| Abstract |
MIT-ANP-TR-120 |
Jiyong Oh and M.W. Golay, Methods for Comparative
Assessment of Active and Passive Safety Systems (February 2008).
|
| Abstract |
MIT-ANP-TR-119 |
M. J. Driscoll, Comparative Economic Prospects
of the Supercritical CO2 Brayton Cycle GFR (February 2008).
|
| Abstract |
MIT-ANP-PR-118 |
Rui Hu and M.S. Kazimi, Stability Analysis of Natural Circulation in BWRs at High Pressure Conditions
(October 2007). |
| Abstract |
MIT-ANP-PR-117 |
P. Hejzlar, M.J. Driscoll, J. Gibbs, Yifang Gong, and S.P. Kao, Supercritical CO2 Brayton Cycle for Medium Power Applications
(July 2007). |
| Abstract |
MIT-ANP-TR-116 |
R. Hannink, J. Buongiorno, Lin-wen Hu, and G. Apostolakis, Using Nanofluids to Enhance the Capability of In-Vessel Retention of Fuel Following Severe Reactor Accidents
(June 2007). |
| Abstract |
MIT-ANP-TR-115 |
J. Lee, P. Hejzlar, and M.S. Kazimi, Gas Heat Transfer in a Heated Vertical Channel under Deteriorated Turbulent Heat Transfer Regime (May 2007). |
| Abstract |
MIT-ANP-TR-114 |
N.A. Carstens, M. J. Driscoll, and P. Hejzlar, Dynamic Response and Safety Implications for Supercritical CO2 Brayton Cycles Coupled to Gen-IV Reactors (June 2007). |
| Abstract |
MIT-ANP-TR-113 |
C.S. Handwerk, M.J.
Driscoll, and P. Hejzlar, Core Design and Performance Assessment for a Supercritical CO2-Cooled Fast Reactor (May 2007). |
| Abstract |
MIT-ANP-TR-112 |
M.A. Pope, P.
Hejzlar, and M.J. Driscoll, Thermal Hydraulics of a 2400 MWth
Supercritical CO2-Direct Cycle GFR (September 2006). |
| Abstract |
MIT-ANP-TR-111 |
R. Eul, K. Ahn,
S.P. Kao, P. Hejzlar, and M.S. Kazimi, A Comparison of Passive vs.
Active Safety Systems for Advanced Light Water Reactors (September
2006). |
| Abstract |
MIT-ANP-TR-110 |
B.D. Middleton
and J. Buongiorno, Supercritical Water Reactor Cycle for Medium Power
Applications (June 2006). |
| Abstract |
MIT-ANP-TR-109 |
C. Gerardi and J.
Buongiorno, Investigation of Pressure Tube and Calandria Tube
Deformation Following a Single Channel Blockage Event in ACR-700 (November 2005). |
| Abstract |
MIT-ANP-TR-108 |
J. Zhao, P. Saha,
and M.S. Kazimi, Stability Analysis of Supercritical Water Cooled
Reactors (September 2005). |
| Abstract |
MIT-ANP-TR-107 |
P. Yarksy, M.J.
Driscoll, and P. Hejzlar, Integrated Design of a Breed and Burn
Gas-cooled Fast Reactor Core (September 2005). |
| Abstract |
MIT-ANP-TR-106 |
G. Jourdan and M.
Golay, Using Risk-Based Regulations for Licensing Nuclear Power
Plants: Case Study of the Gas-cooled Fast Reactor (December 2004). |
| Abstract |
MIT-ANP-TR-105 |
J. Zhao, P. Saha,
and M.S. Kazimi, Analysis of Flow Instabilities in Supercritical
Water-Cooled Nuclear Reactors (October 2004). |
| Abstract |
MIT-ANP-TR-104 |
M.A. Pope, M.
