首页> 外文会议>International Nuclear Fuel Cycle Conference >STUDY ON EUTECTIC MELTING BEHAVIOR OF CONTROL ROD MATERIALS IN CORE DISRUPTIVE ACCIDENTS OF SODIUM-COOLED FAST REACTOR: (2) EFFECT OF B4C ADDITION ON THERMOPHYSICAL PROPERTIES OF AUSTENITIC STAINLESS STEEL IN A SOLID STATE
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STUDY ON EUTECTIC MELTING BEHAVIOR OF CONTROL ROD MATERIALS IN CORE DISRUPTIVE ACCIDENTS OF SODIUM-COOLED FAST REACTOR: (2) EFFECT OF B4C ADDITION ON THERMOPHYSICAL PROPERTIES OF AUSTENITIC STAINLESS STEEL IN A SOLID STATE

机译:钠冷却快速反应器核心破坏性事故中对照杆材料的共晶熔化行为的研究:(2)B4C加入固态奥氏体不锈钢热物理性能的影响

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In a core disruptive accident scenario, the boroncarbide (B_4C) of control-rod material is expected to reactwith stainless steel (SS) of the structural material. Theproduced eutectic material of stainless steel containingboron carbide (SS-B_4C) is assumed to relocate widely inthe core. To add a function to explain this liquefactionand relocation behavior to core disruptive accidentanalysis codes, a database of SS-B_4C thermophysicalproperties must be maintained. In this work, the densityand specific heat of austenite stainless steel (316L SS)containing 7mass%B_4C in the solid state are obtained andcompared with that of 316L SS containing 5mass% B_4Cand the value of 316L SS in the literature. It is found thatas the B_4C concentration in the austenitic stainless steelincreases, the density decreases while the specific heatincreases. By adding 7mass%-B_4C to 316L SS, the densitydecreases 7% at 293K. On the other hand, specific heatincreases 21% at 293K.
机译:在核心破坏性事故情景中,硼预计控制杆材料的硬质合金(B_4C)会发生反应采用不锈钢(SS)的结构材料。这生产含有不锈钢的共晶材料碳化硼(SS-B_4C)被假设覆盖广泛核心。添加功能以解释这种液化和核心破坏性事故的搬迁行为分析代码,SS-B_4C热物理数据库必须维护属性。在这项工作中,密度奥氏体不锈钢的比例(316L SS)获得固态的7mas%B_4c与含有5mass%B_4C的316L SS相比和文献中的316L SS的值。它被发现作为奥氏体不锈钢中的B_4C浓度增加,密度在比热量的同时降低增加。通过将7mass%-b_4c添加到316l ss,密度293K下降7%。另一方面,具体的热量293k增加了21%。

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