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1)  supercritical reactor
超临界堆
2)  Supercritical water reactor
超临界水堆
1.
This paper introduces the software extension in the reactor core analysis code PARCS and thermodynamics code RELAP5 to accommodate the special water thermal physical properties and separated moderator channel design in supercritical water reactor(SCWR).
针对超临界水堆特殊的水物性参数和独立的慢化剂通道设计,对堆芯计算程序PARCS和热工水力程序RELAP5进行了适应性改造。
2.
Research activities of supercritical water reactor(SCWR) have been carried out worldwide,aiming at cost reduction by system simplification and higher thermal efficiency.
由于超临界水堆(SCWR)在系统简化、降低成本和提高热效率上的优势,SCWR的研究在全球范围内得到广泛关注。
3)  supercritical water cooled reactor
超临界水堆
1.
Feasibility of the steel was analysed for in-core component and fuel cladding application in supercritical water cooled reactor.
分析了9Cr3W钢用作超临界水堆堆芯内部件及包壳材料的可行性,其高温力学性能远优于Zr合金包壳材料;拉伸性能与T91钢相当,且韧脆转变温度低于T91钢,冲击吸收功上限高于T91钢,具有优良的冲击韧性;9Cr3W钢的高温瞬时强度低于奥氏体316不锈钢,成为制约其用于超临界水堆堆芯内部件及包壳的因素之一。
2.
Recently,a new supercritical water cooled reactor(SCWR) conceptual design was proposed on the basis of a mixed spectrum core concept consisting of a thermal zone and a fast zone.
针对一种新型的超临界水堆设计方案——混合能谱超临界水堆(SCWR-M)进行分析。
3.
As the only water cooled reactor among the six generation-Ⅳ reactor,supercritical water cooled reactor(SCWR) has its special characteristics,and takes up attentions extensively.
超临界水堆作为6种第4代未来堆型中唯一的水冷堆,具有一些独特的特点,受到了广泛重视。
4)  SCWR
超临界水冷堆
1.
Steady-State Thermal-Hydraulic Analysis of SCWR Assembly;
超临界水冷堆堆芯子通道稳态热工分析
2.
Investigations on the thermal-hydraulic behavior in the SCWR fuel assembly have obtained a significant attention in the international SCWR community.
目前国际上对超临界水冷堆进行了大量的研究,但对其堆芯内超临界流体流动传热的认识还十分欠缺。
5)  supercritical-water-cooled reactor(SCWR)
超临界水堆(SCWR)
6)  super-critical reactor
超临界反应堆
补充资料:超临界反应堆
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CAS号:

性质:选择反应堆的尺寸、形状和慢化剂、反射层材料。使由裂变产生的平均中子数与被燃料、减速剂等吸收及泄漏的中子总数的平均值的比大于1,即反应堆的有效增殖系数大于1。这样的反应堆叫超临界反应堆。它的裂变链是发散的,反应堆内的中子数随时间一直增加,相应地链式裂变反应率增高。

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