A new surrogate method for the neutron kinetics calculation of nuclear reactor core transients von Li, Xiaoqi, Zheng, Youqi, Du, Xianan, Xiao, Bowen

Volltext

Adaptive energy group division in the few-group cross-section generation for full spectrum reactor modeling with deterministic method von Yang, Yichen, Zheng, Youqi, Du, Xianan, Wu, Hongchun

Volltext

The applicability study and validation of TULIP code for full energy range spectrum von Chen, Wenjie, Du, Xianan, Wang, Rong, Zheng, Youqi, Wang, Yongping, Wu, Hongchun

Volltext

Reactivity Effect Evaluation of Fast Reactor Based on Angular-Dependent Few-Group Cross Sections Generation von Du, Xianan, Wu, Xuewen, Zheng, Youqi, Wang, Yongping

Volltext

Conceptual design of a MW heat pipe reactor von Wu, Yunqin, Zheng, Youqi, Chen, Qichang, Li, Jinming, Du, Xianan, Wang, Yongping, Tao, Yushan

Volltext

Verification of SARAX code system in the reactor core transient calculation based on the simplified EBR-II benchmark von Jia, Xiaoqian, Zheng, Youqi, Du, Xianna, Wang, Yongping, Chen, Jianda

Volltext

A Stable Condition and Adaptive Diffusion Coefficients for the Coarse-Mesh Finite Difference Method von Xu, Zhitao, Wu, Hongchun, Zheng, Youqi, Zhang, Qian

Volltext

On the equivalence of reaction rate in energy collapsing of fast reactor code SARAX von Xiao, Bowen, Wei, Linfang, Zheng, Youqi, Zhang, Bin, Wu, Hongchun

Volltext

Effect of high-energy neutron source on predicting the proton beam current in the ADS design von Zheng, Youqi, Li, Xunzhao, Wu, Hongchun

Volltext

Burnable Poison Design for Supercritical Water Cooled Reactor With Annular Fuel von Chuanqi, Zhao, Kunpeng, Wang, Liangzhi, Cao, Youqi, Zheng

Volltext

Modeling and flux reconstruction of unstructured geometric reactor von Xiao, Bowen, Zheng, Youqi, Wei, Linfang

Volltext

Stability analysis of CMFD acceleration for the wavelet expansion method of neutron transport equation von Zheng, Youqi, Wu, Hongchun, Cao, Liangzhi

Volltext

Using ex-core detectors and deep neural networks for monitoring power distribution in small space reactors von Wang, Xingfang, Zheng, Youqi, Wang, Xiayu, Li, Xiaoqi

Volltext

SARAX: A new code for fast reactor analysis part II: Verification, validation and uncertainty quantification von Zheng, Youqi, Qiao, Liang, Zhai, Zi'an, Du, Xianan, Xu, Zhitao

Volltext

Reactor design of UPR-1: A MW-level reactor for unmanned underwater vehicle propulsion using low-enriched uranium von Azeem, Muhammad, Zheng, Youqi, Cao, Liangzhi

Volltext

Solution of neutron transport equation using Daubechies’ wavelet expansion in the angular discretization von Cao, Liangzhi, Wu, Hongchun, Zheng, Youqi

Volltext

An IFDF accelerated parallel nodal SN method for XYZ geometry in SARAX code system von Xu, Zhitao, Zheng, Youqi, Wu, Hongchun

Volltext

SARAX: A new code for fast reactor analysis part I: Methods von Zheng, Youqi, Du, Xianan, Xu, Zhitao, Zhou, Shencheng, Liu, Yong, Wan, Chenghui, Xu, Longfei

Volltext

Improvement of few-group cross-section generation in fast reactor analysis system SARAX von Wei, Linfang, Zheng, Youqi, Wu, Hongchun

Volltext

The acceleration of improved Tone's method in advanced reactor lattice neutron spectrum calculation von Du, Xianan, Yang, Yichen, Zheng, Youqi, Wang, Yongping, Wu, Hongchun

Volltext