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Transient Analysis Of Sulfur-iodine Cycle Experiments And Very High Temperature Reactor Simulations Using Melcor-h2

机译:使用Melcor-h2进行硫碘循环实验的瞬态分析和超高温反应器模拟

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MELCOR is a thermal-hydraulic code used by the United States and the international nuclear community for the modeling of both light water and gas-cooled reactors. MELCOR was extended in order to model nuclear reactors that are coupled to the sulfur-iodine (SI) cycle for cogeneration of hydrogen. This version of the code is known as MELCOR-H2, and it includes modular secondary system components (e.g., turbines, compressors, heat exchangers, and generators), a point-kinetics model, and a graphical user interface. MELCOR-H2 allows for the fully coupled, transient analysis and design of the nuclear thermochemical SI cycle for the purpose of maximizing the production of hydrogen and electricity. Recent work has demonstrated that the hydrogen generation rate calculated by MELCOR-H2 for the SI cycle was within the expected theoretical yield.rnIn order to benchmark MELCOR-H2, we simulated a set of sulfuric acid decomposition experiments that were conducted at Sandia National Laboratories during 2006. We also used MELCOR-H2 to simulate a 2004 Japan Atomic Energy Research Institute SI experiment.rnThe simulations compared favorably with both experiments; most measured and calculated outputs were within 10%. The simulations adequately calculated O_2, SO_2, and H_2 production rate, acid conversion efficiency, the relationship between solution mole percent and conversion efficiency, and the relationship between molar flow rate and efficiency.rnWe also simulated a 6-stage turbine and a 20-stage compressor. Our results were mostly within 1 or 2% of the literature. Then, we simulated a pebble bed very high temperature reactor (VHTR) and compared key MELCOR-H2 results with the literature. The comparison showed that the results were typically within 1 or 2%. Finally, we compared the MELCOR-H2 point-kinetics model with the exact Inhour reactivity solution for various cases, including a 1.0 $ step reactivity insertion. We were able to employ a large time step while successfully matching the theoretical power level. These comparisons demonstrate MELCOR-H2's unique ability to simulate fully coupled VHTRs for the production of hydrogen.
机译:MELCOR是美国和国际核能界用于对轻水反应堆和气冷堆进行建模的热工液压规范。扩展了MELCOR,以建模与硫-碘(SI)循环耦合以共同产生氢的核反应堆。该版本的代码称为MELCOR-H2,它包含模块化的辅助系统组件(例如,涡轮机,压缩机,热交换器和发电机),点动力学模型和图形用户界面。 MELCOR-H2可以对核热化学SI循环进行完全耦合的瞬态分析和设计,以最大程度地产生氢气和电能。最近的工作表明,MELCOR-H2计算出的SI循环制氢速率在预期的理论收率范围内。为了确定MELCOR-H2的基准,我们模拟了一组在桑迪亚国家实验室进行的硫酸分解实验。 2006年。我们还使用MELCOR-H2进行了2004年日本原子能研究所SI实验的仿真。大部分测量和计算的输出都在10%以内。通过模拟可以充分计算出O_2,SO_2和H_2的产生速率,酸转化效率,溶液摩尔百分率与转化效率之间的关系以及摩尔流量与效率之间的关系。rn我们还模拟了6级涡轮和20级涡轮压缩机。我们的结果大多在文献的1%或2%之内。然后,我们模拟了卵石床超高温反应器(VHTR),并将关键的MELCOR-H2结果与文献进行了比较。比较表明,结果通常在1%或2%之内。最后,我们将MELCOR-H2点动力学模型与确切的Inhour反应性解决方案进行了比较,适用于各种情况,包括1.0阶跃反应性插入。在成功匹配理论功率水平的同时,我们能够采用较大的时间步长。这些比较证明了MELCOR-H2独特的能力,可以模拟完全耦合的VHTR以生产氢气。

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