Modelling and neutronic calculation of vvr-m2 fuel assembly and Dalat nuclear research reactor using tripoli4 code and apollo2 code /

অনুরূপ উপাদানগুলি

• Neutronics analysis of Dalat nuclear research reactor by MVP/GMVP code /
  অনুযায়ী: Nguyễn Kiên Cường.
• Assessment of CFD codes used in nuclear reactor safety simulations /
  অনুযায়ী: Smith, B.L..
• Irradiation test of mox fuel in the halden reactor and the analysis of measured data with the fuel performance code cosmos /
  অনুযায়ী: Wiesenack, Wolfgang.
• Characterization of neutron spectrum parameters at irradiation channels for neutron activation analysis after full conversion of the Dalat nuclear research reactor to low …
  অনুযায়ী: Trịnh, Thị Tú Anh
  প্রকাশিত: (2023)
• Characteristics of filtered neutron beam energy spectra at Dalat Reactor
  অনুযায়ী: Tran, Tuan Anh, অন্যান্য
  প্রকাশিত: (2023)