西安脉冲反应器稳态和瞬态模拟的 MC/子通道耦合

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
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引用次数: 0

摘要

将蒙特卡罗(MC)代码 RMC 和子通道代码 CTF 结合起来,用于西安脉冲反应堆(XAPR)的脉冲和耗尽模拟。开发了一个 python 脚本来处理通过文件进行的数据交换。利用脉冲态核心模拟了 3.45 美元脉冲和 2 美元脉冲。作为验证,将脉冲峰值功率和半最大全宽(FWHM)结果与实验结果进行了比较,结果一致。此外,还获得了详细的三维功率和温度分布。结果表明,堆芯功率峰值靠近引入反应性的脉冲棒。由于自屏蔽效应,每根棒的径向功率峰值都位于边界处。棒的温度分布与功率的变化趋势相同,在约 0.12 秒的脉冲时间内冷却剂温度没有变化,这表明在如此短的时间内热传导的作用可以忽略不计。对于稳态堆芯,对 120 个有效全功率日(EFPD)的第一个燃料循环寿命进行了耗竭模拟。通过计算 0 EFPD 时的温度分布和调节杆的差值进行了验证,两者均与实验结果吻合。结果显示,功率分布随着时间的推移几乎没有变化,只是略微平缓一些,这表明材料并没有严重损耗。堆芯的温度分布与功率分布基本一致,只是每根棒的径向温度峰值都在中心,因为热量在稳定状态下是向外传导的。利用 CTF 可以获得详细的冷却剂温度分布。装配边界和中央水室附近的温度明显低于其他部分,这在并行多通道模型中没有显示出来。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
MC/sub-channel coupling for steady state and transient simulation of Xi’an Pulsed Reactor

The Monte Carlo (MC) code RMC and sub-channel code CTF are coupled for Xi’an Pulsed Reactor (XAPR) pulse and depletion simulation. A python script is developed to handle data exchange through files. $3.45 pulse and $2 pulse are simulated with the pulsed state core. The pulse peak power and the Full Width at Half-Maximum (FWHM) results are compared with experiments as a validation and good agreement is achieved. Detailed 3-D power and temperature distributions are also obtained. Results show that the core power peak is close to the pulse rod where the reactivity is introduced. The radial power peak of each rod is at the boundary because of the self-shielding effect. The rod temperature distribution follows the same trend with the power, and the coolant temperature is not changed during the pulse period of about 0.12 s, which suggests that the heat transfer plays a negligible role in such a short time. For the steady state core, depletion simulation is carried out for the lifetime of the first fuel cycle of 120 Effective Full Power Days (EFPD). Validation is done by calculating the temperature distribution and the differential worth of the regulating rod at 0 EFPD, which both agree well with experiments. Results show that the power distribution is almost unchanged over time, only slightly more flat, indicating the material is not greatly depleted. The temperature distribution of the core generally agrees with the power distribution, except the radial temperature peak of each rod is at the center because heat is conducted outwards at steady state. Detailed coolant temperature distribution is obtained thanks to the utilization of CTF. Temperatures at the assembly boundary and near the central water chamber is noticeably lower than the other part, which is not shown in the parallel multi-channel models.

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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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