GALILÉE-1: a validation and processing system for ENDF-6 and GND evaluations

Abstract

GALILÉE-1 is the new validation and processing system for evaluated data, developed at CEA. This system can handle evaluations stored either in the ENDF-6 format or in the new General Nuclear Data (GND) format. It consists of various components respectively dedicated to read/write the evaluated data whatever the format is, to diagnose inconsistencies in the evaluated data and to provide continuous-energy and multigroup data as well as probability tables for transport and depletion codes. All these components are written in C++ language and share the same objects. This paper describes the state of progress of the various parts of the system and gives some illustrations.

Multigroup-like MC resolution of generalised Polynomial Chaos reduced models of the uncertain linear Boltzmann equation (+discussion on hybrid intrusive/non-intrusive uncertainty propagation)

“…They can, for example, be pre-processed (with an accurate integration with respect to dP X ) in a pretreatment code. Note that building physical data from pretreatment codes is common: in neutronics for example, Galilee [55], NJOY [56], CALENDF [57] or PREPRO [58] pre-process evaluated data [59] to make them usable in deterministic or MC resolution codes. From now on, we assume that the pretreated cross-sections Λ s , Λ t together with matrices R, R −1 and v • ∇ x R −1 are available at the beginning of the computations.…”

Development and Verification of Capability for Processing the Generalised Nuclear Database Structure (GNDS) in Nuclear Data Processing Code NECP-Atlas

“…The GNDS format and the ENDF-6 format are both released in some new version libraries, including ENDF-B/VIII.0 and TENDL-2021. Fudge is the first code to parse GNDS format [4] , and most nuclear data, including NJOY [5] , AMPX [6] , FRENDY [7] , GALILEE [8] are developing this function to process GNDS format.…”