Open AccessDevelopment of Terrenus: A Multiphysics Code for Spent Nuclear Fuel Canister Criticality Analysis
Author(s) -
Stylianos Chatzidakis,
Gregory Davidson,
S. R. Johnson
Publication year - 2019
Publication title -
transactions of the american nuclear society - volume 123
Language(s) - English
Resource type - Conference proceedings
DOI - 10.13182/t31155
Subject(s) - criticality , multiphysics , nuclear engineering , spent nuclear fuel , nuclear criticality safety , mox fuel , code (set theory) , nuclear fuel , computer science , environmental science , plutonium , nuclear physics , physics , engineering , finite element method , programming language , structural engineering , set (abstract data type)
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