J. Conlin

发表

ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data

R. Q. Wright, D. Brown, D. Cullen, 2018 .

Arnoldi's method of minimized iterations for Monte Carlo criticality calculations

J. Holloway, J. Conlin, 2008 .

Monte Carlo Application of Arnoldi’s Method for Acceleration of Eigenvalue and Fission Source Convergence

J. Holloway, J. Conlin, 2011 .

Neutron-induced damage simulations: Beyond defect production cross-section, displacement per atom and iron-based metrics

P. Griffin, G. Bonny, Y. Iwamoto, 2019, The European Physical Journal Plus.

Explicit modeling of particle fuel for the very-high temperature gas-cooled reactor

Forrest B. Brown, William R. Martin, Jeremy Lloyd Conlin, 2005 .

Determining Plutonium Mass in Spent Fuel with Non-destructive Assay Techniques – NGSI Research Overview and Update on NDA Techniques , Part II

J. G. Richard, S. Thompson, J. White, 2011 .

Release of ENDF/B-VIII.0-Based ACE Data Files

D. Neudecker, J. Conlin, M. White, 2018 .

Verification and Validation of the ENDF/B-VII.1–Based Continuous-Energy Data Tables for MCNP6

A. Kahler, J. Conlin, M. White, 2014 .

Release of Continuous Representation for S(α,β) ACE Data

J. Conlin, D. Parsons, 2014 .

Explicitly restarted Arnoldi's method for Monte Carlo nuclear criticality calculations

J. Conlin, 2009 .

IMPROVED THERMAL SCATTERING DATA PREPARATION

B. Forget, J. Conlin, A. J. Trainer, 2021, EPJ Web of Conferences.

NJOY2016 updates for ENDF/B-VIII.0

A. Kahler, J. Conlin, W. Haeck, 2018 .

A Compact ENDF (ACE) Format Specification

Paul K. Romano, Jeremy Lloyd Conlin, J. Conlin, 2019 .

COMPUTATIONAL BENCHMARK OF THE DOPPLER REACTIVITY DEFECT

Jeremy Lloyd Conlin, J. Conlin, 2007 .

Uncertainty Quantification for New Approaches to Spent Fuel Assay

T. Burr, T. Ulrich, J. Conlin, 2012 .

Whisper: Sensitivity/Uncertainty-Based Computational Methods and Software for Determining Baseline Upper Subcritical Limits

Forrest B. Brown, Jeremy Lloyd Conlin, Jeffrey A. Favorite, 2015 .

Continuous Energy Neutron Cross Section Data Tables Based upon ENDF/B-VII.1

Donald Kent Parsons, Jeremy Lloyd Conlin, Albert C. Kahler, 2013 .

Validation of MCNP6.1 for Criticality Safety of Pu-Metal, -Solution, and -Oxide Systems

Donald Kent Parsons, Jeremy Lloyd Conlin, Jeffrey A. Favorite, 2014 .

Listing of Available ACE Data Tables

A. Kahler, J. Conlin, M. White, 2014 .

Cross Section Data Benchmarking using Automated Criticality Benchmarks in MCNP 6 and Partisn

J. Conlin, D. Parsons, E. Relson, 2012 .

Technical Cross-Cutting Issues for the Next Generation Safeguards Initiative's Spent Fuel Nondestructive Assay Project

Andrea Favalli, Louise G Evans, Leon E. Smith, 2012 .

Proceedings of the Workshop for Applied Nuclear Data: WANDA2020

Jeremy Lloyd Conlin, Patrick Talou, Brian J. Quiter, 2020 .

Pseudo material construct for coupled neutronic-thermal-hydraulic analysis of VHTGR

William R. Martin, Jeremy Lloyd Conlin, Wei Ji, 2005 .

NJOY21: Next generation nuclear data processing capabilities

Jeremy Lloyd Conlin, Austin Paul McCartney, Albert C. Kahler, 2017 .

On Using Code Emulators and Monte Carlo Estimation to Predict Assembly Attributes of Spent Fuel Assemblies for Safeguards Applications

Stephen J Tobin, Jeremy Lloyd Conlin, Tae-Hoon Lee, 2011 .