Home / Publications / Journals / Nuclear Science and Engineering / Volume 197 / Number 12

Volume 197

Number 12

Table of Contents
Foreword: Special issue featuring papers from the SAMOSAFER Young Molten Salt Reactor Conference(Sandra Dulla, Stefano Lorenzi)
Correction

Investigation of Normal and Abnormal States of the Molten Salt Experimental Loop Using Computational Fluid Dynamics

Michal Cihlář, Pavel Zácha, Jan Uhlíř, Martin Mareček, Václav Dostál, Jan Prehradný

Nuclear Science and Engineering / Volume 197 / Number 12 / December 2023 / Pages 2961-2976

YMSR Paper / dx.doi.org/10.1080/00295639.2023.2189549

Nuclear Data Uncertainty Propagation for the Molten Salt Fast Reactor Design

Nicolo’ Abrate, Alex Aimetta, Sandra Dulla, Nicola Pedroni

Nuclear Science and Engineering / Volume 197 / Number 12 / December 2023 / Pages 2977-2999

YMSR Paper / dx.doi.org/10.1080/00295639.2023.2190861

A New Calculation Strategy for Molten Salt Reactor Neutronic–Thermal-Hydraulic Analysis Implemented with APOLLO3® and TRUST/TrioCFD

Nathan Greiner, François Madiot, Yannick Gorsse, Cyril Patricot, Guillaume Campioni

Nuclear Science and Engineering / Volume 197 / Number 12 / December 2023 / Pages 3000-3021

YMSR Paper / dx.doi.org/10.1080/00295639.2023.2197043

Modeling Flow Blockage Accident in Graphite-Moderated Molten Salt Reactors

Paolo Bianchini, Manuele Aufiero, Francesco Di Lecce

Nuclear Science and Engineering / Volume 197 / Number 12 / December 2023 / Pages 3022-3034

YMSR Paper / dx.doi.org/10.1080/00295639.2023.2219818

Thermodynamic Assessment of the NaCl-CrCl₂, NaCl-CrCl₃, and FeCl₂-CrCl₂ Pseudo-Binary Systems for Describing the Corrosion Chemistry Between Molten Salt Fuel and Steel

V. Tiwari, T. F. Abbink, J. A. Ocádiz Flores, J. L. Flèche, C. Gueneau, S. Chatain, A. L. Smith, J. Martinet, C. Venard

Nuclear Science and Engineering / Volume 197 / Number 12 / December 2023 / Pages 3035-3057

YMSR Paper / dx.doi.org/10.1080/00295639.2023.2223745

Numerical Modeling and Simulation of Melting Phenomena for Freeze Valve Analysis in Molten Salt Reactors

Davide Tartaglia, Antonio Cammi, Carolina Introini, Stefano Lorenzi

Nuclear Science and Engineering / Volume 197 / Number 12 / December 2023 / Pages 3058-3081

YMSR Paper / dx.doi.org/10.1080/00295639.2023.2229576

Pumping Options for Versatile Test Reactor Molten Lead In-Pile Test Cartridge

Mohamed S. El-Genk, Timothy M. Schriener, Ragai Altamimi, Andrew Hahn

Nuclear Science and Engineering / Volume 197 / Number 12 / December 2023 / Pages 3082-3109

Regular Research Article / dx.doi.org/10.1080/00295639.2023.2190723

Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of ²⁴¹Pu

H. Naik, R. J. Singh, S. P. Dange, W. Jang

Nuclear Science and Engineering / Volume 197 / Number 12 / December 2023 / Pages 3110-3124

Regular Research Article / dx.doi.org/10.1080/00295639.2023.2190725

Neutron Measurements and Monte Carlo Simulations of Spent Nuclear Fuel in Dry Cask Storage Using a New Remote Monitoring System Prototype

Jeremy W. King, Craig M. Marianno, Sunil S. Chirayath

Nuclear Science and Engineering / Volume 197 / Number 12 / December 2023 / Pages 3125-3137

Regular Research Article / dx.doi.org/10.1080/00295639.2023.2191579

Solving the Neutron Transport Equation for Microreactor Modeling Using Unstructured Meshes and Exascale Computing Architectures

William C. Dawn, Scott Palmtag

Nuclear Science and Engineering / Volume 197 / Number 12 / December 2023 / Pages 3138-3159

Regular Research Article / dx.doi.org/10.1080/00295639.2023.2189510

Effect of Oxygen Ion Irradiation on Nb-1Zr-0.1C Alloy Characterized Using X-Ray Diffraction Line Profile Analysis

Argha Dutta, Apu Sarkar, Sandip Bysakh, Uttiyoarnab Saha, N. Gayathri, Santu Dey, P. Mukherjee

Nuclear Science and Engineering / Volume 197 / Number 12 / December 2023 / Pages 3160-3174

Regular Research Article / dx.doi.org/10.1080/00295639.2023.2191580

Development of Multiphysics Framework to Analyze Dynamic Gap Heat Transfer and Cross-Flow Effect on Partial Rod Ejection Accident

Awais Zahur, Muhammad Rizwan Ali, Deokjung Lee

Nuclear Science and Engineering / Volume 197 / Number 12 / December 2023 / Pages 3175-3192

Technical Note / dx.doi.org/10.1080/00295639.2023.2189888