T. A. Taiwo

发表

Evaluation of the DRAGON code for VHTR design analysis.

T. A. Taiwo, T. K. Kim, 2006 .

Neutronic assessment of stringer fuel assembly design for liquid-salt-cooledvery high temperature reactor (LS-VHTR).

T. A. Taiwo, F. J. Szakaly, T. K. Kim, 2006 .

Evaluation of a consistent point-kinetics model for the TMI-1 MSLB benchmark problem

James E. Cahalan, F. E. Dunn, T. A. Taiwo, 1999 .

Preliminary Neutronics Design Studies of a Lead Cooled, Small Modular Reactor

T. A. Taiwo, Won Sik Yang, M. A. Smith, 2004 .

Results for the C5G7 benchmark problem using a subelement option of the varitional nodal method.

G. Palmiotti, Elmer E Lewis, T. A. Taiwo, 2002 .

APPLICATION OF NODAL EQUIVALENCE PARAMETERS TO PRISMATIC VHTR CORE ANALYSIS

T. A. Taiwo, C. H. Lee, Z. Zhong, 2007 .

Verification of physics predictions for GT/AD-MHR core designs.

P. J. Finck, C. G. Stenberg, T. A. Taiwo, 2000 .

Macroscopic cross section generation and application for coupled spatial kinetics and thermal hydraulics analysis with SAS-DIF3DK

J. E. Cahalan, R. B. Turski, T. A. Taiwo, 1997 .

Th/U-233 multi-recycle in PWRs.

T. K. Kim, T. A. Taiwo, Di Yun, 2010 .

CODE TDMCC FOR MONTE CARLO COMPUTATIONS OF SPATIAL REACTOR CORE KINETICS

T. A. Taiwo, V. A. Tarasov, S. Cass Avenue, 2005 .

Nuclear Data Needs for Generation IV Nuclear Energy Systems - Summary of U.S. Workshop

T. A. Taiwo, H. S. Khalil, 2006 .

Preliminary assessment of existing experimental data for validation ofreactor physics codes and data for NGNP design and analysis.

J. B. Briggs, W. S. Park, T. A. Taiwo, 2005 .

AN INVESTIGATION OF AN OPTIMAL RANGE OF SUBCRITICALITY FOR ACCELERATOR-DRIVEN SYSTEMS

R. N. Hill, T. A. Taiwo, Won Sik Yang, 2002 .

The Numerical Nuclear Reactor for High Fidelity Integrated Simulation of Neutronic, Thermal-Hydraulic and Thermo Mechanical Phenomena - Project Overview

Thomas J. Downar, Chang Hyo Kim, Han Gyu Joo, 2004 .

Summary of Generation-IV transmutation impacts.

R. N. Hill, T. A. Taiwo, 2005 .

Performance testing of SAS-DIF3DK using the OECD/NEA PWR MSLB benchmark.

J. E. Cahalan, T. A. Taiwo, 2001 .

Enhancement of REBUS-3/DIF3D for Whole-Core Neutronic Analysis of Prismatic Very High Temperature Reactor (VHTR)

Z. Zhong, T. A. Taiwo, Won Sik Yang, 2006 .

Initial verification and validation tests of the MC2-3 ENDF/B-VII.l library for fast reactor systems

Won Sik Yang, T. A. Taiwo, Changho Lee, 2014 .

Implementation of nodal equivalence parameters in DIF3D-VARIANT for core analysis of prismatic Very High Temperature Reactor (VHTR).

T. A. Taiwo, W. S. Yang, H. K. Joo, 2007 .

Performance evaluation of two-stage fuel cycle from SFR to PWR

E. A. Hoffman, T. A. Taiwo, T. K. Kim, 2013 .

Fuel cycle analysis of once-through nuclear systems.

T. A. Taiwo, T. K. Kim, T. Taiwo, 2010 .

A comparison of equilibrium and non-equilibrium cycle methods for Na-cooled ATW system.

R. N. Hill, T. A. Taiwo, Y. Kim, 2002 .

Analysis of the NEACRP PWR rod ejection benchmark problems with DIF3D-K

M. H. Kim, T. A. Taiwo, H. S. Khalil, 1994 .

Status of Reactor Analysis Methods and Codes in the U.S.A

T. A. Taiwo, W. S. Yang, 2004 .

Time-step selection considerations in the analysis of reactor transients with DIF3D-K

J. E. Cahalan, T. A. Taiwo, H. S. Khalil, 1993 .

A particle-bed gas cooled fast reactor core design for waste minimization.

T. A. Taiwo, Won Sik Yang, M. Fatone, 2002 .

Status of reactor physics activities on cross section generation andfunctionalization for the prismatic very high temperature reator, anddevelopment of spatially-heterogenerous codes.

G. Palmiotti, T. A. Taiwo, Won Sik Yang, 2006 .

Preliminary neutronic studies for the liquid-salt-cooled very hightemperature reactor (LS-VHTR).

T. A. Taiwo, T. K. Kim, W. S. Yang, 2005 .

Simulation of TREAT Cores Using High-fidelity Neutronics Code PROTEUS

T. A. Taiwo, H. M. Connaway, T. Taiwo, 2017 .

Physics studies of preliminary gas-cooled fast reactor designs.

E. A. Hoffman, T. A. Taiwo, 2003 .

Development of a coupled dynamics code with transport theory capability and application to accelerator driven systems transients

James E. Cahalan, Giuseppe Palmiotti, T. A. Taiwo, 2000 .

TDMCC Monte-Carlo package coupled with STAR-CD thermal-hydraulics code

V. V. Bakanov, A. K. Zhitnik, V. P. Fomin, 2004 .

Sensitivity study of design parameters for liquid-salt-cooled VHTR

G. Palmiotti, T. A. Taiwo, Won Sik Yang, 2005 .

A feasibility study of reactor-based deep-burn concepts.

T. A. Taiwo, Won Sik Yang, T. K. Kim, 2005 .

Transmutation impacts of generation-IV nuclear energy systems

T. A. Taiwo, R. N. Hill, 2006 .

Whole-core depletion studies in support of fuel specification for the nextgeneration nuclear plant (NGNP) core.

T. A. Taiwo, H. S. Khalil, T. K. Kim, 2004 .

Evaluation of high temperature gas-cooled reactor physics experiments as VHTR benchmark problems.

J. B. Briggs, David W. Nigg, T. A. Taiwo, 2005 .

The TDMCC Monte Carlo capability for spatial kinetics calculations of reactor cores

A. K. Zhitnik, V. M. Povyshev, I. E. Ponomarev, 2004 .

Benchmark Comparisons of Deterministic and Monte Carlo Codes for a PWR Heterogeneous Assembly Design

T. A. Taiwo, J. A. Stillman, C. Chabert, 2004 .

Space-angle approximations in the variational nodal method.

Giuseppe Palmiotti, Elmer E Lewis, T. A. Taiwo, 1999 .

Preliminary assessment of lattice physics capabilities for VHTR analysis.

T. A. Taiwo, Won Sik Yang, M. A. Smith, 2004 .

Feasibility Study of a Proliferation Resistant Fuel Cycle for LWR-Based Transmutation of Transuranics

M. Salvatores, T. A. Taiwo, T. K. Kim, 2002 .

A Finite Subelement Generalization of the Variational Nodal Method

G. Palmiotti, T. A. Taiwo, N. Tsoulfanidis, 2003 .