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PUBLICATIONS |
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(ANS
= American Nuclear Society, ASME = American Society of Mechanical
Engineers)
Students are denoted with an *. A.
Theses
PhD
Dissertation, Integrated Steam Explosion Analysis with the VESUVIUS
Code,
University of M.S.
Thesis, Behavior of Steam-Air Systems Condensing in Cocurrent
Vertical Downflow,
B.
Archival Journal
Publications
1.
K. Vierow,
M. Naitoh, K. Nagano, K. Araki, “Development of the VESUVIUS Code for
Steam Explosion Analysis Part 1: Molten Jet Breakup Modeling”,
Journal of the Japanese Society
of Multiphase Flow, Vol. 12, No. 3, pp. 242-248, 1998.
2.
K. Vierow,
M. Naitoh, K. Nagano, K. Araki, “Development of the VESUVIUS Code for
Steam Explosion Analysis Part 2: Verification of Jet Breakup Modeling”,
Journal of the Japanese Society
of Multiphase Flow, Vol. 12, No. 4, pp. 358-364, 1998.
3.
K. Vierow,
K. Araki, “Deterministic Trigger Model for the VESUVIUS Steam Explosion
Code”, Journal of Nuclear Science
and Technology, Vol. 36, No. 2, pp. 213-215, 1999.
4.
T. Morii, K. Vierow, “The
SOAR Method for Automatically Optimizing SIMPLE Relaxation Factors”,
Numerical Heat Transfer, Part B:
Fundamentals, Vol. 38, pp. 309-332, 2000.
5.
M. Kimura, M. Takei, A. Saima,
K. Vierow, Y. Saito, K. Horii, “Fluctuating Component of
Condensation Jet Image Using Wavelets”,
The Journal of Flow Visualization
and Image Processing, Vol. 8,
Issue 2-3, pp. 149-164,
2001.
6.
K. Vierow,
Y. Liao*, J. Johnson*, M. Kenton, R. Gauntt, “Severe Accident Analysis
of a PWR Station Blackout with the MELCOR, MAAP4 and SCDAP/RELAP5
Codes”,
Nuclear Engineering and Design,
Vol. 234, Issue 1-3, pp.
129-145, 2004.
7.
T. Nagae, M. Murase, T.
Wu*, K. Vierow,
“Analysis of Reflux Condensation Heat Transfer of Steam-Air Mixtures in
a Vertical Tube”, Journal of
Nuclear Science and Technology,
Vol. 42, No. 1, pp. 50-57, 2005.
8.
Y. Liao*, K. Vierow, “MELCOR
Modeling of Creep Rupture in Steam Generator Tubes”,
Nuclear Technology, Vol. 152, No. 3,
pp.
302-313, 2005.
9.
T. Wu*, K. Vierow, “A Local
Heat Flux Measurement Technique for Inclined Heat Exchanger Tubes”,
Experimental Heat Transfer,
Vol. 19, No. 1, pp. 1-14, 2006.
10.
T. Wu*, K. Vierow,
“Experimental Study of Steam Horizontal In-Tube in the Condensation in
the Presence of a Noncondensable Gas”,
International Journal of Heat and
Mass Transfer, Vol.
49, pp. 2491-2501, 2006.
11.
T. Nagae, M. Murase, T. Chikusa,
K. Vierow, T. Wu*, “Reflux Condensation Heat Transfer of Steam-Air
Mixture under Turbulent Flow Conditions in a Vertical Tube”,
Journal of Nuclear Science and
Technology, Vol. 44, No. 2, pp. 171-182, 2007.
12.
Y.
Liao*,
K. Vierow, “A Generalized
Diffusion Layer Model for Condensation of Vapor with Non-condensable
Gases”,
Transactions of the ASME, Journal
of Heat Transfer, Vol. 129, pp. 988-994, Aug. 2007.
13.
Y. Liao*, K. Vierow, A.
Dehbi, S. Guentay, “Transition from Natural Convection for Steam-Gas
Flow Condensing along a Vertical Plate”, submitted to
International Journal of Heat and
Mass Transfer, accepted in Mar. 2008 for publication.
14.
Y. Liao*, K. Vierow,
“Variable Property Effects on Vapor Condensation with a Noncondensable
Gas”, submitted to Nuclear
Technology, accepted in Apr. 2008 for publication.
C.
Submitted
Archival Journal
Publications
1.
S. B. Rodriguez, D. Louie, R. O. Gauntt, F. Gelbard, R. Cole, M.
El-Genk, J.-M. Tournier, K. Mcfadden, S. T. Revankar,
K. Vierow, T. Drennen, B.
Martin, L. Archuleta, “MELCOR-H2 Transient Analysis Of Sulfur-Iodine
Cycle Experiments And Recent MELCOR-H2 Benchmarks Of VHTRS”, submitted
to Nuclear Technology, Nov.
2007.
2.
N. Brown, S. Oh, S. T. Revankar,
K. Vierow, S. Rodriguez, R. Cole Jr., R. O. Gauntt, “Simulation of
Sulfur Iodine Thermochemical Hydrogen Production Plant Coupled To High
Temperature Heat Source”, submitted to
Nuclear Technology, Dec.
2007.
3.
K. Vierow,
K. Hogan*, H. Alkaabi*, S. Revankar, R. K. Cole Jr., R. O. Gauntt, S. B.
Rodriguez, “MELCOR Analysis of High-Temperature Gas-Cooled Nuclear
Reactors”, submitted to Journal
of Enhanced Heat Transfer, Feb. 2008.
