Lattice physics computations

D Knott, A Yamamoto - Handbook of nuclear engineering, 2010 - infona.pl
This chapter presents a detailed description of the elements that comprise a lattice physics
code. Lattice physics codes are used to generate cross section data for nodal codes, where …

Resonance treatment based on ultra-fine-group spectrum calculation in the AEGIS code

N Sugimura, A Yamamoto - Journal of nuclear science and …, 2007 - Taylor & Francis
The resonance calculation method using the ultra-fine-group spectrum calculations in the
AEGIS code is explained in detail. By a simple benchmark problem, it is verified that the …

GENESIS: a three-dimensional heterogeneous transport solver based on the Legendre polynomial expansion of angular flux method

A Yamamoto, A Giho, Y Kato, T Endo - Nuclear Science and …, 2017 - Taylor & Francis
A heterogeneous transport solver in three-dimensional (3-D) geometry, GENESIS, is
developed incorporating recent developments in the method of characteristics (MOC) in 3-D …

The enhancements and testing for the MCNPX 2.6. 0 depletion capability

ML Fensin, JS Hendricks, S Anghaie - Nuclear technology, 2010 - Taylor & Francis
Monte Carlo–linked depletion methods have gained recent interest due to the ability to
model complex three-dimensional geometries using continuous-energy cross sections. The …

Simplified treatments of anisotropic scattering in LWR core calculations

A Yamamoto, Y Kitamura, Y Yamane - Journal of nuclear science …, 2008 - Taylor & Francis
The validity of various simplified treatments of anisotropic scattering is investigated in typical
LWR configurations that simulate PWR, BWR, and APWR. In addition to the explicit …

Auto MOC—A 2D neutron transport code for arbitrary geometry based on the method of characteristics and customization of AutoCAD

Q Chen, H Wu, L Cao - Nuclear Engineering and Design, 2008 - Elsevier
A new 2D neutron transport code AutoMOC for arbitrary geometry has been developed. This
code is based on the method of characteristics (MOCs) and the customization of AutoCAD …

Evaluation of background cross section for heterogeneous and complicated geometry by the enhanced neutron current method

A Yamamoto - Journal of nuclear science and technology, 2008 - Taylor & Francis
A new approach for evaluating the background cross section for heterogeneous and
complicated geometry (the enhanced neutron current method) is presented. The present …

[HTML][HTML] Evaluation of Transport–Burnup Coupling Strategy in Double-Heterogeneity Problem

Y Zhang, Q Zhang, Y Zou, B Zhou, R Yan, G Zhu, J Guo… - Energies, 2024 - mdpi.com
The simulation of fuel composition requires coupled calculations of neutron transport and
burnup. It is generally assumed that the neutron flux density and cross-sections remain …

AEGIS: an advanced lattice physics code for light water reactor analyses

A Yamamoto, T Endo, M Tabuchi… - Nuclear Engineering …, 2010 - koreascience.kr
AEGIS is a lattice physics code incorporating the latest advances in lattice physics
computation, innovative calculation models and efficient numerical algorithms and is mainly …

[图书][B] Development of the MCNPX depletion capability: A Monte Carlo linked depletion method that automates the coupling between MCNPX and CINDER90 for high …

ML Fensin - 2008 - search.proquest.com
Monte Carlo-linked depletion methods have gained recent interest due to the ability to more
accurately model complex 3-dimesional geometries and better track the evolution of …