Driscoll, and P. Hejzlar, Reactor Physics Design of Supercritical CO2-Cooled
Fast Reactors (September 2004). |
| Abstract |
MIT-ANP-TR-103 |
K. Gezelius, M.J.
Driscoll, and P. Hejzlar, Design of Compact Intermediate Heat
Exchangers for Gas Cooled Fast Reactors (May 2004). |
| Abstract |
MIT-ANP-TR-102 |
T. Zhai, A.
Kadak, and H-C. No, LOCA and Air Ingress Accident Analysis of a
Pebble Bed Reactor (March 2004). |
| Abstract |
MIT-ANP-TR-101 |
J. Wang, R.
Ballinger, and S. Yip, An Integrated Performance Model for High
Temperature Gas Cooled Reactor Coated Particle Fuel (March 2004). |
| Abstract |
MIT-ANP-TR-100 |
V. Dostal, M.J.
Driscoll, P. Hejzlar, A Super Critical Carbon Dioxide Cycle for Next
Generation Nuclear Reactors (March 2004). |
| Abstract |
MIT-ANP-TR-099 |
S. Blair and N.E.
Todreas, Thermal Hydraulic Performance Analysis of a Small Integral
Pressurized Water Reactor Core (December 2003). |
| Abstract |
MIT-ANP-TR-098 |
J.A. Malen and
N.E. Todreas, Thermal Hydraulic Design of Hydride Fueled Pressurized
Water Reactor Cores (). |
| Abstract |
MIT-ANP-TR-097 |
J.G.B. Saccheri,
N.E. Todreas, and M.J. Driscoll, A Tight Lattice, Epithermal Core
Design for the Integral PWR (August 2003). |
| Abstract |
MIT-ANP-TR-096 |
J.G.B. Saccheri
and N.E. Todreas, A Tight Lattice, Epithermal Core Design for the
IRIS Reactor (May 2003). |
| Abstract |
MIT-ANP-TR-095 |
W. Williams, P.
Hejzlar, M.J. Driscoll, N.E. Todreas, P. Saha, and W-J. Lee, Analysis
of a Convection Loop for GFR Post-LOCA Decay Heat Removal (March
2003). |
| Abstract |
MIT-ANP-PR-094 |
A.C. Kadak and
R.G. Ballinger Modular Pebble Bed Reactor Project, Fourth
Annual Report (December 2002). |
| Abstract |
MIT-ANP-PR-093 |
M.J. Driscoll, P.
Hejzlar, N.E. Todreas, Y. Okano, V. Dostal, and K. Yu, Development of
Gen IV Advanced Gas-Cooled Reactors with Hardened/Fast Neutron Spectrum,
Annual Progress Report (September 2002). |
| Abstract |
MIT-ANP-PR-092 |
P.E. MacDonald,
N.E. Todreas, and J. Buongiorno et al., Design
of an Actinide Burning, Lead or Lead-Bismuth Cooled Reactor That Produces the
Low Cost Electricity, FY-02 Annual Report (October 2001). |
| Abstract |
MIT-ANP-TR-091 |
(Withdrawn) R. Herron, N.E.
Todreas, and P. Hejzlar, Component Design and Capital Cost Analysis
of a Forced Circulation Lead-Bismuth Eutectic Cooled Nuclear Reactor. |
| Abstract |
MIT-ANP-TR-090 |
V. Dostal, M.J.
Driscoll, P. Hejzlar, and N.E. Todreas, CO2 Brayton Cycle
Design and Optimization (November 2002). |
| Abstract |
MIT-ANP-TR-089 |
J.E. Withee and
M.W. Golay, Deterministic Causality Analysis of the Pebble Bed
Modular Reactor for Use with Risk-Based Safety Regulation (August
2002). |
| Abstract |
MIT-ANP-TR-088 |
Y. Okano, P.
Hejzlar, N.E. Todreas, and M.J. Driscoll, Thermal Hydraulics and
Shutdown Cooling of Supercritical CO2 GT-GCFRs (August
2002). |
| Abstract |
MIT-ANP-TR-087 |
M.J. Driscoll, P.
Hejzlar, N.E. Todreas, and B. Veto, Modern GCFR Safety Assurance Considerations (May 2003). |
| Abstract |
MIT-ANP-TR-086 |
K. Yu, M.J.
Driscoll, and P. Hejzlar, Neutronic Evaluation of GCFR Core Diluents (Withdrawn). |