D.
Books
and Book Chapters
1.
K.
Vierow, “Evaluation
of Condensation Heat Transfer in a Vertical Tube Heat Exchanger”,
Handbook of Heat Transfer Calculations, Myer Kutz,
(Ed.),
2.
K.
Vierow,
“Enhancement of Nuclear Power Plant Safety by Passive Condensation Heat
Transfer Systems”, Thermal Engineering Aspects in Power Systems,
Book series “Development in Heat Transfer”, R. Amano, B. Sunden (Ed.),
WIT press, expected publication date of 2008.
**invited contribution**
E.
Refereed
Conference
or
Symposium
Proceedings
2.
K. Vierow,
V. E. Schrock, “Condensation in a Natural Circulation Loop with
Noncondensable Gases Part II - Flow Instability”,
Proc. of International Conference
on Multiphase Flow ‘91 (Japanese Society of Multiphase Flow, ANS),
3.
K. Vierow,
H. E. Townsend, J. R. Fitch, J. G. M. Andersen, Md. Alamgir, V. E.
Schrock, “BWR Passive Containment Cooling System by Condensation-Driven
Natural Circulation”, Proc. of
The First ASME/JSME Joint International Conference on Nuclear
Engineering - 1 (ICONE-1), Tokyo, Japan, pp. 289 - 294, Nov., 1991.
4.
K. Vierow,
V. E. Schrock, “Condensation in a Natural Circulation Loop with
Noncondensable Gas Present: Part I - Heat Transfer”,
Proc.
of
5.
K. Vierow,
V. E. Schrock, “Condensation in a Natural Circulation Loop with
Noncondensable Gas Present: Part II - Flow Instability”,
Proc.
of
6.
K. Vierow,
J. R. Fitch, F. E. Cooke, “Analysis of SBWR Passive Containment Cooling
Following a LOCA”, Proc. of
International Conference on Design and Safety of Advanced Nuclear Power
Plants (Atomic Energy Society of Japan), Tokyo, Japan, pp. 31.2-1 -
31.2-7, Oct., 1992.
7.
K. Vierow,
D. B. MacDonald, C. E. Buchholz, J. R. Fitch, “Comparison of the TRACG
and MAAP-SBWR Codes for SBWR Safety Analysis”,
Proc. of The Second ASME/JSME
Joint International Conference on Nuclear Engineering - 2 (ICONE-2),
San Francisco, CA, pp. 193 - 200, Mar., 1993.
8.
K. Vierow,
“A Method for Predicting Condensation-Driven Heat Removal in a BWR
Passive Containment Cooling System”,
Computer Assisted Mechanics and
Engineering Sciences (CAMES),
proc.
of conference sponsored by
the Polish Academy of Sciences, Vol. 1, No. 3/4, pp. 205 - 226 , 1994.
9.
K. Vierow,
M. Akiyama, S. Ohta, H. Ban, A. Hoizumi, M. Naitoh, Y. Shinohara, K.
Takumi, “The IMPACT Super
Simulator - Conceptual Design”,
Proc. of The Second Workshop on Super Simulators for Nuclear Power
Plants, (Nuclear Power Engineering Corporation) Tokyo, Japan, pp. 3
- 10, Nov., 1994.
10.
K. Vierow,
M. Akiyama, S. Ohta, H. Ban, A. Hoizumi, M. Naitoh, Y. Shinohara, K.
Takumi, “The IMPACT Super Simulator - Basic Framework”,
Proc. of 1995 Simulation
Multiconference (Society for Computer Simulation), Phoenix, AZ, pp.
169 - 174, Apr., 1995.
11.
K. Vierow,
M. Naitoh, K. Nagano, K. Araki, “Parallelization of the VESUVIUS Module
for Analysis of an Ex-Vessel Steam Explosion on an IBM SP2”,
Proc. of The Third Workshop on
Super Simulators for Nuclear Power Plants (SS’95) (Univ. of Tokyo),
Tokyo, Japan, pp. 75 - 85, Dec., 1995.
12.
K. Vierow,
K. Nagano, K. Araki, “Development of the VESUVIUS Model and Analysis of
the Premixing Phase of an Ex-vessel Steam Explosion”,
Proc. of The
Fourth International
Conference on Nuclear Engineering - 4 (ICONE-4),
New Orleans, LA, Vol. 1, Part A, pp. 333 - 341, Mar., 1996.
13.
K. Vierow,
M. Naitoh, K. Nagano, K. Araki, “Development of the Steam Explosion
Analysis Module VESUVIUS - (1) Modeling of the Premixing Phase”,
Proc. of The Fifteenth Symposium
on Multiphase Flow (Japanese Society of Multiphase Flow),
14.
M. Akiyama, K. Vierow, M.
Naitoh, Y. Nakadai, K. Nagano, “Parallelization of the Single-Phase Flow
Analysis Module”, Proc. of The
Fifteenth Symposium on Multiphase Flow (Japanese Society of
Multiphase Flow), Fukui, Japan, pp. 217 - 220, Jul., 1996. (in Japanese)
15.
K. Vierow,
M. Naitoh, K. Nagano, K. Araki, “Analysis of the Premixing Phase of a
Vapor Explosion with the VESUVIUS Code”,
Proc. of the 74th Annual Meeting
of the Japan Society of Mechanical Engineers, Tokyo, Japan, pp. 52 -
55, Mar., 1997.
