云南高校图书馆联盟文献共享服务平台- PWR

PWR: 作品数：214被引量：197H指数：6; 导出分析报告; 相关领域：核科学技术更多>>; 相关作者：张乐福欧阳钦杨高升谢仲生徐雪莲更多>>; 相关机构：西安交通大学中国原子能科学研究院清华大学中国核动力研究设计院更多>>; 相关期刊：更多>>; 相关基金：国家自然科学基金中央高校基本科研业务费专项资金国家科技重大专项国家高技术研究发展计划更多>>

基于NRSTAP-PWR程序的压水堆放射性源项计算研究: 《核科学与技术》2025年第1期1-10,共10页雷星张竞宇郑浩杨晨由立松; 国家磁约束核聚变能发展研究专项(2019YFE03110000、2019YFE03110003),中央高校基本科研业务费专项(2024MS050)。; 放射性源项是用于评价核电厂正常运行期间放射性释放对环境影响的基础数据。本文研究了压水堆中放射性核素的迁移、吸附、滞留、衰变规律,根据放射性核素在系统中的产生和消失机理,建立了计算放射性核素活度的数学模型,开发了相应的计...; 关键词：压水堆源项放射性核素 NRSTAP-PWR程序

Proposal of a Deuterium-Deuterium Fusion/PWR Fission Hybrid Reactor: 《World Journal of Nuclear Science and Technology》2024年第4期190-233,共44页Patrick Lindecker; This article proposes to associate a Deuterium-Deuterium (D-D) fusion reactor with a PWR (fission Pressurized Water Reactor) in a hybrid reactor. Even if the mechanical gain (Q factor) of the D-D fusion reactor is bel...; 关键词：Fusion Reactor Fission Reactor Hybrid Reactor Nuclear Energy Deuterium-Deuterium Reactor DEUTERIUM Colliding Beams Racetrack STELLARATOR Power Plant PWR

自主化压水堆子通道分析软件传热模型分析: 《科学技术与工程》2024年第32期13819-13825,共7页贾斌温爽史强乔雪冬靖剑平高新力; 核能开发科研项目(KGJ-LH2201);国家科技重大专项(2019ZX06005001)。; 为更好地开展自主化压水堆(pressurized water reactor,PWR)子通道分析软件传热模型的评价工作,对国家核安全局目前在审的几款国产自主化压水堆子通道分析软件的传热模型开展分析研究。首先,确认传热模型对于自主化压水堆子通道分析软...; 关键词：自主化压水堆(PWR) 子通道分析软件传热模型软件评价核态沸腾起始点(ONB)

From Chooz to the Ling'ao NPP:The Technology Transfer of Pressurized Water Reactor Technology from France to China: 《Chinese Annals of History of Science and Technology》2024年第1期97-124,共28页CHEN Yue LI Yunyi; a phase study of a key project of the Fourteenth Five-Year Plan of the Institute for the History of Natural Sciences,Chinese Academy of Sciences:“A Comparative Study of the Sino-Foreign History of Scientific and Technological Innovation:The Road to Scientific and Technological Self-Reliance and Self-Improvement”,E2291J01。; The transfer of pressurized water reactor(PWR)technology from France to China is an important event in the history of Sino-French scientific and technological relations.China has gradually achieved self-reliance in th...; 关键词：pressurized water reactor(PWR) technology transfer Sino-French relations Chooz NPP Daya Bay NPP Ling'ao NPP

A Monte Carlo method for quantitatively calculating the neutron sensitivity of rhodium self-powered neutron detectors in reactors: 《Radiation Detection Technology and Methods》2024年第2期1162-1170,共9页Xiong Wu Jieqiong Jiang Tingyu Wu Shijie Luo; Purpose Self-powered neutron detectors(SPNDs)with rhodium emitters exhibit high thermal neutron sensitivity and extensively equipped in nuclear reactors for core monitoring.The neutron sensitivity of SPND is the most ...; 关键词：Rhodium SPND PWR Reactor monitoring Neutron sensitivity Monte Carlo method

Response characteristics of PWR primary circuit under SBLOCAs considering steam bypass discharging: 《Nuclear Science and Techniques》2024年第6期189-201,共13页Shuai Yang Xiang-Bin Li Yu-Sheng Liu Jia-Ning Xu De-Chen Zhang; Small-break superposed station blackout(SBO)accidents are the basic design accidents of nuclear power plants.Under the condition of a small break in the cold leg,SBO further increases the severity of the accident,and ...; 关键词：Steam bypass discharging Pressurized water reactor SBLOCA Numerical simulation

肺癌患者血清LDH、CysC、PWR水平检测意义被引量：1: 《昆明医科大学学报》2024年第4期163-169,共7页王缨傅聪傅颖; 常州市卫生健康青苗人才基金资助项目(CZQM2023022)。; 目的探究肺癌患者血清乳酸脱氢酶(LDH)、半胱氨酸蛋白酶抑制剂C(CysC)、血小板/白细胞比值(PWR)水平检测意义。方法2023年1月至2023年6月选取常州市第四人民医院72例肺癌患者设为观察组,另选取同期肺部良性病变患者72例设为对照组,比较2...; 关键词：肺癌乳酸脱氢酶半胱氨酸蛋白酶抑制剂C 血小板/白细胞比值

压水堆燃料元件腐蚀产物沉积行为试验研究进展: 《腐蚀与防护》2024年第3期61-68,共8页吴宗佩姜峨唐月明熊静邓平赵永福张萍萍; 压水堆(PWR)燃料元件表面腐蚀产物沉积(CRUD)对系统稳定可靠运行产生诸多不利影响,因此研究压水堆燃料元件腐蚀产物沉积的关键影响因素,并针对性地开发CRUD缓解技术,对压水堆的安全和高质量发展至关重要。归纳了压水堆燃料元件表面CRUD...; 关键词：腐蚀产物沉积(CRUD) 试验研究燃料元件压水堆(PWR)

Uncertainty and sensitivity analysis of in-vessel phenomena under severe accident mitigation strategy based on ISAA-SAUP program: 《Nuclear Science and Techniques》2024年第1期108-123,共16页Hao Yang Ji-Shen Li Zhi-Ran Zhang Bin Zhang Jian-Qiang Shan; This work was supported financially by the National Natural Science Foundation of China(No.12375176).; The phenomenology involved in severe accidents in nuclear reactors is highly complex.Currently,integrated analysis programs used for severe accident analysis heavily rely on custom empirical parameters,which introduce...; 关键词：Gen-III PWR Severe accident mitigation Wilks’formula HYDROGEN Fission products Uncertainty and sensitivity analysis

Preparation and properties of Ti_(3)SiC(2) -based corrosion mitigation coatings for SiC_(f) /SiC PWR accident tolerant fuel cladding被引量：3: 《Journal of Advanced Ceramics》2024年第1期73-85,共13页Jinsong Yang Fang Ye Laifei Cheng Kai Zhao Yucong Wei; supported by the National Natural Science Foundation of China(Nos.52072304 and 52172100);the Science Center for Gas Turbine Project(No.P2022-B-IV-002-001);Key Research and Development Program of Shaanxi(No.2022GY367);the 111 Project of China(No.B08040).; To enhance the resistance of SiC_(f)/SiC to hydrothermal corrosion in the pressurized water reactor(PWR)environment,structurally tunable Ti_(3)SiC(2)-based corrosion mitigation coatings for SiC_(f)/SiC were prepared u...; 关键词：Ti_(3)SiC(2) SiC_(f)/SiC nuclear materials hydrothermal corrosion coating

PWR