Analysis of thermal-hydraulic safety features for Ultra-Long Cycle Fast Reactor using MATRA-LMR

Han Seo; Sarah Kang; In Cheol Bang

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Analysis of thermal-hydraulic safety features for Ultra-Long Cycle Fast Reactor using MATRA-LMR

机译：利用MATRA-LMR分析超长循环快堆的热工安全特性

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The following results are obtained. (1) The current design of UCFR-1000 MWe does notrnsatisfy the safety requirements, whereas KALIMER-600 MWe keeps the desirable safety margin. This is the original limitation as a technical barrier developing long cycle reactor.

机译：得到以下结果。（1）当前UCFR-1000 MWe的设计不能满足安全要求，而KALIMER-600 MWe保持了理想的安全裕度。这是开发长循环反应器的技术障碍的最初限制。

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《Transactions of the American nuclear society》 |2012年第11期|p.1399-1402|共4页
作者
Han Seo; Sarah Kang; In Cheol Bang;
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Ulsan National Institute of Science and Technology (UNIST) 100, Banyeon-ri, Eonyang-eup, Ulju-gun, Ulsan Metropolitan City, 689-798, Republic of Korea;

Ulsan National Institute of Science and Technology (UNIST) 100, Banyeon-ri, Eonyang-eup, Ulju-gun, Ulsan Metropolitan City, 689-798, Republic of Korea;

Ulsan National Institute of Science and Technology (UNIST) 100, Banyeon-ri, Eonyang-eup, Ulju-gun, Ulsan Metropolitan City, 689-798, Republic of Korea;

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机译：小型超长周期快堆堆芯的子通道分析
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3. Adoption of nitrogen power conversion system for small scale ultra-long cycle fast reactor eliminating intermediate sodium loop [J] . Bin Seo Seok, Seo Han, Bang In Cheol Annals of nuclear energy . 2016,第JANaPTa2期

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4. Thermal-hydraulics Design and Safety Analysis of Small Modular Lead-Bismuth Cooled Fast Reactors [C] . Liu Dalin, Tan Jiaqi, Liu Xiaojing, International Conference on Power and Energy Systems . 2020

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5. Scaling approach and thermal-hydraulic analysis in the reactor cavity cooling system of a high temperature gas -cooled reactor and thermal-jet mixing in a sodium fast reactor. [D] . Omotowa, Olumuyiwa A. 2014

机译：高温气冷反应堆的反应堆腔冷却系统中的结垢方法和热工水力分析，以及钠快速反应堆中的热喷射混合。
6. Microfluidic reactors for advancing the MS analysis of fast biological responses [O] . Iulia M. Lazar, Jingren Deng, Mark A. Stremler, 2019

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7. MELT-III: a neutronics, thermal-hydraulics computer program for fast reactor safety analysis. Volume I [O] . Waltar, A.E., Partain, W.L., Kolesar, D.C., 1974

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Analysis of thermal-hydraulic safety features for Ultra-Long Cycle Fast Reactor using MATRA-LMR

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