16.
M. Naitoh, H. Ujita, H. Nagumo, K. Miyagi, N. Abe,
K. Vierow, M. Akiyama, M.
Shiba, “Development of the Simulation System "IMPACT" for Analysis of
Nuclear Power Plant Severe Accidents”,
Proc. of the Eighth International
Topical Meeting on Nuclear Reactor Thermal-Hydraulics
(NURETH-8) (Atomic
Energy Society of Japan, ANS), Kyoto, Japan, pp. 1204 - 1211, Sept.,
1997.
17.
K. Vierow,
H. Ujita, H. Nagumo, K. Miyagi, N. Sato, S. Nagata, Y. Ando, M. Naitoh,
“The IMPACT Simulation System for Evaluating Nuclear Power Plant
Safety”, Proc. of the 75th Annual
Meeting of the Japan Society of Mechanical Engineers, Tokyo, Japan,
(4
pp.) Apr., 1998.
18.
K. Vierow,
M. Naitoh, K. Nagano, K. Araki, “Development of the VESUVIUS Module -
Molten Jet Breakup Modeling and Model Verification”,
Proc. of OECD/CSNI Specialists
Meeting on Fuel Coolant Interactions, Tokai, Japan, May 19 - 21,
1997, JAERI Conf 97-011, NEA/CSNI R(97)26, pp. 541-565, Jun., 1998.
19.
K. Vierow,
S. Nagata, K. Araki, “Parallelization of the IMPACT Simulator for
Nuclear Power Plant Accident Evaluations”,
Proc. of the Advanced Simulation
Technologies Conference 1999 (Society for Computer Simulation),
20.
T. Ikeda, M. Naitoh, H. Ujita, N. Sato, T. Iwashita, T. Morii,
K. Vierow, S. Nagata,
“Overview of the Simulation System “IMPACT” for Analysis of Nuclear
Power Plant Thermal-Hydraulics and Severe Accidents”,
Proc.
of OECD Workshop on
Advanced Thermal-Hydraulic and Neutronic Codes Applications,
Barcelona, Apr., 2000.
21.
K. Vierow,
“Analytical Investigation of Effect of Melt Composition on the Premixing
Phase of a Steam Explosion”,
Proc. of Second Japan-Korea Symposium on Nuclear Thermal Hydraulics and
Safety-NTHAS2, Fukuoka, Japan, pp. 537-545, Oct., 2000.
22.
M. Kimura, M. Takei, K. Vierow,
Y. Saito, K. Horii, A. Saima, “Wavelet Analysis of Cold Jets Image
Issuing into High Humidity Environment”,
Proc.
of
The 3rd Pacific Symposium on Flow Visualization and Image Processing,
Maui, HI, paper
F3317, (9 pp.) Mar.,
2001.
23.
M. Kimura, M. Takei, A. Saima,
K. Vierow, Y. Saito, K. Horii, “Relationship between Temperature
Distribution and 2D Image of Condensation Jets Using Discrete Wavelets
Multiresolution”,
Proc.
of
ASME Fluids Engineering
Division Summer Meeting,
Forum on Wavelet Applications in Fluid Mechanics,
paper
FEDSM2002-31114, (10 pp.)
July 2002.
24.
M. Kimura, K. Hodoya, M. Takei, A. Saima,
K. Vierow, “A Study on
Condensation Jet by Using LLS and Wavelets Multiresolution”,
Proc.
of 3rd Pacific-Asia
Conference on Mechanical Engineering,
Manila, Philippines,
(10
pp.) Aug., 2002.
25.
M. Kimura, M. Takei, A. Saima,
K. Vierow, Y. Saito, K. Horii, “Temperature Boundary Analysis of
Condensation Jets Using Discrete Wavelets Multiresolution and 2
Dimensional Imaging”,
Proc.
of
ASME Fluids Engineering
Division Summer Meeting, 4th ASME-JSME Joint Fluids Engineering
Conference,
Honolulu, HI,
paper
FEDSM2003-45027, (6 pp.)
July 2003.
26.
J. Johnson Colbert*, K. Vierow,
“Verification of the MELCOR Code against SCDAP/RELAP5 for Severe
Accident Analysis”,
Proc.
of
International Conference on
Advanced Nuclear Power Plants and Global Environment, ANP2003/GENES4,
Kyoto, Japan,
paper
1139 (6 pp.), Sept.
2003.
27.
K. Vierow,
T. Nagae, T. Wu*, “Experimental Investigation of Reflux Condensation
Heat Transfer in PWR Steam Generator Tubes in the Presence of
Noncondensible Gases”,
Proc.
of
10th International Topical
Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10),
Seoul, Korea,
paper
C00305, (17 pp.) Oct.
2003.
28.
T. Wu*, H. Tokuma, K. Vierow,
“Experimental Investigation of Steam Condensation in a Horizontal Tube
in the Presence of Noncondensable Gas”,
Proc.
of International
Congress on Advanced Nuclear Power Plants (ICAPP’04),
(embedded in 2004 ANS annual meeting), Pittsburgh, PA,
paper 4137, pp. 1453-1462,
June, 2004.
29.
K. Vierow,
Y. Liao*, “Progress in and Challenges for U.S. Severe Accident Analysis
Codes”,
proc. of Sixth International
Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operations and
Safety (NUTHOS-6), Nara, Japan, paper KN-05, (16 pp.)
30.
T.
