Zobrazeno 1 - 3
of 3
pro vyhledávání: '"Chanatip Tippayakul"'
Publikováno v:
Annals of Nuclear Energy. 38:731-741
The MCOR (MCnp-kORigen) code system is a Monte Carlo based depletion system for reference fuel assembly and core calculations. The MCOR code is designed as an interfacing code that provides depletion capability to the LANL Monte Carlo code by couplin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::11d8831e17c2c12f4e2ec3f98d3b963c
https://doi.org/10.1016/j.anucene.2010.12.010
https://doi.org/10.1016/j.anucene.2010.12.010
Publikováno v:
Annals of Nuclear Energy. 35:414-424
The deregulated utility environment and better utilization of fuel assemblies in nuclear power plants has allowed designers to burn fuel assemblies to maximum allowable exposures. Any uncertainties, associated with the technical approach and numerica
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a054e844dbedb66efd6a48fcee6e1d67
https://doi.org/10.1016/j.anucene.2007.07.005
https://doi.org/10.1016/j.anucene.2007.07.005
Publikováno v:
Annals of Nuclear Energy. 35:539-551
A practical fuel management system for the he Pennsylvania State University Breazeale Research Reactor (PSBR) based on the advanced Monte Carlo methodology was developed from the existing fuel management tool in this research. Several modeling improv
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f6bf76b2b5d0d9570130b7f55dde1f59
https://doi.org/10.1016/j.anucene.2007.07.013
https://doi.org/10.1016/j.anucene.2007.07.013