaloy rods and no gap closure. The thermal performance of the two rods is very similar and the neutron absorption penalty due to stainless steel use could be compensating by combining small increase in U-235 enrichment and pitch size changes. 展开更多
关键词 Austenitic stainless steel cladding Zircaloy cladding PWR fuel rod steady-state fuel performance codes.
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