摘要:
小型棒控压水堆舍弃了可溶硼,并高度依赖控制棒与可燃毒物棒控制堆芯的反应性.为研究控制棒对堆芯关键性能的影响,本文以核动力破冰船用KLT-40模型为对象,以轴向功率偏移、堆芯寿期、燃料利用率与径向功率峰因子为指标,开展长寿期小型棒控压水堆控制棒布置与动作策略设计分析.首先,基于OpenMC程序开发带棒燃耗程序;其次,比较堆芯带控制棒与无控制棒运行时的堆芯寿期等指标;最后,分析不同动作策略对轴向功率偏移等指标的影响.结果表明:控制棒将堆芯寿期从590 EFPDs(等效满功率天,Effective full power days)延长至650~698 EFPDs;低价值棒组优先动作策略使轴向功率偏移程度由-0.69与+0.80分别下降至-0.29与+0.52.因此,要准确计算长寿期压水堆寿期必须采用带控制棒燃耗计算策略,并且通过合理的动作策略能够有效减小控制棒带来的轴向功率偏移.
通讯机构:
[Xie, JS ; Yu, T] U;Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Peoples R China.;Minist Educ, Key Lab Adv Nucl Energy Design & Safety, Hengyang 421001, Peoples R China.
关键词:
data-driven;deep neural networks;infinite multiplication factor k(inf);neutron transport equation
摘要:
With the continuous development of computer technology, artificial intelligence has been widely applied across various industries. To address the issues of high computational cost and inefficiency in traditional numerical methods, this paper proposes a data-driven artificial intelligence approach for solving high-dimensional neutron transport equations. Based on the AFA-3G assembly model, a neutron transport equation solving model is established using deep neural networks, considering factors that influence the neutron transport process in real engineering scenarios, such as varying temperature, power, and boron concentration. Comparing the model's predicted values with reference values, the average error in the infinite multiplication factor k(inf) of the assembly is found to be 145.71 pcm (10(-5)), with a maximum error of 267.10 pcm. The maximum relative error is less than 3.5%, all within the engineering error standards of 500 pcm and 5%. This preliminary validation demonstrates the feasibility of using data-driven artificial intelligence methods to solve high-dimensional neutron transport equations, offering a new option for engineering design and practical engineering computations.
作者:
Liu, Hongliang;Zeng, Wenjie;Xie, Jinsen;Luo, Run
期刊:
PROCEEDINGS OF THE INSTITUTION OF CIVIL ENGINEERS-ENERGY,2024年307:132645 ISSN:1751-4223
通讯作者:
Zeng, WJ
作者机构:
[Liu, Hongliang] Univ South China, Sch Math & Phys, Hengyang 421001, Peoples R China.;[Zeng, Wenjie; Zeng, WJ; Xie, Jinsen] Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Peoples R China.;[Luo, Run] Univ South China, Sch Resources Environm & Safety Engn, Hengyang 421001, Peoples R China.
通讯机构:
[Zeng, WJ ] U;Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Peoples R China.
关键词:
RBF neural networks;Chattering-free fixed-time stable;Event-triggered mechanism;Load following of PWR
摘要:
Preventing chattering phenomenon in load following control of the Pressurized Water Reactor (PWR) is still a main challenge. This article focuses on the chattering-free and rapid load following control strategy for PWR. Firstly, by proposing a newly adaptive updated law, the Radial Basis Function Neural Networks (RBFNNs) is employed to compensate the unmeasured states of relative delayed neutron precursor density, average fuel temperature and uncertain disturbances simultaneously online. On this basis, a fixed-time stable controller including saturation function is constructed to guarantee that the actual output power (OP) of nuclear reactor can follow the desired power (DP) within a fixed-time and the chattering phenomenon is alleviated. Additionally, to save the limited network resource and reduce the cost of computation, an event- triggered mechanism is constructed. Based on it, a chattering-free fixed-time stable controller is structured to ensure that the actual reactivity of control rod (ARCR) converges to the desired control rod reactivity (DCRR) within a fixed-time, meanwhile, it can eliminate Zeno phenomenon during the control process. Finally, the effectiveness and feasibility of the theoretical results are demonstrated through simulation examples.