Wu*,
K. Vierow, “Horizontal
In-Tube Condensation In The Presence Of A Noncondensable Gas”,
Proc. of
11th International
Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-11),
31.
C.
Burns*, Y. Liao*,
K. Vierow, “MELCOR Code
Assessment by Simulation of TMI-2”,
Proc.
of 11th
International Topical Meeting on Nuclear Reactor Thermal Hydraulics
(NURETH-11),
32.
T.
Nagae, M. Murase, T.
Wu*, K. Vierow, “Modeling of
Reflux Condensation Heat Transfer In The Presence Of
a
Noncondensable Gas”,
Proc.
of
11th International
Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-11),
Avignon, France,
(9
pp.) Oct. 2005.
33.
Y. Liao*, K. Vierow,
“Application of a Generalized Diffusion Layer Theory to Predict
Experiment Data on Condensation of Vapor-air Mixtures”,
Proc.
of International Conference for Advanced Nuclear Power Plants (ICAPP-06),
Reno, NV, (8 pp.) June 2006.
34.
S. T.
Revankar, K. Vierow, A.
Ward*, A. Wichman*, K. Wangerin*, J. Foster,* “Coupled High Temperature
Gas Reactor and Sulfur Iodide Process for Hydrogen Generation”,
Proc. of ASEE Annual Conference,
Chicago, IL, June 2006.
35.
Y. Liao*, K. Vierow,
“Optimum Channel Inclination for Gas Venting under Countercurrent Flow
Limitations”, Proc. of The
Fourteenth International Conference on Nuclear Engineering - 14
(ICONE-14), Miami, FL, paper ICONE14-89665 (7 pp.), Jul. 17-20,
2006.
36.
S. B.
Rodríguez Jr., D. Louie, R. O. Gauntt, R. Cole Jr., K. McFadden, F.
Gelbard, T. Drennen, B. Martin, L. Archuleta, S. T. Revankar,
K. Vierow, M. El-Genk, and
J. M. Tournier, “Melcor-H2 Benchmarking of the SNL Sulfuric Acid
Decomposition Experiments”, Proc.
of AIChE 2007 Spring National Meeting,
37.
Sal B. Rodriguez, Dave Louie, Randall O. Gauntt, Fred Gelbard, Randy
Cole, Katherine McFadden, Tom Drennen, Billy Martin, Louis Archuleta,
Mohamed El-Genk, Jean-Michel Tournier, Shripad T. Revankar, and
K. Vierow, “MELCOR-H2
Transient Analysis of Sulfur-Iodine Cycle Experiments”,
Proc. of ANS 2007 Annual Meeting,
Hydrogen Embedded Topical, Boston, MA, (5 pp.) June 2007.
38.
Y.
Liao*, K. Vierow, “Variable
Property Effects on Vapor Condensation with a Noncondensable Gas”,
Proc. of 12th International
Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12),
Pittsburgh, PA, (12 pp.) Oct., 2007.
39.
N.
Brown, S. T. Revankar, K. Vierow,
S. Rodriguez, R. Cole Jr., R. O. Gauntt, “Thermochemical Hydrogen Pant
Coupled to High Temperature Gas Cooled Reactor”,
Proc. of 12th International
Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12),
Pittsburgh, PA, (17 pp.) Oct., 2007.
40.
K.
Vierow,
K. Hogan*, H. Alkaabi*, S. Revankar, R. K. Cole Jr., R. O. Gauntt, S. B.
Rodriguez, “MELCOR Analysis of High-Temperature Gas-Cooled Nuclear
Reactors”, Proc. of India Society
of Heat and Mass Transfer – American Society of Mechanical Engineers
Conference, JNTU Hyderabad, India, (8 pp.) Jan. 3-5, 2008.
41.
K.
Vierow,
“Severe Accident Investigations and Modeling – Recent Progress and
Issues”, Proc. of New Horizons in
Nuclear Reactor Thermal Hydraulics, Bhabha Atomic Research Centre
(BARC), Mumbai, (10 pp.) Jan 7-8, 2008.
F.
Refereed
Conference
Summaries
or Abstracts
1.
J. Johnson Colbert*, K. Vierow
“Comparison of MELCOR and SCDAP/RELAP5 Codes for Station Blackout
Analysis”,
Proc.
of
ANS
2003
Winter Meeting,
New Orleans,
pp.
398-399, Nov. 2003.
2.
T.
Wu*,
K. Vierow, “Fundamental
Condensation Heat Transfer Studies for Horizontal PCCS Heat Exchanger”,
Proc. of
2005 ANS Annual Meeting,
3.
S.
Rodríguez, Jr., R. O. Gauntt, S. T. Revankar,
K. Vierow, “Development of
Design and Simulation Model and Safety Study of Large-Scale Hydrogen
Production Using Nuclear Power”,
Proc. of AIChE 2005 Annual Meeting, Cincinnati, OH, Oct. 30-Nov. 4,
2005.
4.
Y. J.
Song*, K. Vierow,
“Horizontal Heat Exchanger Scaling for Passive Containment Heat Removal
System Experiments”, Proc. of the
ANS 2005 Winter Meeting,
5.
S. Rodríguez, R. O. Gauntt, S. Revankar,
K. Vierow, “MELCOR
Modification for Large-Scale Hydrogen Production Using Nuclear
Thermochemical Cycles”, Proc. of
the ANS 2005 Winter Meeting,
6.
K.
