Zobrazeno 1 - 4
of 4
pro vyhledávání: '"Duy Long Ta"'
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 12, Pp 4722-4730 (2022)
This paper introduces a new point depletion-based source term calculation code named BESNA (Bateman Equation Solver for Nuclear Applications), which is aimed to estimate nuclide inventories and source terms from spent nuclear fuels. The BESNA code em
Externí odkaz:
https://doaj.org/article/fd01dbbbe9dc431fa06ee39280ebd936
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 1, Pp 19-29 (2021)
This paper presents the validation of the MCS code for critical safety analysis with burnup credit for the spent fuel casks. The validation process in this work considers five critical benchmark problem sets, which consist of total 80 critical experi
Externí odkaz:
https://doaj.org/article/87ddfc208f924e888cc5674f2daae1c0
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 1, Pp 19-29 (2021)
This paper presents the validation of the MCS code for critical safety analysis with burnup credit for the spent fuel casks. The validation process in this work considers five critical benchmark problem sets, which consist of total 80 critical experi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::0d9840cd440bc691739c143c423f2063
https://doi.org/10.1016/j.net.2020.06.016
https://doi.org/10.1016/j.net.2020.06.016
Publikováno v:
Nuclear Science and Technology. 6:31-38
This paper presents a computational scheme using MCNP5 and COBRA-EN for coupling neutronics/thermal hydraulics calculation of a VVER-1000 fuel assembly. A master program was written using the PERL script language to build the corresponding inputs for
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::16054bcc7b79545f19fb12dba2ce809a
https://doi.org/10.53747/jnst.v6i2.153
https://doi.org/10.53747/jnst.v6i2.153