摘要:
<jats:p>In response to the significant dependency on empirical judgment in measuring the prompt neutron decay constant with the traditional Rossi-alpha method and the issue of requiring an excessive number of detectors with the DMD-Rossi-alpha method, this paper introduces a calculation method for the prompt neutron decay constant based on a combination of Latin Hypercube Sampling (LHS), Dynamic Mode Decomposition (DMD), and the Rossi-alpha method. Initially, the method uses LHS to expand the sample dataset of neutron noise data to reduce the number of detectors required. It then employs the Rossi-alpha method to construct a Rossi-alpha distribution model from neutron noise data. Finally, it utilizes DMD for feature extraction from the Rossi-alpha distribution model, thereby determining the prompt neutron decay constant. Research findings demonstrate that, by simulating the KUCA facility using RMC3.5 in a near-critical state, the relative error of the α value calculated by the LHS-DMD-Rossi-alpha method model is 9% less than that calculated by the Rossi-alpha method. This approach, capable of enhancing the precision of measuring the prompt neutron decay constant with just a single detector, holds significant theoretical value and engineering significance for the advancement of reactor physics and experimental techniques.</jats:p>
摘要:
The helical-coiled once-through steam generator (H-OTSG) has the advantages of compact structure and strong heat transfer ability, and is appropriate for lead-cooled fast reactor. The two-phase flow instability may cause mechanical vibration and thermal fatigue of heat transfer tube bundles, posing a serious threat to the safe operation of the H-OTSG. In this work, the secondary side of the H-OTSG characterized as multi-parallel channels is modeled by RELAP5/MOD3.4 code, and the oscillation behavior during start-up and the influence of structural and operating parameters on system stability are studied based on time-domain method. The results indicate that the pressure, flow rate, and temperature of the secondary fluid exhibit density wave oscillations at the heating section in a (n-2,2) pattern. In addition, increasing inlet throttling, reducing outlet throttling, controlling subcooling within an appropriate range and avoiding operation under low loads are all beneficial for improving the system stability of the helical-coiled once-through steam generator.
摘要:
<jats:title>Abstract</jats:title>
<jats:p>Previous simulations studying winds only focus on the line force due to photons from central active galactic nuclei. What properties of the winds will be when including the re-radiation force due to the scattered and reprocessed photons (i.e., the re-radiation effect)? We perform simulations to study the large-scale dynamics of accretion disk winds driven by radiation line force and re-radiation force. For the fiducial run, we find that the re-radiation force drives stronger outflows during the early stages. When the flows get into the steadiness, the UV radiation due to spectral lines dominates total radiation and the re-radiation effect could be negligible. The opening angle of winds narrows as the initial gas density increases. The larger the gas density is, the stronger the re-radiation effect will be. For <jats:italic>M</jats:italic>
<jats:sub>BH</jats:sub> = 10<jats:sup>6</jats:sup>
<jats:italic>M</jats:italic>
<jats:sub>⊙</jats:sub>, <jats:italic>ε</jats:italic> = 0.3, the outflows do become much stronger with the re-radiation effect and the winds still cannot escape from gravitational potential. We find that the detection probability of ultra-fast outflows and the properties of the winds are both consistent with the observations.</jats:p>
作者:
Ni, Zining;Xie, Jinsen*;Wasaye, Muhammad Abdul;Zhang, Erpin;Yu, Tao
期刊:
International Journal of Energy Research,2023年2023:1-14 ISSN:0363-907X
通讯作者:
Xie, Jinsen;Yu, T
作者机构:
[Wasaye, Muhammad Abdul; Zhang, Erpin; Xie, Jinsen; Ni, Zining; Yu, Tao] Univ South China, Sch Nucl Sci & Technol, Hengyang, Hunan, Peoples R China.;[Wasaye, Muhammad Abdul; Zhang, Erpin; Xie, Jinsen; Ni, Zining; Yu, Tao] Univ South China, Res Ctr Digital Nucl Reactor Engn & Technol Hunan, Hengyang, Hunan, Peoples R China.;[Xie, Jinsen; Yu, Tao] Univ South China, Sch Nucl Sci & Technol, Hengyang, Hunan, Peoples R China.;[Xie, Jinsen; Yu, Tao] Univ South China, Res Ctr Digital Nucl Reactor Engn & Technol Hunan, Hengyang, Hunan, Peoples R China.
通讯机构:
[Xie, JS; Yu, T ] ;Univ South China, Sch Nucl Sci & Technol, Hengyang, Hunan, Peoples R China.;Univ South China, Res Ctr Digital Nucl Reactor Engn & Technol Hunan, Hengyang, Hunan, Peoples R China.