J. Hogan*,
K. Vierow, S. T. Revankar,
R. K. Cole, Jr., R. O. Gauntt, S. Rodriguez, “Assessment of PBMR
Analysis Using the MELCOR Code”,
Proc. of the ANS 2006 Annual Meeting, Reno, NV, June, 2006.
7.
S. T. Revankar, S. Oh, N. Brown, S. Rodriguez,
K. Vierow, R. Gauntt, R.
Cole, “Simplified Model to Couple SI Cycle to Nuclear Heat Transport
System”, Proc. of the ANS 2006
Annual Meeting, Reno, NV, June, 2006.
8.
S. T. Revankar, S. Oh, N. Brown, S. Rodriguez,
K. Vierow, R. Cole, R.
Gauntt, “Assessment of Sulfur Iodine Thermochemical Water Splitting
Process Flowsheet with ASPEN Code”,
Proc. of the ANS 2006 Annual
Meeting, Reno, NV, June, 2006.
9.
Oh, S., S. T. Revankar, N. Brown, S. B. Rodriguez,
K. Vierow, “Simulation of
Sulfur Iodine Thermochemical Cycle Coupled to Nuclear Heat Transport
System”, AICHe 2006 Annual
Meeting, Nov., 2006
10.
S. Rodriguez, R. Gauntt, R. Cole, M. Modesto, K. Mcfadden, T. Drennen,
W. Martin, S. T. Revankar, K
Vierow, D. Louie, L. Archuleta, ‘Modeling of Z-IFE Hydrogen Plants
with MELCOR-H2”, Proc. of 17th
Topical Meeting of Fusion Energy, embedded topical in the 2006 ANS
Winter Meeting, Nov. 2006.
11.
S. Oh, N. R. Brown, S. T. Revankar,
K. Vierow, S. Rodriguez, R.
Cole Jr., R. Gauntt, “Transient Model for SI Cycle Hydrogen Generating
Plant Coupled to High Temperature Gas Cooled Reactor”,
Proc. of ANS 2006 Winter Meeting,
Albuquerque, NM, Nov. 2006.
12.
S. Rodriguez, R. Gauntt, R. Cole, K. Mcfadden, F. Gelbard, W. Martin, S.
T. Revankar, K. Vierow, D.
Louie, L. Archuleta, M. S. El-Genk, “MELCOR-H2: A Modular, Generalized
Tool for the Dynamic Simulation and Design of Fully-Coupled Nuclear
Reactor/Hydrogen Production Plants”,
Proc. of ANS 2006 Winter Meeting,
Albuquerque, NM, Nov. 2006.
13.
S. Rodriguez, R. Cole, K. Mcfadden, R. Gauntt, F. Gelbard, L.
Malczynski, W. Martin, S. T. Revankar,
K. Vierow, D. Louie, L.
Archuleta, M. S. El-Genk, J. M. Tournier, “Addition of Secondary System
Modules and a Graphical User Interface into MELCOR-H2 Phase 1”,
Proc. of ANS 2006 Winter Meeting,
Albuquerque, NM, Nov. 2006.
14.
K. J.
Hogan*, Y. Liao*, K. Vierow,
R.K. Cole, Jr., R.O. Gauntt, “Implementation of a New Diffusion Layer
Model for Condensation with Non-condensible Gases Into MELCOR”,
Proc. of 2007 ANS Winter Meeting,
Washington DC, Nov. 2007.
15.
N.
Zhen*, K. Vierow, S.
Rodriquez, R. Gauntt, “Development of Prismatic VHTR Model Using the
MELCOR Code”, Proc. of 2007 ANS
Winter Meeting,
16.
S.
Rodriguez, D. Louie, R. Gauntt, S. T. Revankar,
K. Vierow, “MELCOR-H2
Transient Analysis of Sulfur-Iodine Cycle Experiments”,
Proc. of
ANS 2007 Annual Meeting,
Boston, MA, June 2007.
G.
Non-refereed
Conference
or
Symposium
Proceedings
1.
K. Vierow,
M. Naitoh, K. Nagano, K. Araki, “Development of the Super Simulator
"IMPACT" (III) - (4) VESUVIUS Module Development for Steam Explosion
Analysis”, Proc. of the 1996 Fall
Conference of the Atomic Energy Society of Japan, Sendai, Japan, p.
419, Sept., 1996. (in Japanese)
2.
K. Vierow,
K. Araki, “Development of the Super Simulator IMPACT (V) - (7)
Propagation Phase Analysis with the VESUVIUS Steam Explosion Module”,
Proc. of the 1998 Fall Conference
of the Atomic Energy Society of Japan, Fukui, Japan, p. 486, Sept.,
1998. (in Japanese)
3.
K. Vierow,
K. Araki, “Development of the Super Simulator IMPACT (V) - (8)
Integration of the VESUVIUS Steam Explosion Analysis Module”,
Proc. of the 1998 Fall Conference
of the Atomic Energy Society of Japan, Fukui, Japan, p. 487, Sept.,
1998. (in Japanese)
4.
K. Vierow,
K. Araki, “Integral Steam Explosion Calculations with the Steam
Explosion Analysis Code VESUVIUS”,
Proc. of The Eighteenth Symposium
on Multiphase Flow (Japanese Society of Multiphase Flow),
5.
K. Vierow,
K. Nagano, “Hydrogen Mixing Analysis in the Nuclear Power Plant
Containment Vessel with the Two-Fluid HYMIX Module”,
Proc. of The Japanese Society of
Multiphase Flow Annual Meeting 2000, Sendai, Japan, pp. 125 - 126,
Jul., 2000. (in Japanese)
6.
