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 …

The new version of the Japanese evaluated nuclear data library, JENDL-5, was released in
December 2021. This paper demonstrates the validation of JENDL-5 for fission reactor …

A renaissance in fast reactor research and development and the rapid development of
computing technologies have encouraged improvements in fast reactor modeling and …

Benchmark testing for the newly developed Japanese evaluated nuclear data library JENDL-
4.0 is carried out by using a huge amount of integral data. Benchmark calculations are …

Computing effective eigenvalues for neutron transport often requires a fine numerical
resolution. The main challenge of such computations is the high memory effort of classical …

How to generate the precise broad group cross section is important for the fast reactor
design. In this study, a fast reactor multi-group cross-section generation code MGGC2. 0 are …

A set of cross section libraries for the isotope generation and depletion calculation code
ORIGEN2 was produced by using recent nuclear data based on JENDL-4.0 which was …

High accuracy neutronic simulations are required for the development of Generation-IV
sodium cooled fast reactors (SFR). This paper therefore focuses on the development and …

A comprehensive and versatile reactor analysis code system, MARBLE, has been
developed. MARBLE is designed as a software development framework for reactor analysis …

In order to achieve highly accurate resonance calculations with short computation time, a
new ultra-fine-group resonance calculation method is developed. The ultra-fine-group …