J. J. Sienicki

发表

Modeling and numerical methods of TWOPOOL. [LMFBR]

P. B. Abramson, J. J. Sienicki, 1978 .

J. J. Sienicki, A. Moisseytsev, J. A. Bennett, 2017 .

PACER -- A fast running computer code for the calculation of short-term containment/confinement loads following coolant boundary failure. Volume 1: Code models and correlations

J. J. Sienicki, 1997 .

Numerical mixing errors in Eulerian calculations of coupled thermohydrodynamic motions. [LMFBR]

P. B. Abramson, J. J. Sienicki, J. Sienicki, 1979 .

Simulation of IST Turbomachinery Power-Neutral Tests with the ANL Plant Dynamics Code

J. J. Sienicki, A. Moisseytsev, 2016 .

Open upper plenum of LOF thermal hydraulics and inherent control rod insertion

J. J. Sienicki, 1986 .

Response of Soviet-designed VVER-440 steam generator vessel to pressurization

J. M. Kennedy, J. J. Sienicki, 1989 .

Analysis of supercritical CO{sub 2} cycle control strategies and dynamic response for Generation IV Reactors.

J. J. Sienicki, A. Moisseytsev, 2011 .

Supercritical carbon dioxide cycle control analysis.

J. J. Sienicki, A. Moisseytsev, 2011 .

Extension of the supercritical carbon dioxide brayton cycle to low reactor power operation: investigations using the coupled anl plant dynamics code-SAS4A/SASSYS-1 liquid metal reactor code system.

J. J. Sienicki, A. Moisseytsev, 2012 .

Pressure loadings of Soviet-designed VVER (Water-Cooled, Water-Moderated Energy Reactor) reactor release mitigation structures from large-break LOCAs

J. J. Sienicki, W. C. Horak, 1989 .

PACER -- A fast running computer code for the calculation of short-term containment/confinement loads following coolant boundary failure. Volume 2: User information

J. J. Sienicki, 1997 .

Supercritical CO2Brayton Cycle Control Strategy for Autonomous Liquid Metal-Cooled Reactors

J. J. Sienicki, A. Moisseytsev, 2004 .

Physics of reactor safety. Quarterly report, October--December 1976. [LMFBR]

P. A. Pizzica, P. B. Abramson, J. J. Sienicki, 1977 .

13 – Nuclear power

J. J. Sienicki, A. Moisseytsev, A. Moisseytsev, 2017 .

Development of the ANL plant dynamics code and control strategies for the supercritical carbon dioxide Brayton cycle and code validation with data from the Sandia small-scale supercritical carbon dioxide Brayton cycle test loop.

J. J. Sienicki, A. Moisseytsev, 2011 .

Validation of the THIRMAL-1 melt-water interaction code

J. J. Sienicki, B. W. Spencer, C. C. Chu, 1995 .

Optimization of a small modular lead fast reactor with steam cycle for remote siting.

E. E. Feldman, T. Y. C. Wei, J. J. Sienicki, 2004 .

Thermal behavior of molten corium during TMI-2 core relocation event

J. L. Anderson, J. J. Sienicki, 1988 .

Comparison of the EPIC and PLUTO computer codes for TOP conditions

P. A. Pizzica, P. B. Abramson, J. J. Sienicki, 1977 .

Linear stability analysis on single-phase circulation in Argonne lead loop facility.

J. J. Sienicki, Q. Wu, 2002 .

Progress report on dynamic simulation of the Sandia small-scale supercritical carbon dioxide brayton cycle test loop with the ANL plant dynamics code

J. J. Sienicki, A. Moisseytsev, 2012 .

Performance improvement options for the supercritical carbon dioxide brayton cycle.

J. J. Sienicki, A. Moisseytsev, 2008 .

Analysis of Transient Coolant Void Formation During a Guillotine-Type HX Tube Rupture Event in the STAR-LM System Employing a Supercritical CO2 Brayton Cycle

J. J. Sienicki, M. T. Farmer, J. Sienicki, 2004 .

Analysis of reactor material experiments investigating corium crust stability and heat transfer in jet impingement flow

B. W. Spencer, J. J. Sienicki, 1985 .

Probabilistic Accident Analysis with Deterministic Codes Using Stochastically Variable Parameters

H. H. Hummel, P. A. Pizzica, P. B. Abramson, 1978 .