Collision probability methods using rational approximations for space shielding of cross sections in nuclear reactor codes allowing for one level of heterogeneity are first reviewed. A Dancoff factor for a cylindrical HTGR fuel pin with grain structure is then derived. A new simple method for cross section space shielding in a doubly heterogeneous HTGR system using collision probabilities and rational approximations is subsequently presented and calculations based on it are compared with calculations based on more elaborate methods. 39 references. (auth
Two of the primary challenges associated with the neutronic analysis of the Very High Temperature Re...
This thesis describes a tool called TXSAMC (Transport Cross Sections from Applied Monte Carlo) that ...
International audienceThis work summarizes the results of a neutronic study on the HCLL blanket for ...
A new methodology has been developed recently to treat resonance self-shielding in systems for which...
A new methodology has been developed to treat resonance self-shielding in doubly heterogeneous very ...
Motivated by the increased importance of high-fidelity modeling capabilities that can improve the ec...
A method for generating few-group homogenized cross sections using three-dimensional Monte Carlo ass...
Fully ceramic micro-encapsulated (FCM) fuel is a kind of fuel that employs tri-structural isotropic ...
This method, which takes into account the influence of assembly heterogeneity on neutron leakage, is...
A method for generating few-group homogenized cross sections using three-dimensional Monte Carlo ass...
Reactor core safety analysis is a complex problem and needs processed input data and cannot be perfo...
High-speed computational procedures for space radiation shielding have relied on asymptotic expansio...
Equations are presented for the calculation of collision probabilities in cylindrical geometry with ...
A preventing shield for neutrons and gamma rays was designed using alternate layers of water and iro...
So far, the two-dimensional reactor dynamics code TINTE (time-dependent nucleonics and temperatures)...
Two of the primary challenges associated with the neutronic analysis of the Very High Temperature Re...
This thesis describes a tool called TXSAMC (Transport Cross Sections from Applied Monte Carlo) that ...
International audienceThis work summarizes the results of a neutronic study on the HCLL blanket for ...
A new methodology has been developed recently to treat resonance self-shielding in systems for which...
A new methodology has been developed to treat resonance self-shielding in doubly heterogeneous very ...
Motivated by the increased importance of high-fidelity modeling capabilities that can improve the ec...
A method for generating few-group homogenized cross sections using three-dimensional Monte Carlo ass...
Fully ceramic micro-encapsulated (FCM) fuel is a kind of fuel that employs tri-structural isotropic ...
This method, which takes into account the influence of assembly heterogeneity on neutron leakage, is...
A method for generating few-group homogenized cross sections using three-dimensional Monte Carlo ass...
Reactor core safety analysis is a complex problem and needs processed input data and cannot be perfo...
High-speed computational procedures for space radiation shielding have relied on asymptotic expansio...
Equations are presented for the calculation of collision probabilities in cylindrical geometry with ...
A preventing shield for neutrons and gamma rays was designed using alternate layers of water and iro...
So far, the two-dimensional reactor dynamics code TINTE (time-dependent nucleonics and temperatures)...
Two of the primary challenges associated with the neutronic analysis of the Very High Temperature Re...
This thesis describes a tool called TXSAMC (Transport Cross Sections from Applied Monte Carlo) that ...
International audienceThis work summarizes the results of a neutronic study on the HCLL blanket for ...