T. Nagae, M.
Murase, T. Wu*, K. Vierow,
“Reflux Condensation Heat Transfer of Steam-Air Mixture in a Vertical
Tube under Laminar Gas-Liquid Countercurrent Flow Conditions”,
Proc.
of Fall Meeting of the
Atomic Energy Society of Japan,
Shizuoka, Japan,
paper
F50, p. 403, Sept. 24-26,
2003. (in Japanese)
7.
T. Nagae, M.
Murase,
T.
Wu*,
K. Vierow,
“Evaluation Method of Condensation Heat Transfer of Steam-Air Mixture in
a Vertical Tube”,
Proc.
of the Annual Meeting of the
8.
T. Nagae, M. Murase, T. Wu*,
K. Vierow, “Reflux
Condensation Heat Transfer of Steam and Noncondensable Gas Mixture under
Gas-Liquid Countercurrent Flow (1) Correlation of Condensation Heat
Transfer Coefficients in a Vertical Tube”,
Proc. of Fall Meeting of the
Atomic Energy Society of Japan, Kobe, Japan, p. 307, Sept. 13-15,
2005. (in Japanese)
H.
Other Submitted Publications
1.
P. V. Tsvetkov, K. Vierow,
K. L. Peddicord, J. C. Ragusa, S. M. Mcdeavitt, J. W. Poston, Sr., L.
Shao, G. Willems, “Autonomous Multi-Purpose Floating Power System With a
Compact Static Pebble Bed Reactor”, accepted for full paper submission
to PHYSOR'08 International Conference on the Physics of Reactors,
“Nuclear Power: A Sustainable Resource”, Kursaal Conference Center,
Interlaken, Switzerland, September 14–19, 2008.
2.
Y. Liao*, K. Vierow,
J. T. Han, “MELCOR Validation against a PUMA Facility Main Steam Line
Break Integral Test”, submitted to
Proc. of International Conference
for Advanced Nuclear Power Plants (ICAPP-08), Anaheim, CA, June
2008.
3.
K. Vierow, F. Best,
J. Ford, Y. Hassan, S. McDeavitt, J. Ragusa, W. D. Reece, L. Shao, P.
Tsvetkov, “TAMU Nuclear Safety Curriculum Development for a 21st Century
Workforce”, accepted for publication in
Proc. of 2008 ANS Annual Meeting,
Anaheim, CA, June 2008.
I.
Government, University, or Industrial Reports (non-refereed)
1.
K. Vierow,
O. Yokomizo, Effect of Additional Core Support Plate Stiffeners on
Steady-State Core Pressure Drop, Energy Research Laboratory,
Hitachi, Ltd., Research Rpt. 2870,
2.
K. Vierow,
V.
3.
K. Vierow,
V. E. Schrock, Condensation Heat Transfer in Natural Circulation with
Noncondensable Gas, Dept. of Nuclear Engineering, Univ. of CA at
Berkeley, May 1990.
4.
J. R. Fitch, K. Vierow, U.
Saxena, SBWR Containment Methods for Pressure Calculation, GE
Nuclear Energy, Rpt. No. DRO-00012, 1992.
5.
K. Vierow,
GIRAFFE Passive Heat Removal Testing Program, GE Nuclear Energy,
Rpt. No. NEDC-32215P, Jun. 1993.
6.
K. Vierow,
S. Yokobori, GIRAFFE Passive Heat Removal Testing Program,
Nuclear Engineering Laboratory, Toshiba, Ltd., Rpt. No. TOGE239-T05,
Jun. 1993.
7.
K. Vierow
et al., GIRAFFE Testing Program to Support SBWR PCCS Design, GE
Nuclear Energy, Design Record File No. DRO-00002, Dec. 1993.
8.
J. G. M. Andersen, Md. Alamgir, J. S. Bowman, Y. K. Cheung, J. Haces, S.
Khorana, L. A. Klebanov, W. Marquino, M. Robergeau, D. A. Salmon, J. C.
Shaug, B. S. Shiralkar, F. D. Shum,
K. Vierow, A. L. Wirth,
TRACG Qualification, prepared by GE Nuclear Energy, NEDE-32177P,
Rev. 1, Class 3, San Jose, CA, June 1993.
9.
K. Vierow,
J. Johnson*, R. Alley*, A. Garmoe*, E. Germain*, A. Slaga*, J.
Mikkelssen*, Task Order No. 12 “MELCOR Assessment against
SCDAP/RELAP5, Contract Research Final Report submitted to U.S.
Nuclear Regulatory Commission, Jan. 2003.
10.
K. Vierow,
T. Wu*, Y. J. Song*, M. Cameron*, J. Hardy*, Investigation Of
Horizontal Heat Exchanger Performance for Passive Containment Heat
Removal, Contract Research Final Report submitted to Tokyo Electric
Power Company, Jun. 2003.
11.
K. Vierow,
T. Wu*, M. Cameron*, A. Donato*, Y. J. Song*, Investigation of
Condensation Heat Transfer and Fluid Flow in PWR Steam Generator Tubes
in the Presence of Noncondensible Gases, Contract Research Final
Report submitted to Institute of Nuclear Safety System, Inc., Mar. 2004.
12.
M. Ishii, X. Sun, S. T. Revankar,
K. Vierow, Y. Xu, S. Kim, B.
Ozar, S. Vasavada, H. H. Yoon, S. Paranjape, S. Kuran, L. Cheng, R.
