RESEARCH_REACTOR

作品数：37被引量：31H指数：3
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Management System Activities of the Operation and Utilization of GHARR-1
《World Journal of Engineering and Technology》2023年第4期807-826,共20页Edward Shitsi Henry Cecil Odoi Kwame Gyamfi Philip Dordoh-Gasu Isaac Kwasi Baidoo Edward Oscar Amponsah-Abu Emmanuel Kwesi Boafo Samuel Yao Ganyaglo Samuel Boakye Dampare Henry Kwame Obeng William Osei-Mensah Wilfred Sedofia Massiasta Robert Ekow Quagraine 
The Ghana Research Reactor-1 (GHARR-1) is a 34 kW low enriched uranium (LEU) Miniature Neutron Source Reactor (MNSR), tank-in-pool type and cooled by natural circulation under atmospheric pressure operating conditions...
关键词：Management Systems Quality Assurance and Quality Control Research Re-actor Operation and Utilization Monitoring Forms Ghana Research Reactor-1 (GHARR-1) 
Application of silicon carbide temperature monitors in 49-2 swimming-pool test reactor被引量：1
《Chinese Physics B》2023年第5期97-101,共5页宁广胜 张利民 钟巍华 王绳鸿 刘心语 汪定平 何安平 刘健 张长义 
High purity SiC crystal was used as a passive monitor to measure neutron irradiation temperature in the 49-2 research reactor.The SiC monitors were irradiated with fast neutrons at elevated temperatures to 3.2×10^(20...
关键词：silicon carbide irradiation temperature monitor research reactor 
Conceptual design and safety characteristics of a new multi-mission high flux research reactor被引量：3
《Nuclear Science and Techniques》2023年第3期9-24,共16页Wei Xu Jian Li Heng Xie Zhi-Hong Liu Jing Zhao Fei Xie Lei Shi 
Research reactors with neutron fluxes higher than 10^(14) n cm^(−2) s^(−1) are widely used in nuclear fuel and material irradiation,neutron-based scientific research,and medical and industrial isotope production.Such ...
关键词：High flux research reactor Neutron flux Safety analysis Maximum temperature of cladding surface Departure from nucleate boiling ratio 
Radiological Concentration Distribution of <sup>134</sup>Cs and <sup>137</sup>Cs Due to a Hypothetical Accident of TRIGA Research Reactor
《World Journal of Nuclear Science and Technology》2021年第3期119-131,共13页Arif Jahan Sarawer M. Ajijul Hoq M. Abu Khaer M. Shafiqul Islam M. Mominur Rahman M. Tareque Chowdhury M. Mizanur Rahman 
The assessment of the radiological concentration of 134Cs and 137Cs owing to hypothetical accident of TRIGA Mark-II research Reactor at AERE, Savar, Bangladesh is presented here in this work. The...
关键词：Concentration Hypothetical Accident Pathway Radiological Protection TRIGA Mark-II 
Development of a PARCS/Serpent model for neutronics analysis of the Dalat nuclear research reactor被引量：5
《Nuclear Science and Techniques》2021年第2期32-44,共13页Viet-Phu Tran Kien-Cuong Nguyen Donny Hartanto Hoai-Nam Tran Vinh Thanh Tran Van-Khanh Hoang Pham Nhu Viet Ha 
the Ministry of Science and Technology of Vietnam(No.DTCB.06/18/VKHKTHN).
Cross-sectional homogenization for full-core calculations of small and complex reactor configurations,such as research reactors,has been recently recognized as an interesting and challenging topic.This paper presents ...
关键词：PARCS Serpent 2 Group constant DNRR 
Conceptual design of irradiation device for silicon neutron transmutation doping around Es-Salam research reactor被引量：3
《Nuclear Science and Techniques》2020年第4期69-78,共10页M.Salhi B.Mohammedi S.Laouar M.Dougdag M.Touiza M.Abbaci M.Moughari 
supported by the Nuclear Research Centre of Birine of Algerian Atomic Energy Commission.
Silicon neutron transmutation doping remains one of the most viable nuclear applications for research reactors.Providing this kind of product involves an irradiation method capable of fulfilling the quality requiremen...
关键词：IRRADIATION DEVICE PROTOTYPE Es-Salam research REACTOR NTD-Si IRRADIATION temperature CFD method 
Development of a polarized ~3He neutron spin filter based on spin exchange optical pumping at China Mianyang Research Reactor被引量：5
《Science China(Physics,Mechanics & Astronomy)》2019年第10期119-122,共4页Song Yan Mo-Fan Zhang Wen-Chuan Guo Wen-Zhao Wang Jian Gong Tian-Jiao Liang Ben-Qiong Liu Mei Peng Shu-Ming Peng GuanAi Sun Xiao-Qing Tu Hai-Yang Yan Jian-Hua Zhang Hao Zheng 
supported by the National Natural Science Foundation of China(Grant Nos.91636103,11675152,and 11875238);the National Key Program for Research and Development(Grant No.2016YFA0401504)
Spin-polarized^3He gas is widely used in many research areas.It is used to search for new spin-dependent interactions beyond the standard model[1,2].It works as a target for electron scattering when studying the spin ...
关键词：POLARIZED latter EXCHANGE 
Calculation of dpa rate in graphite box of Tehran Research Reactor(TRR)被引量：2
《Nuclear Science and Techniques》2019年第6期44-56,共13页Mohamad Amin Amirkhani Mohsen Asadi Asadabad Mostafa Hassanzadeh Seyed Mohammad Mirvakili Ali Mohammadi 
Radiation damage is an important factor that must be considered while designing nuclear facilities and nuclear materials. In this study, radiation damage is investigated in graphite, which is used as a neutron reflect...
关键词：Radiation damage GRAPHITE SPECTER SRIM MCNPX TEHRAN Research Reactor 
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 
Determination of fuel burnup distribution of a research reactor based on measurements at subcritical conditions被引量：1
《Nuclear Science and Techniques》2018年第12期30-38,共9页Quang Binh Do Hoai-Nam Tran Quang Huy Ngo Giang T. T. Phan 
supported by National Foundation for Science and Technology Development(NAFOSTED)of Vietnam under Grant103.04-2016.30
This paper presents the determination of the fuel burnup distribution of the Dalat nuclear research reactor(DNRR) using a method of measurements at subcritical conditions. The method is based on the assumption of line...
关键词：研究反应堆 燃料 分发 测量过程 验证方法 方法论 价值 计算 
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