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International Journal of Nuclear Energy Science and Technology

International Journal of Nuclear Energy Science and Technology

EI

中文名称：国际核能科学技术杂志

ISSN：1741-6361
出版周期：Quarterly

发文量：351

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1.A multi-group extended linear discontinuous method for fixed-source discrete ordinates problems in slab geometry

机译：平板几何中固定源离散坐标问题的多组扩展线性不连续方法
- 作者：Iram B. Rivas-Ortiz;Dany S. Dominguez;Carlos R. García Hernández;Susana M. Iglesias
- 期刊名称：《International Journal of Nuclear Energy Science and Technology》 | 2019年第1期
- multi-group transport problems;
- discrete ordinate formulation;
- fixed-source problems;
- linear discontinuous;
2.Semi-empirical formula for photon energy absorption buildup factors of elements and compounds

机译：元素和化合物的光子能量吸收累积因子的半经验公式
- 作者：H.C. Manjunatha;L. Seenappa;K.N. Sridhar
- 期刊名称：《International Journal of Nuclear Energy Science and Technology》 | 2019年第1期
- fast reactors;
- sodium-cooled reactor;
- breed and burn;
- metallic fuel;
- ASTRID;
3.Nuclear power plants in India: achieving clean and green energy

机译：印度的核电站：实现清洁和绿色能源
- 作者：Usha Shukla;Rishabh Bajpai
- 期刊名称：《International Journal of Nuclear Energy Science and Technology》 | 2019年第1期
- nuclear power plant;
- nuclear energy;
- India's nuclear power program;
- India's nuclear energy limitations;
4.A preliminary comparative study between oxide and metallic fuelled ASTRID-like reactor under a B&B strategy

机译：B＆B策略下氧化物和金属燃料的ASTRID样反应堆之间的初步比较研究
- 作者：Juan-Luis François;Elías-Yammir García-Cervantes;Cecilia Martín-del-Campo
- 期刊名称：《International Journal of Nuclear Energy Science and Technology》 | 2019年第1期
- fast reactors;
- sodium-cooled reactor;
- breed and burn;
- metallic fuel;
- ASTRID;
5.Feasibility study for production of ~(99)Mo and ~(99m)Tc by the neutron activation of ~(98)Mo in the MNSR reactor

机译：在MNSR反应堆中通过中子活化〜（98）Mo产生〜（99）Mo和〜（99m）Tc的可行性研究
- 作者：Kassem Khattab;George Saba
- 期刊名称：《International Journal of Nuclear Energy Science and Technology》 | 2019年第1期
- Mo production;
- neutron flux;
- irradiation time;
- specific activity;
- MNSR;
- miniature neutron source reactor;
6.Fuel loading, criticality and control rod worth calculations of the Triga Mark III reactor using Serpent and MCNP

机译：使用蛇形和MCNP的Triga Mark III反应堆的燃料负载，临界度和控制棒价值计算
- 作者：Jaime Hernandez-Galeana;Juan Galicia-Aragon;Armando Gomez-Torres;Carlos Filio-Lopez
- 期刊名称：《International Journal of Nuclear Energy Science and Technology》 | 2019年第1期
- Triga Mark III reactor;
- Monte Carlo methods;
- criticality and fuel loading;
- control rod worth;
7.Calculation for gamma ray buildup factor for aluminium, graphite and lead

机译：铝，石墨和铅的伽马射线累积因子的计算
- 作者：Hiwa Mohammad Qadr
- 期刊名称：《International Journal of Nuclear Energy Science and Technology》 | 2019年第1期
- sodium iodide detector;
- gamma attenuation;
- buildup factor;
- good geometry;
- graphite;

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