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A neural network to predict reactor core behaviors 被引量:1
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作者 Juan Jose Ortiz-Servin David A.Pelta Jose Alejro Castillo 《Nuclear Science and Techniques》 SCIE CAS CSCD 2014年第1期75-80,共6页
The global fuel management problem in BWRs(Boiling Water Reactors) can be understood as a very complex optimization problem,where the variables represent design decisions and the quality assessment of each solution is... The global fuel management problem in BWRs(Boiling Water Reactors) can be understood as a very complex optimization problem,where the variables represent design decisions and the quality assessment of each solution is done through a complex and computational expensive simulation.This last aspect is the major impediment to perform an extensive exploration of the design space,mainly due to the time lost evaluating non promising solutions.In this work,we show how we can train a Multi-Layer Perceptron(MLP) to predict the reactor behavior for a given configuration.The trained MLP is able to evaluate the configurations immediately,thus allowing performing an exhaustive evaluation of the possible configurations derived from a stock of fuel lattices,fuel reload patterns and control rods patterns.For our particular problem,the number of configurations is approximately 7.7×10^(10);the evaluation with the core simulator would need above 200 years,while only 100hours were required with our approach to discern between bad and good configurations.The later were then evaluated by the simulator and we confirm the MLP usefulness.The good core configurations reached the energy requirements,satisfied the safety parameter constrains and they could reduce uranium enrichment costs. 展开更多
关键词 神经网络预测 行为 质量评估 堆芯 沸水反应堆 多层感知器 MLP 优化问题
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Wide Range Neutron Monitoring(WRNM)System in Boiling Water Reactors(A Short Communication&Memorandum)
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作者 Seyed Kamal Mousavi Balgehshiri Ali Zamani Paydar Bahman Zohuri 《Journal of Energy and Power Engineering》 2022年第5期186-212,共27页
The WRNM(wide range neutron monitoring)is a newly developed neutron monitoring channel which was initially conceived as a means to meet Regulatory Guide 1.97 requirements for post-accident neutron monitoring.The scope... The WRNM(wide range neutron monitoring)is a newly developed neutron monitoring channel which was initially conceived as a means to meet Regulatory Guide 1.97 requirements for post-accident neutron monitoring.The scope was expanded to include the startup monitoring function with the aim of replacing both the source and IRMs(intermediate range monitors)in BWRs(boiling water reactors).The WRNMs,consisting of a newly designed fixed incore regenerative sensor and new electronics,which include both counting and MSV(mean square voltage)channels,have been tested in several reactors and its capabilities have been confirmed.The channel will cover the neutron flux range from 103 nv to 1.5×103 nv;it has greater than 1 decade overlap between the counting and MSV channels.Because of the regenerative fissile coating the sensor,even though fixed incore,has a life of approximately 6.0 full power years in a 51 kW/L BWR and similar situation has been proposed for newly designed small modular reactor such as BWRX-300 of General Electric Hitachi reactor. 展开更多
关键词 bwr light water reactor advanced reactor advanced small modular reactor high temperature advanced reactor Generation IV nuclear power reactors nuclear energy nuclear radiation environment
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Analysis of Neutronic Characteristics of Uranium Zirconium Hydride Fuel in Advanced Boiling Water Reactor
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作者 Ahmed Abdelghafar Galahom Ibrahim Ismail Bashter Moustafa Aziz 《材料科学与工程(中英文A版)》 2013年第6期437-442,共6页
关键词 先进沸水堆 燃料组件 中子通量 氢化锆 蒙特卡罗法 特性 三维模型 Abwr
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中国核电发展的安全性研究 被引量:12
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作者 周涛 李精精 侯周森 《华北电力大学学报(社会科学版)》 2011年第2期1-6,共6页
安全是中国核电发展的第一原则。核电标准建设是核电安全发展的前提;先进的核电技术是核电安全性的基础;核安全文化是核电站安全运行的重要保障。对比中国压水堆和日本福岛沸水堆,本文阐述了中国现有的压水堆及正在发展的第三代AP1000... 安全是中国核电发展的第一原则。核电标准建设是核电安全发展的前提;先进的核电技术是核电安全性的基础;核安全文化是核电站安全运行的重要保障。对比中国压水堆和日本福岛沸水堆,本文阐述了中国现有的压水堆及正在发展的第三代AP1000的典型安全特征。通过吸取福岛核电站事故教训,不断改进中国核电发展中的一些问题,严格有效地执行完善的核电技术标准,积极发展先进的核电安全技术,中国核电就会得到安全快速发展。 展开更多
关键词 压水堆 沸水堆 标准 技术 文化 安全性
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福岛核电事故分析及其启示 被引量:8
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作者 王庆红 龚婷 《南方电网技术》 2011年第3期17-22,共6页