| Abstract |
MIT-ANP-TR-085 |
V. Dostal, N.E.
Todreas, P. Hejzlar, and M.S. Kazimi, Power Conversion Cycle
Selection for the LBE Cooled Reactor with Forced Circulation (February 2002). |
| Abstract |
MIT-ANP-PR-084 |
A.C. Kadak and
R.G. Ballinger et al., Modular Pebble Bed
Reactor Project, Third Annual Report (November 2001). |
| Abstract |
MIT-ANP-PR-083 |
P.E. MacDonald,
N.E. Todreas, and J. Buongiorno et al., Design
of an Actinide Burning, Lead or Lead-Bismuth Cooled Reactor that Produces the
Low Cost Electricity, FY-01 Annual Report (October 2001). |
| Abstract |
MIT-ANP-TR-082 |
V. Dostal, P.
Hejzlar, N.E. Todreas, and M.S. Kazimi, Plant Design and Cost
Assessment of Forced Circulation Lead-Bismuth Cooled Reactor with
Conventional Power Conversion Cycles (September 2001). |
| Abstract |
MIT-ANP-TR-081 |
P. Hejzlar, M.J.
Driscoll, N.E. Todreas, and M.S. Kazimi, Evaluation of a Once-Through
Lead-Bismuth-Cooled Reactor Concept (September 2001). |
| Abstract |
MIT-ANP-TR-080 |
R.G. Ballinger,
J.Y. Lim, and M.S. Kazimi, A Review of US Research Activities on
Material Compatibility Issues in Nuclear Systems Using Heavy Liquid-Metal
Coolant and Needs for Improved Materials (July 2001). |
| Abstract |
MIT-ANP-TR-079 |
J. Buongiorno,
N.E. Todreas, M.S. Kazimi, and K.R. Czerwinski, Conceptual Design of
a Lead-Bismuth Cooled Fast Reactor with In-Vessel Direct-Contact Steam
Generation (March 2001). |
| Abstract |
MIT-ANP-TR-078 |
L.C. Doboe Jr.,
N.E. Todreas, and M.W. Golay, The Role of Uncertain Consequences in
Nuclear Power Investment Decision Making (September 2000). |
| Abstract |
MIT-ANP-TR-077 |
T.A. Galen, D.G.
Wilson, and A.C. Kadak, Comparison Between Air and Helium for Use as
Working Fluids in the Energy-Conversion Cycle of the MPBR (February
2001). |
| Abstract |
MIT-ANP-TR-076 |
D. Kim, N.E.
Todreas, M.S. Kazimi, and M.J. Driscoll, Plant Design and Cost
Estimation of a Natural Circulation Lead-Bismuth Reactor with Helium Power
Conversion Cycle (November 2000). |
| Abstract |
MIT-ANP-PR-075 |
A.C. Kadak and
R.G. Ballinger et al., Modular Pebble Bed
Reactor Project: Second Annual Report (July 2000). |
| Abstract |
MIT-ANP-TR-074 |
D. Kim, N.E.
Todreas, M.S. Kazimi, and M.J. Driscoll, Plant Design and Cost
Estimation of a Natural Circulation Lead-Bismuth Reactor with Steam Power
Conversion Cycle (August 2000). |
| Abstract |
MIT-ANP-TR-073 |
A. Romano, and
N.E. Todreas, Analysis of Novel Fuel Geometries for the Generation IV
"IRIS" Reactor (June 2000). |
| Abstract |
MIT-ANP-TR-072 |
J. Buongiorno, P.
Hejzlar, N.E. Todreas et al., Design of
Lead-Bismuth Cooled Reactors for Actinide Burning and for Low Cost
Electricity (June 2000). |
| Abstract |
MIT-ANP-TR-071 |
A. Romano and
N.E. Todreas, Selection of Correlations and Look-Up Tables for
Critical Heat Flux Prediction in the Generation IV "IRIS" Reactor (June 2000). |
| Abstract |
MIT-ANP-TR-070 |
J.R. Lebenhaft
and M.J. Driscoll, Physics Benchmark Analysis of the HTR-10 Reactor
Using the Monte Carlo Code MCNP (March 2000). |
| Abstract |
MIT-ANP-TR-069 |
P. Hejzlar, M.J.
Driscoll, and M.S. Kazimi, Conceptual Reactor Physics Design of a
Lead-Bismuth-Cooled Critical Actinide Burner (February 2000). |
| Abstract |
MIT-ANP-TR-068 |
P. Hejzlar, M.J.
Driscoll, and M.S. Kazimi, Void Reactivity Performance in
Lead-Bismuth-Cooled Reactor for Actinide Transmutation (August
1999). |
| Abstract |
MIT-ANP-TR-066 |
J. Buongiorno,
N.E. Todreas, and M.S. Kazimi, Thermal Design of Lead-Bismuth Cooled
Reactor for Actinide Burning and Power Production (July 1999). |
| Abstract |
MIT-ANP-TR-065 |
J. Buongiorno, P.
Hejzlar, N.E. Todreas et al., Design of an
Actinide Burning, Lead-Bismuth Cooled Reactor That Produces Low Cost
Electricity (June 1999). |
| Abstract |
MIT-ANP-TR-064 |
K. Tezuka and
M.W. Golay, Reliability-Based Nuclear Power Plant Maintenance
Resource Allocation in Order to Reduce Unfavorable Operational Publicity (June 1999). |
| Abstract |
MIT-ANP-TR-063 |
H. Liu and N.E.
Todreas, A Semi-Passive Containment Cooling System Conceptual Design,
Final Report (March 1999). |
| Abstract |
MIT-ANP-TR-062 |
C.S. Byun, D.W.
