云南高校图书馆联盟文献共享服务平台- NEUTRONIC

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Neutronic study on the effect of first wall material thickness on tritium production and material damage in a fusion reactor被引量：2: 《Nuclear Science and Techniques》2022年第4期33-50,共18页HacıMehmet S¸ahin Güven Tunc¸ Alper Karakoc¸ Melood Mohamad Omar; In this study,the effects of changing first wall materials and their thicknesses on a reactor were investigated to determine the displacement per atom(DPA)and gas production(helium and hydrogen)in the first wall,as we...; 关键词：ITER First wall material Material damage Tritium breeding ratio Fluorides family molten salt materials

Optimization of spatial structure designs of control rod using Monte Carlo code RMC: 《Frontiers in Energy》2021年第4期974-983,共10页Hao LUO Mancang LI Shanfang HUANG Minyun LIU Kan WANG; the National Key R&D Project(Grant No.2020YFB1901700);the National Natural Science Foundation of China(Grant No.11775127).; Control rod is the most important approach to control reactivity in reactors,which is currently a cluster of pins filled with boron carbide(B4C).In this case,neutrons are captured in the outer region,and thus the inne...; 关键词：control rod optimized spatial structure neutronic performance burnup stability

Neutronic calculations of the China dual-functional lithium–lead test blanket module with the parallel discrete ordinates code Hydra被引量：2: 《Nuclear Science and Techniques》2020年第8期1-12,共12页Guang-Chun Zhang Jie Liu Liang-Zhi Cao Hong-Chun Wu Xian-Bao Yuan; the National Key Research and Development Program of China(Nos.2018YFB0204301,2017YFB0202104,and 2017YFE0302200)。; The China dual-functional lithium–lead test blanket module(DFLL-TBM) is a liquid Li Pb blanket concept developed by the Institute of Nuclear Energy Safety Technology of the Chinese Academy of Sciences for testing in ...; 关键词：Discrete ordinates method DFLL-TBM Neutronic analysis Tritium breeding performance

Preliminary performance analysis and optimization based on 1D neutronics model for Indian DEMO HCCB blanket: 《Plasma Science and Technology》2020年第8期184-191,共8页D AGGARWAL C DANANI M Z YOUSSEF; India,under its breeding blanket R&D program for DEMO,is focusing on the development of two tritium breeding blanket concepts;namely the lead-lithium-cooled ceramic breeder and the helium-cooled ceramic breeder(HCCB)....; 关键词：DEMO helium-cooled ceramic BREEDER BLANKET NEUTRONIC optimization study tritium breeding ratio

Recent studies on potential accident-tolerant fuel-cladding systems in light water reactors被引量：7: 《Nuclear Science and Techniques》2020年第3期94-123,共30页Sheng-Li Chen Xiu-Jie He Cen-Xi Yuan; supported by the National Key Research and Development Program of China(No.2018YFB1900405);the National Natural Science Foundation of China(No.11775316);the Tip-top Scientific and Technical Innovative Youth Talents of Guangdong Special Support Program(No.2016TQ03N575);the Fundamental Research Funds for the Central Universities(No.19lgpy299);the Science and Technology Planning Project of Guangdong Province,China(No.2019A050510022);the Nuclear Power Institute of China(No.HT-ATF-14-2018001); Accident-tolerant fuel(ATF)has attracted considerable research attention since the 2011 Fukushima nuclear disaster.To improve the accident tolerance of the fuel-cladding systems in the current light-water reactors,it ...; 关键词：Accident-tolerant fuel Accident-tolerant cladding Light-water reactor Neutronic evaluation

A neutronic experiment to support the design of an Indian TBM shield module for ITER被引量：2: 《Plasma Science and Technology》2019年第6期147-152,共6页H L SWAMI M ABHANGI Sanchit SHARMA S TIWARI A N MISTRY V VASAVA V MEHTA S VALA C DANANI V CHAUDHARI P CHAUDHURI; A shield module is associated with an Indian Test Blanket Module (TBM) in ITER to limit the radiation doses in port inter-space areas.The shield module is made of stainless steel plates and water channels.It is identi...; 关键词：TBM SHIELD MODULE NEUTRONIC EXPERIMENT ITER MCNP neutron attenuation

Neutronic analysis of silicon carbide cladding accident-tolerant fuel assemblies in pressurized water reactors被引量：5: 《Nuclear Science and Techniques》2019年第3期105-113,共9页Zhi-Xiong Tan Jie-Jin Cai; supported by the National Natural Science Foundation of China(No.11675057);the Fundamental Research Funds for the Central Universities(No.2017ZD100); In resonance with the Fukushima Daiichi Nuclear Power Plant accident lesson, a novel fuel design to enhance safety regarding severe accident scenarios has become increasingly appreciated in the nuclear power industry....; 关键词：Accident-tolerant fuels Silicon CARBIDE CLADDING NEUTRONIC characteristics Pressurized water reactor

Neutronic analysis of ITER radial x-ray camera被引量：2: 《Plasma Science and Technology》2019年第2期105-112,共8页Luying NIU Hongrui CAO Kun XU Liqun HU; supported by National Natural Science Foundation of China (No. 11605240);China International Nuclear Fusion Energy Program Execution Center Radial x-ray Camera Design Contract (No. 5.5.P1.CN.02/1A); The radial x-ray camera(RXC) is designed to measure the poloidal profile of plasma x-ray emission with high spatial and temporal resolution. The RXC diagnostic system consists of internal camera module and external ca...; 关键词：TOKAMAK RADIAL X-RAY CAMERA NEUTRONIC

Prediction of Neutronic and Kinetic Parameters of Ghana Research Reactor 1 (GHARR-1) after 19 Years of Operation Using Monte Carlo-N Particle (MCNP) Code: 《World Journal of Nuclear Science and Technology》2018年第4期160-175,共16页Bright Madinka Mweetwa Emmanuel Ampomah-Amoako Edward Horga Kordzo Akaho Cecil Odoi; The Ghana Research Reactor-1 (GHARR-1) core was modified with an addition of a 9.0 mm layer of beryllium to the top shim tray to compensate for reactivity loss due to fuel depletion after 19 years of operation. Neutro...; 关键词：Delayed NEUTRON Fraction NEUTRON Generation Time MODERATOR REACTIVITY Coefficient Power Peaking Factor

Neutronic design investigation of a liquid injection-based second shutdown system for a typical research reactor using MCNPX被引量：1: 《Nuclear Science and Techniques》2018年第3期51-60,共10页Ehsan Boustani Mostafa Hassanzadeh; Safety systems, built on state-of-the-art technology, are essential for achieving acceptable levels of plant safety to minimize hazards to the reactor and the general public. The second shutdown system(SSS) as an engi...; 关键词：TEHRAN research reactor SECOND SHUTDOWN system Nuclear safety Design criteria MCNPX code

NEUTRONIC