Results 141 to 150 of about 25,004 (172)

Characteristics of Irradiation Production of Radioisotope in an Ultra-High Flux Research Reactor

Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology
Radioisotopes are widely used in industry, agriculture, healthcare, and other fields, they are important basic materials for nuclear science and technology.
Jian Li, Wei Xu, Jing Zhao, Zhihong Liu, Ding She, Heng Xie, Lei Shi   +6 more
semanticscholar   +1 more source

Development Progress of Neutronics and Thermal-Hydraulics Calculation Program NECP-Panda for Pebble-Bed High Temperature Gas-Cooled Reactor

Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology
The Pebble-Bed High Temperature Gas-cooled Reactor (PB-HTGR) is considered one of the most promising next-generation nuclear energy systems. Due to its unique operational characteristics and neutron spectrum, PB-HTGR presents many challenges and issues
Yuxuan Wu, Yongping Wang, Shuai Qin, Liangzhi Cao, Hongchun Wu, Yong Luo   +5 more
semanticscholar   +1 more source

Neutronics Study and Conceptual Design for Small Sodium-Cooled-Fast-Reactor With Annular Fuel

Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology
This paper presents a conceptual design for a small Sodium-Cooled-Fast-Reactor core with annular fuel through the analysis of neutronic character, various power strategies and control rod control system.
Bin Ye, Ayodeji A. Ala
semanticscholar   +1 more source

Study on Neutronics Properties of Zirconium Hydride Moderator in Reactor

Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology
The metal hydride ZrH1.6 has a high hydrogen atom density, equivalent to that of liquid water. Compared to other hydrides (such as H2O and organic compounds), particularly at high temperatures, ZrH1.6 exhibits good strength and stability.
Shixin Lin, Youqi Zheng
semanticscholar   +1 more source

ELEMENTS OF NEUTRON TRANSPORT THEORY

Nuclear Reactor Physics and Engineering, 2020

semanticscholar   +1 more source

Three-Dimensional Refined Burnup Calculation of Helical-Cruciform Nuclear Fuel

Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology
The Helical Cruciform Nuclear fuel (HCF) is an Advanced Technology of Fuel (ATF), a low-enriched uranium fuel has been proposed by Lightbridge. The innovation of HCF lies in the use of metallic materials and the geometry is a petal-shaped cross-section
Qianni Duan, Li Wei, Junmei Wu
semanticscholar   +1 more source

A Nonlocal Meso-Scale Damage Model for Nuclear Graphite

Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology
Due to its excellent nuclear physical properties and high-temperature resistance, graphite is widely used in many areas of the nuclear industry.
Yan Ma, Yue Qian, Yuchen Hao, Musen Lin, Yue Li, Jinhua Wang, Haitao Wang   +6 more
semanticscholar   +1 more source

Some nonlinear problems of nuclear reactor theory

, 1964
O. B. Moskalev
semanticscholar   +1 more source

Coupling of Time-Dependent Neutron Transport Theory with the Thermal Hydraulics Code ATHLET and Application to the Research Reactor FRM-II

, 2003
A. Pautz, A. Birkhofer
semanticscholar   +1 more source

An integral equation arising in two group neutron transport theory

, 2003
J. Cassell, M M R Williams
semanticscholar   +1 more source