Jerng, N.E. Todreas, and M.J. Driscoll, Conceptual Design and
Distributed Parameter Analysis of a Semi-passive Containment Cooling System
for a Large Dry Concrete Containment (February 1999). |
| Abstract |
MIT-ANP-TR-061 |
H-Y. Liu, N.E.
Todreas, and M.J. Driscoll, An Experimental Investigation of A
Passive Cooling Unit for Nuclear Plant Containment (February 1999). |
| Abstract |
MIT-ANP-TR-060 |
M.W. Golay, J.D.
Dulik, F.A. Felder, and S.M. Utton, Project on Integrated Models,
Data Bases and Practices Needed for Performance-Based Safety Regulation,
Final Report (December, 1998). |
| Abstract |
MIT-ANP-TR-059 |
Y.H. Kim, N.E.
Todreas and M.J. Driscoll, Distributed Parameter Modeling of the KNGR
Containment using GOTHIC (January 1998). |
| Abstract |
MIT-ANP-TR-058 |
S. Utton and M.W.
Golay, Risk-Informed, Performance-Based Regulatory Implications of
Improved Emergency Diesel Generator Reliability (January 1998). |
| Abstract |
MIT-ANP-TR-057 |
M.W. Golay, C.W.
Kang, J.B. Lee, and Y. Sui, On-Line Monitoring for Improved Nuclear
Power Plant Availability and Operational Advice, Vols. I, II, & III (February 1998). |
| Abstract |
MIT-ANP-TR-056 |
J.D. Dulik and
M.W. Golay, Use of Performance Monitoring to Improve Reliability of
Emergency Diesel Generators (December 1997). |
| Abstract |
MIT-ANP-TR-055 |
B.T. Mattingly,
N.E. Todreas, and M.J. Driscoll, Containment Analysis Incorporating
Boundary Layer Heat and Mass Transfer Techniques, Part II (February
1999). |
| Abstract |
MIT-ANP-TR-055 |
B.T. Mattingly
and N.E. Todreas, MIT Advanced Containment Project: Review of
Condensation Models and Computer Code Evaluation, Part I (July
1997). |
| Abstract |
MIT-ANP-TR-054 |
Y.H. Kim, N.E.
Todreas, and M.J. Driscoll, Lumped Parameter Modeling of the KNGR
Containment Using GOTHIC (July 1997). |
| Abstract |
MIT-ANP-TR-053 |
M. Leiendecker,
N.E. Todreas, and M.J. Driscoll, Design and Numerical Simulation of a
Two-Phase Thermosyphon Loop as a Passive Containment Cooling System for PWRs,
Rev. 1, Vols. I & II (September 1997). |
| Abstract |
MIT-ANP-TR-052 |
C.W. Kang and
N.E. Todreas, A Strategy for Reducing the Forced Outage Rates of
Reactor Coolant Pumps for a 48-Month Operating Cycle (August 1997). |
| Abstract |
MIT-ANP-TR-051 |
R.S. McHenry and
N.E. Todreas, Nuclear Power Plant Surveillance Issues for Extended
Operating Cycles (February 1997). |
| Abstract |
MIT-ANP-TR-050 |
N.E. Todreas,
M.J. Driscoll, P. Hejzlar, B. Mattingly, and G. Dalporto, Conceptual
Design of a Water Cooled Reactor with Passive Decay Heat Removal, Final
Performance Technical Report (November 1996). |
| Abstract |
MIT-ANP-TR-049 |
C.S. Handwerk,
M.J. Driscoll, N.E. Todreas and M.V. McMahon, Economic Analysis of
Implementing a Four-Year Extended Operating Cycle in Existing PWRs (January 1997). |