2011年3月11日日本发生的9.0级地震引发了日本福岛第一核电站7级核泄漏事故,该事故成为近期全世界关注的热点。介绍了福岛核电事故的经过、分析了事故的原因、影响及启示。地震和海啸是表面的诱因,深层的原因则是很复杂的。从技术上层... 2011年3月11日日本发生的9.0级地震引发了日本福岛第一核电站7级核泄漏事故,该事故成为近期全世界关注的热点。介绍了福岛核电事故的经过、分析了事故的原因、影响及启示。地震和海啸是表面的诱因,深层的原因则是很复杂的。从技术上层面上讲,核事故的原因主要归结为3个方面:福岛核电采用了安全性不够好的核电第二代技术,核电站的抗震能力设计不足,且其1号机组超设计寿期运行。通过AP1000和ERP的安全系统在设计、性能、技术等方面比较,认为在安全性方面核电第三代技术AP1000比EPR要优越得多。针对我国现时核电是第二代技术和第三代技术并存,探讨了中国核电的安全监督制度、核电主力堆型的发展方向、应急联动机制以及应急预案。 展开更多
关键词 日本3·11大地震 福岛核电事故 核电技术 非能动系统 沸水堆 欧洲压水堆
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Feasibility Study of RNPP (Rooppur Nuclear Power Project) in Bangladesh
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作者 Tausif Ali Iftekhar Zaman Arnab +3 位作者 Saiful Islam Bhuiyan Anik , Rahman Iftekhar Hossain M. Shidujaman 《Energy and Power Engineering》 2013年第4期1526-1530,共5页
Bangladesh is densely populated country with a population of 16 core and small area about 1, 47,570 Square-Kilometer. Among these large population only a few section are taking the blessings of power. But now at a sta... Bangladesh is densely populated country with a population of 16 core and small area about 1, 47,570 Square-Kilometer. Among these large population only a few section are taking the blessings of power. But now at a stage government can’t give the power even to that special section. Because day by day population is increasing and also power demands is also increasing. Governments are trying to meet up the power crisis in Bangladesh by taking various steps. Like small (10-20MW) power plants, IPP, Rental power plant etc. But these are not a permanent solution. More over these rental and IPP are mainly oil and gas based, which are very costly and not very efficient. Besides these government are going with coal based power station and small scale renewable energy. But coal based power station are required very large space, its initial cost is high and create serious environmental threat. Renewable energy is not yet developed and its efficiency is very poor. Though there are many problems and threats but Nuclear Power Plant can be a permanent solution for Bangladesh. Bangladesh government is now going for nuclear power plant and recently they have taken a project called Rooppur Nuclear Power Plant Project (RNPP) which is already approved in the cabinet meeting. The purpose of this paper is to study the feasibility of RNPP. 展开更多
关键词 BANGLADESH NUCLEAR Power Roopppur reactor RADIOACTIVE PWR bwr Desaster URANIUM Security Planning Development
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Improvement of solidification model and analysis of 3D channel blockage with MPS method
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作者 Reo KAWAKAMI Xin LI +3 位作者 Guangtao DUAN Akifumi YAMAJI Isamu SATO Tohru SUZUKI 《Frontiers in Energy》 SCIE CSCD 2021年第4期946-958,共13页
In a severe accident of a nuclear power reactor,coolant channel blockage by solidified molten core debris may significantly influence the core degradations that follow.The moving particle semi-implicit(MPS)method is o... In a severe accident of a nuclear power reactor,coolant channel blockage by solidified molten core debris may significantly influence the core degradations that follow.The moving particle semi-implicit(MPS)method is one of the Lagrangian-based particle methods for analyzing incompressible flows.In the study described in this paper,a novel solidification model for analyzing melt flowing channel blockage with the MPS method has been developed,which is suitable to attain a sufficient numerical accuracy with a reasonable calculation cost.The prompt velocity diffusion by viscosity is prioritized over the prompt velocity correction by the pressure term(for assuring incompressibility)within each time step over the“mushy zone”(between the solidus and liquidus temperature)for accurate modeling of solidification before fixing the coordinates of the completely solidified particles.To sustain the numerical accuracy and stability,the corrective matrix and particle shifting techniques have been applied to correct the discretization errors from irregular particle arrangements and to recover the regular particle arrangements,respectively.To validate the newly developed algorithm,2-D benchmark analyses are conducted for steady-state freezing of the water in a laminar flow between two parallel plates.Furthermore,3-D channel blockage analyses of a boiling water reactor(BWR)fuel support piece have been performed.The results show that a partial channel blockage develops from the vicinity of the speed limiter,which does not fully develop into a complete channel blockage,but still diverts the incoming melt flow that follows to the orifice region. 展开更多
关键词 boiling water reactor(bwr) severe accident channel blockage moving particle semi-implicit(MPS)method solidification*
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