K. Clarno

发表

VERA Core Simulator Methodology for Pressurized Water Reactor Cycle Depletion

William A. Wieselquist, Brendan Kochunas, Yuxuan Liu, 2017 .

Validation Study of Pin Heat Transfer for UO2 Fuel Based on the IFA-432 Experiments

L. J. Ott, Bobby Philip, Srikanth Allu, 2014 .

Assessment of the analysis capability for core-wide PWR pellet-clad interaction screening of Watts Bar Unit 1

B. Wirth, S. Stimpson, K. Clarno, 2018, Nuclear Engineering and Design.

Modeling and simulation of oxygen transport in high burnup LWR fuel

S. Simunovic, T. Besmann, J. Mcmurray, 2020 .

MPACT Subgroup Self-Shielding Efficiency Improvements

Yuxuan Liu, B. Collins, S. Stimpson, 2016 .

Initial Validation of the AMP Nuclear Fuel Performance Code

G. Ivan Maldonado, Richard C. Martineau, G. I. Maldonado, 2010 .

Neutron Capture Energies for Flux Normalization and Approximate Model for Gamma-Smeared Power

K. Kim, W. Martin, Yuxuan Liu, 2018 .

Depletion, Chemical Reaction and Transport in High Burnup Nuclear Fuel

S. Simunovic, T. Besmann, J. Mcmurray, 2019 .

Coupled thermochemical, isotopic evolution and heat transfer simulations in highly irradiated UO2 nuclear fuel

Kevin T. Clarno, Srdjan Simunovic, Theodore M. Besmann, 2013 .

The Virtual Environment for Reactor Applications (VERA): Design and architecture☆

Roger P. Pawlowski, Benjamin Collins, Kevin T. Clarno, 2016, J. Comput. Phys..

Thermochemically-informed mass transport model for interdiffusion of U and Zr in irradiated U-Pu-Zr fuel with fission products

S. Simunovic, T. Besmann, K. Clarno, 2021 .

Evaluation of Salt Coolants for Reactor Applications

K. T. Clarno, D. Williams, K. Clarno, 2008 .

Standalone BISON Fuel Performance Results for Watts Bar Unit 1, Cycles 1-3

Jeffrey J. Powers, Roger P. Pawlowski, Kevin T. Clarno, 2016 .

High fidelity modeling of Pellet-CLAD interaction using the CASL virtual environment for reactor applications

Brendan Kochunas, Roger P. Pawlowski, Benjamin Collins, 2015 .

Pellet-clad mechanical interaction screening using VERA applied to Watts Bar Unit 1, Cycles 1–3

Jeffrey J. Powers, Roger P. Pawlowski, Kevin T. Clarno, 2018 .

Criticality safety enhancements for SCALE 6.2 and beyond

Bradley T Rearden, Dorothea Wiarda, Cihangir Celik, 2015 .

Sensitivity Analysis of Reactivity Responses Using One-Dimensional Discrete Ordinates and Three-Dimensional Monte Carlo Methods

J. Gehin, K. Clarno, M. Williams, 2006 .

A Validation Study of Pin Heat Transfer for MOX Fuel Based on the IFA-597 Experiments

Bobby Philip, Srikanth Allu, Kevin T. Clarno, 2014 .

A parallel multi-domain solution methodology applied to nonlinear thermal transport problems in nuclear fuel pins

Bobby Philip, Srikanth Allu, Steven P. Hamilton, 2014, J. Comput. Phys..

A new fuel modeling capability, CTFFuel, with a case study on the fuel thermal conductivity degradation

David J. Kropaczek, Robert K. Salko, Aysenur Toptan, 2019, Nuclear Engineering and Design.

Analysis of Anderson Acceleration on a Simplified Neutronics/Thermal Hydraulics System

Roger P. Pawlowski, Carl Tim Kelley, Kevin T. Clarno, 2015 .

Vera core simulator methodology for PWR cycle depletion

William A. Wieselquist, Thomas J. Downar, Brendan Kochunas, 2015 .

MODULAR ORIGEN-S FOR MULTI-PHYSICS CODE SYSTEMS

Ian C Gauld, Kevin T. Clarno, Gokhan Yesilyurt, 2011 .

An assessment of coupling algorithms for nuclear reactor core physics simulations

Roger P. Pawlowski, C. T. Kelley, Alex Toth, 2016, J. Comput. Phys..

Denovo: A New Three-Dimensional Parallel Discrete Ordinates Code in SCALE

Kevin T. Clarno, Rachel N. Slaybaugh, Thomas M. Evans, 2010 .

An approach for coupled-code multiphysics core simulations from a common input

Rodney Cannon Schmidt, Roger P. Pawlowski, Kevin T. Clarno, 2015 .

Benchmarking of software and methods for use in transient multidimensional fuel performance with spatial reactor kinetics

B. Philip, K. Clarno, S. Hamilton, 2012 .

Integrated Radiation Transport and Nuclear Fuel Performance for Assembly-Level Simulations

Bobby Philip, Srikanth Allu, Steven P. Hamilton, 2012 .

C++ Coding Standards for the AMP Project

Thomas M. Evans, Kevin T. Clarno, K. Clarno, 2009 .

COUPLED NEUTRONICS AND THERMAL-HYDRAULIC SOLUTION OF A FULL-CORE PWR USING VERA-CS

Rodney Cannon Schmidt, Robert K. Salko, Thomas M. Evans, 2014 .

A New Semi-Implicit Direct Kinetics Method with Analytical Representation of Delayed Neutrons

K. Clarno, S. Hamilton, J. Banfield, 2012 .

Mathematical Framework for Coupling the AMP and Denovo Codes

K. Clarno, S. Hamilton, 2011 .

MPACT Theory Manual, Version 2.2.0

Mitchell T. H. Young, E. Larsen, W. Martin, 2016 .

Integration of the NESTLE Core Simulator with SCALE

G. I. Maldonado, Kevin T. Clarno, Matthew Anderson Jessee, 2009 .

Assessment of Pellet-Clad Interaction Indicators in Watts Bar Unit 1, Cycles 1-3 Using VERA

Jeffrey J. Powers, Ryan N. Bratton, Roger P. Pawlowski, 2016 .

VERA Benchmarking Results for Watts Bar Nuclear Plant Unit 1 Cycles 1-12

William A. Wieselquist, Thomas J. Downar, Jeffrey J. Powers, 2016 .

Modeling Input Space for Testing Scientific Computational Software: A Case Study

Jesse H. Poore, Kevin T. Clarno, Sergiy A. Vilkomir, 2008, ICCS.

Foundational development of an advanced nuclear reactor integrated safety code.

Rodney Cannon Schmidt, William F. Spotz, Richard J. Pryor, 2010 .

CASL Milestone Report L 3 : PHI . CMD . P 8 . 01 Evaluation of Coupling Approaches

M. Berrill, R. Pawlowski, K. Clarno, 2014 .

Capturing the Effects of Unlike Neighbors in Single-Assembly Calculations

M. Adams, K. Clarno, 2005 .

A Transport Acceleration Scheme for Multigroup Discrete Ordinates with Upscattering

Jim E. Morel, Kevin T. Clarno, Thomas M. Evans, 2010 .