Situ, S. W. Choi, W. Wang, Scaling and Scientific Design Study for GE
ESBWR Relative to PUMA Facility, PU/NE-03-07, prepared for the U.S.
Nuclear Regulatory Commission, Mar. 2004.
13.
M. Ishii, S. T. Revankar, K.
Vierow, S. W. Choi, J. Yang, H. J. Yoon, W. Wang, PCCS Separate
Effects Tests in the PUMA Facility (Quick Look Report),
PU/NE 04/03,
prepared for the U.S. Nuclear Regulatory Commission, Apr. 2004.
14.
M. Ishii, S. T. Revankar, K.
Vierow, S. W. Choi, J. Yang, H. J. Yoon, J. Han, QA of the
Current PUMA Design, PU/NE 04/XX, prepared for the U.S. Nuclear
Regulatory Commission, Apr. 2004.
15.
M. Corradini, R. Henry, S. Levy, D. Powers,
K. Vierow,
Severe Accident Phenomena Identification and Ranking Tables, in
Phenomena Identification and Ranking Technique (PIRT) Applied to the
ACR-700 Design,
NUREG/CR-XXXX, May,
2004.
16.
M.
Ishii, S. T. Revankar, K. Vierow,
H. J. Yoon, X. Sun, L. Cheng, S. W. Choi, J. H. Lim, J. Yang, W. Wu,
A Data Report on PUMA Large Break LOCA Main Steam Line Break Test Data
for Partial Simulation of ESBWR, PU/NE 04/ XX, prepared for the U.S.
Nuclear Regulatory Commission, Jul. 2004.
17.
M. Ishii, X. Sun, S. T. Revankar,
K. Vierow, Y. Xu, S. J. Kim,
H. J. Yoon, L. Cheng, B. Ozar, S. Vasavanda, S. Paranjape, S. Kuran, R.
Situ, S. W. Choi, J. Lim, T. Norman, K. S. Woo, J. Yang, W. Wang, J.
Han, Second Scaling and Scientific Design Study for GE ESBWR Relative
to PUMA Facility with Volumetric Ratio of 1/475,
PU/NE 04/04,
prepared for the U.S. Nuclear Regulatory Commission, Jul. 2004.
18.
T. Nagae, M. Murase, T. Wu*, K.
Vierow, “Reflux Condensation Heat Transfer of Steam-Air Mixtures
under Gas-Liquid Countercurrent Flow”,
INSS Journal, Oct. 2004.
19.
M.
Ishii, S. T. Revankar, K. Vierow,
H. J. Yoon, L. Cheng, K. S. Woo, W. Wang, PUMA Medium Break LOCA
Gravity Drain Line Break Test Data for Partial Simulation of ESBWR,
PU/NE-04-XX, prepared for the U.S. Nuclear Regulatory Commission, Dec.
2004.
20.
M.
Ishii, S. T. Revankar, K. Vierow,
H. J. Yoon, S.W. Choi, J. Yang, W. Wang, PUMA Medium Break LOCA GDCS
Drain Line Break Test with One ICS and One PCCS Disabled for Partial
Simulation of ESBWR, PU/NE-04-XX, prepared for the U.S. Nuclear
Regulatory Commission, Dec. 2004.
21.
M.
Ishii, S. T. Revankar, K. Vierow,
H. J. Yoon, S. W. Choi, J. Yang, W. Wang, A Data Report on PUMA Small
Break LOCA Bottom Drain Line Break Test with All ICS Disabled for
Partial Simulation of ESBWR, PU/NE 04/XX, prepared for the U.S.
Nuclear Regulatory Commission, Dec. 2004.
22.
M.
Ishii, S. T. Revankar, K. Vierow,
H. J. Yoon, L. Cheng, K. S. Woo, J. Han, PUMA Large Break LOCA Main
Steam Line Break Test with ICS Disabled for Partial Simulation of ESBWR,
PU/NE 05/XX, prepared for the U.S. Nuclear Regulatory Commission, Jan.
2005.
23.
M.
Ishii, S. T. Revankar, K. Vierow,
L. Cheng, K. S. Woo, J. Lim, J. Han, Separate Effects Test -
Suppression Pool Condensation and Mixing – Quick Look Report, PU/NE
05/XX, prepared for the U.S. Nuclear Regulatory Commission, Jan. 2005.
24.
M. Ishii, S. T. Revankar, K.
Vierow, J. Lim, H. J. Yoon, H. S. Park, L. Cheng, TRACE
Assessment against PUMA SBWR Main Steam Line Break Test Data,
PU/NE-05-XX, prepared for the U.S. Nuclear Regulatory Commission, July
2005.
25.
M. Ishii, S. T. Revankar, K.
Vierow, K. S. Woo, L. Cheng, J. Lim, H. J. Yoon, H. S. Park, J. T.
Han, Noncondensable Gas Effect on Thermal Stratification in the
Suppression Pool, PU/NE 05-07,
prepared for the U.S. Nuclear Regulatory Commission,
Aug. 2005.
26.
K. Vierow,
T. Wu*, Y. J. Song*, H. Alkaabi*, M. Cameron*, T. Drzewiecki*, J.
Hardy*, B. Mount*, B. Nadir*, K. Prater*, Horizontal Heat Exchanger
Design And Analysis For Passive Containment Heat Removal Systems,
PU/NE 05-10,
contract research final report submitted to U.S. Department of Energy,
Aug. 2005.