| Abstract |
MIT-ANP-TR-048 |
M. Leiendecker,
N.E. Todreas, M.J. Driscoll and A. Hurtado, Passive Containment
Cooling System for Large PWRs Using Thermosyphon Loops (October
1996). |
| Abstract |
MIT-ANP-TR-047 |
J. Automo and
M.W. Golay, Dependency of Human Operator Performance Quality Upon
Task Complexity (September 1996). |
| Abstract |
MIT-ANP-TR-046 |
N.E. Todreas and
M.V. McMahon, Improvement in Nuclear Plant Capacity Factors Through Longer
Cycle Length Operation, Annual Report (July 1996). |
| Abstract |
MIT-ANP-TR-045 |
M.V. McMahon,
M.J. Driscoll, and N.E. Todreas, Modeling and Design of a Reload PWR
Core for a 48-Month Fuel Cycle (July 1996). |
| Abstract |
MIT-ANP-TR-044 |
T.J. Moore and
N.E. Todreas, A Strategy for Reducing Forced Outage Rates in
Commercial Nuclear Reactors with a Main Feed Pump Case Study (July
1996). |
| Abstract |
MIT-ANP-TR-043 |
F. Li and M.W.
Golay, A Study for Improving Reliability and Capacity Factor of the
PWR Feedwater Supply System (June 1996). |
| Abstract |
MIT-ANP-TR-042 |
T.L. Stoops and
M.W. Golay, An Investigation of How Powerful a Nuclear Reactor Can Be (June 1996). |
| Abstract |
MIT-ANP-TR-041 |
H. Masui and M.W.
Golay, Quantitative Methodology for Surveillance Interval Extension
at Nuclear Power Plants (June 1996). |
| Abstract |
MIT-ANP-TR-040 |
J.R. Lunglhofer,
M.W. Golay, and D.D. Lanning, Complete Safety Software Testing: A
Formal Method (January 1996). |
| Abstract |
MIT-ANP-TR-039 |
C.W. Kang, M.
Ouyang, and M.W. Golay, A Mental Procedure for More Reliable
Specification of System Control Software Requirements (December
1995). |
| Abstract |
MIT-ANP-TR-038 |
C. Lapp and M.W.
Golay, A Methodology for Modular Nuclear Power Plant Design and
Construction (October 1995). |
| Abstract |
MIT-ANP-TR-037 |
A.A. Dehbi, M.W.
Golay, and M.S. Kazimi, The Performance Study of the Tube Water Wall
PCCL and an Experimental Correlation for Steam Condensation in the Presence
of Air Under Natural Convection (September 1995). |
| Abstract |
MIT-ANP-TR-036 |
T.J. Moore, J.H.
Maurer, R.S. McHenry, and N.E. Todreas, Surveillance Strategy for a
Four-Year Operating Cycle in Commercial Nuclear Reactors (June
1996). |
| Abstract |
MIT-ANP-TR-035 |
M. Ouyang and
M.W. Golay, An Integrated Formal Approach for Developing High Quality
Software for Safety-Critical Systems (September 1995). |
| Abstract |
MIT-ANP-TR-034 |
M. Gavrilas, N.E.
Todreas, and M.J. Driscoll, Alternative Passive Cooling Concepts for
a Large Rating Pressurized Water Reactor Containment (August 1995). |
| Abstract |
MIT-ANP-TR-033 |
J. Novak, N.E.
Todreas, and M.J. Driscoll, Conception and Experimental Investigation
of Thermal Switches (June 1995). |
| Abstract |
MIT-ANP-TR-032 |
A.F.A. Ayoub and
M.J. Driscoll, A Strategy for Extending Cycle Length to Improve
Pressurized Water Reactor Capacity Factor (June 1995). |
| Abstract |
MIT-ANP-TR-031 |
B.T. Mattingly,
P. Hejzlar, N.E. Todreas, and M.J. Driscoll, Fuel Matrices for the
Passive Pressure Tube Light Water Reactor (March 1995). |
| Abstract |
MIT-ANP-TR-030 |
G. Dalporto and
N.E. Todreas, Achieving Higher Capacity Factors in Nuclear Power
Plants Through Longer Operating Cycles (February 1995). |
| Abstract |
MIT-ANP-TR-029 |
X. Chen and N.E.
Todreas, Thermal Analysis of Dry Spent Fuel Transportation and
Storage Casks (January 1995). |
| Abstract |
MIT-ANP-TR-028 |
M.Ouyang and M.W.
