Molten salt reactors: A new beginning for an old idea
Molten salt reactors: A new beginning for an old idea
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DOI：
10.1016/j.nucengdes.2009.12.033
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发表时间：
2010-06-01
影响因子：
1.7
通讯作者：
LeBlanc, David
中科院分区：
文献类型：
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作者：
LeBlanc, David
在过去的十年中，熔盐反应堆的兴趣明显复苏，突出表现为它们被列为六种第四代反应堆类型之一。然而，最活跃的发展时期是在20世纪50年代中期和70年代初之间的橡树岭国家实验室（ORNL），任何新的重新审查这一概念必须牢记当时不同的优先事项。高增殖比和短倍增时间是至关重要的，这指导了熔盐增殖反应堆（MSBR）计划的发展。随着熔盐概念的固有优势对全球越来越多的研究人员来说变得显而易见，重要的是不要简单地继续ORNL停止的地方，而是回归基础，以便使用更新的目标和能力提供最佳设计。MSBR设计和本演示的主题是返回ORNL为其MSR计划的大部分提出的操作模式。这是双流体设计，其中将单独的盐用于裂变（233）UF（4）和增殖性ThF（4）。由于所谓的“管道问题”，橡树岭放弃了这条有前途的路线。它将被证明，一个简单而关键的修改核心的几何形状可以解决这个问题，使许多优点的双流体设计。此外，ORNL设计的另一条非常有前途的路线是简化的单流体转换器反应堆，它可以获得比LWR或CANDU更上级的铀利用率，而无需进行简单化学控制之外的任何燃料处理。还将探讨这一非常有吸引力的概念的更新和潜在改进。(C)2010 Elsevier B.V.保留所有权利。
Molten salt reactors have seen a marked resurgence of interest over the past decade, highlighted by their inclusion as one of six Generation IV reactor types. The most active development period however was between the mid 1950s and early 1970s at Oak Ridge National Laboratories (ORNL) and any new re-examination of this concept must bear in mind the far different priorities then in place. High breeding ratios and short doubling times were paramount and this guided the evolution of the Molten Salt Breeder Reactor (MSBR) program. As the inherent advantages of the molten salt concept have become apparent to an increasing number of researchers worldwide it is important to not simply look to continue where ORNL left off but to return to basics in order to offer the best design using updated goals and abilities.A major potential change to the traditional Single Fluid, MSBR design and a subject of this presentation is a return to the mode of operation that ORNL proposed for the majority of its MSR program. That being the Two Fluid design in which separate salts are used for fissile (233)UF(4) and fertile ThF(4). Oak Ridge abandoned this promising route due to what was known as the "plumbing problem". It will be shown that a simple yet crucial modification to core geometry can solve this problem and enable the many advantages of the Two Fluid design. In addition, another very promising route laid out by ORNL was simplified Single Fluid converter reactors that could obtain far superior lifetime uranium utilization than LWR or CANDU without the need for any fuel processing beyond simple chemistry control. Updates and potential improvements to this very attractive concept will also be explored. (C) 2010 Elsevier B.V. All rights reserved.