关键词:
Computation theory;Harmonic analysis;Modal analysis;Neutron sources;Perturbation techniques;Accelerator-driven subcritical reactors;High order harmonics;High-order;Higher order harmonics;Higher-order;Modal kinetics;Perturbation theory;Physical characteristics;Power;Steady state;Neutron flux
作者机构:
[Deng, Nianbiao] Univ South China, Sch Resource Environm & Safety Engn, Hengyang 421001, Peoples R China.;[Xie, Chao; Xie, Jinsen; Yu, Tao] Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Peoples R China.;[Hou, Cheng] China Inst Atom Energy, Beijing 102413, Peoples R China.;[Li, Zhulun] North China Elect Power Univ, Sch Nucl Sci & Engn, Beijing 102206, Peoples R China.
通讯机构:
[Jinsen Xie; Tao Yu] A;Authors to whom correspondence should be addressed.<&wdkj&>School of Nuclear Science and Technology, University of South China, Hengyang 421001, China
关键词:
ADS Subcritical Reactor;deep subcriticality;heterogeneity of neutron fluence rate in time–space;Monte Carlo homogenization method;neutron kinetics
通讯机构:
[Jinsen Xie; Tao Yu] A;Authors to whom correspondence should be addressed.<&wdkj&>School of Nuclear Science and Technology, University of South China, Hengyang 421001, China
关键词:
KLT-40S;assembly design;optimal burnup lattice;local power peaking factor;power-flattening design
作者:
Wu, Zhiqiang;Chen, Pengyu;Xie, Jinsen;Zhou, Zedong;Yu, Tao
期刊:
Springer Proceedings in Physics,2023年285 SPPHY:656-663 ISSN:1867-4941
通讯作者:
Xie, Jinsen(jinsen_xie@usc.edu.cn)
作者机构:
School of Nuclear Science and Technology, University of South China, Hunan, Hengyang, China;Virtual Simulation Experiment Teaching Center on Nuclear Energy and Technology, University of South China, Hunan, Hengyang;421001, China;[Wu, Zhiqiang; Chen, Pengyu; Xie, Jinsen; Zhou, Zedong; Yu, Tao] School of Nuclear Science and Technology, University of South China, Hunan, Hengyang, China <&wdkj&> Virtual Simulation Experiment Teaching Center on Nuclear Energy and Technology, University of South China, Hunan, Hengyang;[Wu, Zhiqiang; Chen, Pengyu; Xie, Jinsen; Zhou, Zedong; Yu, Tao] 421001, China
作者:
Zhang, Chunyuan;Chen, Pengyu;Jiang, Fangling;Xie, Jinsen;Yu, Tao
期刊:
Energies,2023年16(6):2934- ISSN:1996-1073
通讯作者:
Xie, J.;Yu, T.
作者机构:
[Chen, Pengyu; Zhang, Chunyuan; Xie, Jinsen; Yu, Tao] Univ South China, Sch Nucl Sci & Technol, Hengyang 421000, Peoples R China.;[Chen, Pengyu; Zhang, Chunyuan; Xie, Jinsen; Yu, Tao] Univ South China, Res Ctr Digital Nucl Reactor Engn & Technol Hunan, Hengyang 421000, Peoples R China.;[Jiang, Fangling] Univ South China, Coll Comp Sci, Hengyang 421000, Peoples R China.
通讯机构:
[Jinsen Xie; Tao Yu] A;Authors to whom correspondence should be addressed.<&wdkj&>School of Nuclear Science and Technology, University of South China, Hengyang 421000, China<&wdkj&>Research Center for Digital Nuclear Reactor Engineering and Technology of Hunan Province, University of South China, Hengyang 421000, China
作者:
Wasaye, Muhammad Abdul;Yu, Tao;Xie, Jinsen;Chen, Zhenping;Ni, Zining
期刊:
Journal of the Korean Physical Society,2023年82(10):954-962 ISSN:0374-4884
通讯作者:
Muhammad Abdul Wasaye<&wdkj&>Tao Yu<&wdkj&>Jinsen Xie
作者机构:
[Wasaye, Muhammad Abdul; Chen, Zhenping; Xie, Jinsen; Ni, Zining; Yu, Tao] Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Hunan, Peoples R China.
通讯机构:
[Muhammad Abdul Wasaye; Tao Yu; Jinsen Xie] S;School of Nuclear Science and Technology, University of South China, Hengyang, China<&wdkj&>School of Nuclear Science and Technology, University of South China, Hengyang, China<&wdkj&>School of Nuclear Science and Technology, University of South China, Hengyang, China
关键词:
Monte Carlo;Radiotherapy;Bremsstrahlung;Differential cross-section;Energy distribution;Angular distribution