D. Verrier

发表

Characterization and extrapolation of a conceptual experimental accelerator driven system

A. Billebaud, R. Brissot, E. Liatard, 2003 .

THE ERANOS CODE AND DATA SYSTEM FOR FAST REACTOR NEUTRONIC ANALYSES

Gérald Rimpault, Danièle Plisson, Jean Tommasi, 2002 .

Improved performances of the fast reactor calculational system ERANOS-ERALIB1 due to improved a priori nuclear data and consideration of additional specific integral data 1 1 Sponsored by BNFL.

G. Rimpault, R. Jacqmin, D. Verrier, 2003 .

Codes and methods improvements for safety assessment and LTO: varied approaches

D. Verrier, Albannie Cagnac, Vladislav Pištora, 2023, EPJ Nuclear Sciences & Technologies.

France–Japan synthesis concept on sodium-cooled fast reactor review of a joint collaborative work

Masaaki Tanaka, K. Koyama, S. Ohki, 2021, EPJ Nuclear Sciences & Technologies.

The ASTRID core at the midterm of the conceptual design phase (AVP2)

Denis Verrier, Thierry Beck, Christophe Venard, 2015 .

Core and safety design for France–Japan common concept on sodium-cooled fast reactor

S. Ohki, L. Costes, H. Yamano, 2022, EPJ Nuclear Sciences & Technologies.

STATUS OF THE ASTRID CORE AT THE END OF THE PRE-CONCEPTUAL DESIGN PHASE 1

N. Devictor, Laurent Martin, Chenaud, 2013 .

Pre-conceptual design study of ASTRID core

Bruno Fontaine, Nicolas Devictor, Denis Verrier, 2012 .

In vessel detection of delayed neutron emitters from clad failure in sodium cooled nuclear reactors: An estimation of the signal

F. Jadot, D. Verrier, C. Jammes, 2014 .