Transport equivalent full core neutronics calculations via finite volume method and optimized diffusion parameters

Development and application of TaSNAM 2.0 for advanced pressurized water reactor

(2021) Yuchen Huo et al.   ANNALS OF NUCLEAR ENERGY

Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core

(2020) Linrong Ye et al.   Science and Technology of Nuclear Installations

Analysis of the BEAVRS PWR benchmark using SCALE and PARCS

(2019) Piotr Darnowski et al.   NUKLEONIKA

A Newton solution for the Superhomogenization method: The PJFNK-SPH

(2018) Javier Ortensi et al.   ANNALS OF NUCLEAR ENERGY

Calculation of multiple eigenvalues of the neutron diffusion equation discretized with a parallelized finite volume method

(2018) Alvaro Bernal et al.   PROGRESS IN NUCLEAR ENERGY

Assembly Discontinuity Factors for the Neutron Diffusion Equation discretized with the Finite Volume Method. Application to BWR

(2016) A. Bernal et al.   ANNALS OF NUCLEAR ENERGY

Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code

(2016) Jaakko Leppänen et al.   ANNALS OF NUCLEAR ENERGY

The Serpent Monte Carlo code: Status, development and applications in 2013

(2015) Jaakko Leppänen et al.   ANNALS OF NUCLEAR ENERGY

Solution of the BEAVRS benchmark using the nTRACER direct whole core calculation code

(2015) Min Ryu et al.   JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY

Steady and transient solutions of neutronics problems based on finite volume method (FVM) with a CFD code

(2015) Jian Ge et al.   PROGRESS IN NUCLEAR ENERGY

A stylized three dimensional PWR whole-core benchmark problem with Gadolinium

(2010) Steven Douglass et al.   ANNALS OF NUCLEAR ENERGY