期刊


ISSN2332-8983
刊名Journal of nuclear engineering and radiation science
参考译名核工程和辐射科学杂志
收藏年代2016～2023



全部

2016 2017 2018 2019 2020 2021
2022 2023

2023, vol.9, no.1 2023, vol.9, no.2 2023, vol.9, no.3

题名作者出版年年卷期
Solution of Neutron Diffusion Problems by Discontinuous Galerkin Finite Element Method With Consideration of Discontinuity FactorsLi, Wanai; Gong, Helin; Zhang, Chunyu20232023, vol.9, no.3
Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated MicrospheresNoah, Olugbenga O.; Slabber, Johan F.; Meyer, Josua P.20232023, vol.9, no.3
Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power DistributionLindley, Ben; Velarde, Francisco Alvarez; Baker, Una; Bodi, Janos; Cosgrove, Paul; Charles, Alan; Fiorina, Carlo; Fridman, Emil; Krepel, Jiri; Lavarenne, Jean; Mikityuk, Konstantin; Nikitin, Evgeny; Ponomarev, Alexander; Radman, Stefan; Shwageraus, Eugene; Tollit, Brendan20232023, vol.9, no.3
Long-Term Performance of Semimetallic GasketsBouzid, Abdel-Hakim; Das, Shubhra Kanti20232023, vol.9, no.3
Estimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal ReactorWang, Xiaolin; Shi, Youqing; Bickel, Grant; Robert, DeAbreu20232023, vol.9, no.3
Development and Calibration of an Indigenous Spectroscopic System for Radiation Portal Monitor ApplicationPandey, Arun Kumar; Wahi, Pankaj; Sinha, Niraj; Munshi, Prabhat; Fnu, Akanchha; Bhadouria, Vikesh Singh20232023, vol.9, no.3
Burnup Characteristics of Transuranic Fuel With Burnable Poison in Dual Cooled Annular Rod of VVER-1000Ahmed, Md. Tanvir; Sahadath, Md. Hossain; Islam, Md. Ashraful20232023, vol.9, no.3
A Novel Algorithm for Fast Measurement of Material Density in Symmetrical Objects Using X-Ray RadiographySinha, Vaibhav; Strantz, Frank Angelo; Lee, Hyoung Koo20232023, vol.9, no.3
Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast ReactorKikuchi, Norihiro; Imai, Yasutomo; Yoshikawa, Ryuji; Doda, Norihiro; Tanaka, Masaaki20232023, vol.9, no.3
Benchmarking Fast Neutrons Leakage Spectrum From Copper Block With Cf-252 Source in CenterCzakoj, Tomas; Kost'al, Michal; Schulc, Martin; Rypar, Vojtech; Novak, Evzen; Losa, Evzen20232023, vol.9, no.3
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