27.
S. T.
Revankar,
K. Vierow, S. M. Oh, K.
Hogan*, H. Alkaabi*, Development of Design and Simulation Model and
Safety Study of Large-Scale Hydrogen Production Using Nuclear Power,
Annual Technical Report, Dec. 13, 2004 through Sept. 23, 2005, PU/NE
05-13, submitted to Sandia National Laboratories/U.S. Department of
Energy, Sept. 28, 2005.
28.
T. L. Norman, H. S. Park, S. T. Revankar, M. Ishii,
K. Vierow, J. M. Kelly,
Steam-Air Mixture Condensation in a Subcooled Water Pool – Facility
Design and Scoping Tests, PU/NE-05-19, prepared for the U.S. Nuclear
Regulatory Commission, Dec. 2005.
29.
T. L. Norman, H. S. Park, S. T. Revankar, M. Ishii,
K. Vierow, J. M Kelly,
Steam-Air Mixture Condensation in a Subcooled Water Pool – Data Report,
PU/NE-05-20, prepared for the U.S. Nuclear Regulatory Commission, Dec.
2005.
30.
M. Ishii, S. W. Choi, J. Yang,
K. Vierow, S. T. Revankar, W. Wang, J. Han, PCCS Separate Effects
Tests in the PUMA Facility (Letter Report), PU/NE-05-17, prepared
for the U.S. Nuclear Regulatory Commission, May 2006.
31.
K. Vierow,
Y. Liao* J. T. Han, MELCOR Assessment against a PUMA Main Steam Line
Break Integral Test, PU/NE 06-07, prepared for the U.S. Nuclear
Regulatory Commission, July, 2006.
32.
S. T. Revankar, K. Vierow,
S. M. Oh, N. Brown, K. Hogan*, H. Alkaabi*, Development of Design and
Simulation Model and Safety Study of Large-Scale Hydrogen Production
Using Nuclear Power -
Annual Technical Report, Oct. 1, 2005 through Sept. 15, 2006, PU/NE
06-14, submitted to Sandia National Laboratories/U.S. Department of
Energy, Sept. 15, 2006.
33.
K. Vierow,
Y. Liao*, J. T. Han, MELCOR Assessment against a PUMA Bottom Drain
Line Break Integral Test, PU/NE 06-08, prepared for the U.S. Nuclear
Regulatory Commission, Feb. 2007.
34.
K. Vierow,
Y. Liao*, J. T. Han, MELCOR Assessment against a PUMA GDCS Line Break
Integral Test, prepared for the U.S. Nuclear Regulatory Commission,
April. 2007.
35.
K. Vierow,
T. Aldemir, U. Catalyurek, K. Hogan*, K. Metzroth, “Uncertainty
Quantification in the Reliability and Risk Assessment of Generation IV
Reactors” Yearly Progress Report, March 13, 2006 through March 12,
2007, submitted to the U. S. Department of Energy, June 8, 2007.
36.
K. Vierow,
H. Alkaabi*, K. Hogan*, N. Zhen*, Thermo-Chemical Generation of
Hydrogen: Demonstration of MELCOR-H2 For Usage in the Simulation of
Pebble Bed and Prismatic Very High Temperature Reactors, Final
Technical Report, Feb. 20, 2007 through Sept. 1, 2007, submitted to
Sandia National Laboratories/U.S. Department of Energy, Sept. 10, 2007.
37.
K. Vierow,
I. Choutapalli, K. Hogan*, M. Solmos*, Countercurrent Flow Limitation
Experiments and Modeling for Improved Reactor Safety, Second Year
Progress Report, July 1, 2006 through June 30, 2007, submitted to U.S.
Department of Energy, Sept. 28, 2007. For
multiyear contracts that require annual progress reports, only the
latest report is listed unless there is a special distinction among the
yearly reports.
J.
Publications in Popular Press/Magazines
1.
K. Vierow, “Obtaining the Best of Both Worlds: Dual Experiences in
2.
K. Vierow, Interviewed by Exponent staff, “Nuclear Engineer Joins
Faculty”, Exponent,
3.
K. Vierow, M. Ishii, A. Solomon, Editorial to the Lafayette Journal
and Courier, “Uninformed fear can't guide nuclear issues”,
4.
K. Vierow, “An American’s View of the Changing U.S.”, The Gakusai
Forum for Interdisciplinary Dialogue, Statistics Research Institute,
Tokyo, Japan, Oct. 2002.
(in Japanese)
5.
K. Vierow, “Thermal Hydraulic Research in the Laboratory for Nuclear
Heat Transfer Systems”, Japanese
Journal of Multiphase Flow, Vol. 18, No. 1, Mar. 2004.
6.
K. Vierow, Interview by Emil Venere, “Engineers Improving Programs
Needed for Nuclear Reactor Safety”, Purdue University News release,
http://news.uns.purdue.edu/html4ever/2005/050125.Vierow.nukesafety.html,
7.
K. Vierow,
“Engineers Improving Programs Needed for Nuclear Reactor Safety”,
scientific website PhysOrg.com,
http://www.physorg.com/news2824.html,
8.
K. Vierow, Interview by ANS staff Rick Michal, “ 9. K. Vierow, “Learning from Disaster”, Mechanical Engineering, monthly magazine of the American Society of Mechanical Engineers, pp. 18 and 20, Apr. 2005.
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