Golay, Comparative Performance Evaluation of an Advanced Semi-Passive
and an Evolutionary Pressurized Water Reactor Nuclear Power Plants in the
Loss of Offsite Power Event (December 1994). |
| Abstract |
MIT-ANP-TR-027 |
J.T. Hwang, N.E.
Todreas, and M.J. Driscoll, Experimental Evaluation of a Passive
Water Cooled Containment Concept (August 1994). |
| Abstract |
MIT-ANP-TR-026 |
E.M. Hermanson
and M.W. Golay, The Dependence of Human Reliability Upon Task
Information Content (August 1994). |
| Abstract |
MIT-ANP-TR-025 |
P. Hejzlar, N.E.
Todreas, and M.J. Driscoll, Technical Summary of a Conceptual Design
of a Large, Passive Pressure-Tube Light Water Reactor (July 1994). |
| Abstract |
MIT-ANP-TR-024 |
H.A. Hasanein,
M.W. Golay, and M.S. Kazimi, Steam Condensation in the Presence of
Noncondensable Gases under Forced Convection Conditions (July 1994). |
| Abstract |
MIT-ANP-TR-023 |
P. Hejzlar, N.E.
Todreas, and M.J. Driscoll, Conceptual Design of a Large, Passive
Pressure-Tube Light Water Reactor (June 1994). |
| Abstract |
MIT-ANP-TR-022 |
M.G. Arno and
M.W. Golay, Verification and Validation of Safety Related Software (June 1994). |
| Abstract |
MIT-ANP-TR-021 |
P. Hejzlar, N.E.
Todreas, and M.J. Driscoll, Special Computer Codes and Supplementary
Data for the Conceptual Design of a Large, Passive, Pressure-tube LWR (May 1994). |
| Abstract |
MIT-ANP-TR-020 |
A.R. Patel, N.E.
Todreas, and M.J. Driscoll, Integrated Containment/Hyperbolic Cooling
Tower System (January 1994). |
| Abstract |
MIT-ANP-TR-019 |
K.E. Poorman,
M.W. Golay, and D.D. Lanning, On the Complete Testing of Simple,
Safety-Related Software (February 1994). |
| Abstract |
MIT-ANP-TR-018 |
H. Khan and M.J.
Driscoll, An Evaluation of Passive Spray Cooling for Nuclear Reactor
Containments (September 1993). |
| Abstract |
MIT-ANP-TR-017 |
P. Hejzlar, N.E.
Todreas, and M.J. Driscoll, Evaluation of Materials for the Pressure
Tube Matrix of a Passive LWR Concept (November 1993). |
| Abstract |
MIT-ANP-TR-016 |
P. Hejzlar, N.E.
Todreas, M.J. Driscoll, and B. Mattingly, Conceptual Design of a
Water Cooled Reactor with Passive Decay Heat Removal, DOE Progress Report (May 1993). |
| Abstract |
MIT-ANP-TR-015 |
C.H. Kang and
M.S. Kazimi, Transmutation Effects on Transuranic Waste Inventory and
Its Repository Risk (March 1993). |
| Abstract |
MIT-ANP-TR-014 |
A. Schneider and
D. Freed, Integral Fast Reactor-Related ResearchÇ Subtask 1C:
Analysis of IFR Demonstration Program, Final Report (June 1992). |
| Abstract |
MIT-ANP-TR-013 |
J.R. Tang, N.E.
Todreas, and M.J. Driscoll, Conceptual Design of the Passive Light
Water Cooled and Moderated Pressure Tube Reactor (PLPTR), Volumes I and II (August 1992). |
| Abstract |
MIT-ANP-TR-012 |
W.W. Schenler and
M.W. Golay, ORNL/MIT Technical Support Tasks for USDOE/MITNE Integral
Fast Reactor Program: Task 2, Environmental Impact Assessment (May
1992). |
| Abstract |
MIT-ANP-TR-011 |
N.S. Qureshi and
M.W. Golay, A Sensitivity Analysis of the Role of Human Actions for
the Loss of Offsite Power Scenario (May 1992). |
| Abstract |
MIT-ANP-TR-010 |
M. Siddique, M.W.
Golay, and M.S. Kazimi, The Effects of Noncondensable Gases on Steam
Condensation under Turbulent Natural Convection Conditions (March
1992). |
| Abstract |
MIT-ANP-TR-009 |
J.R. Tang, M.J.
Driscoll, and N.E. Todreas, Physics Considerations in a Passive Light
Water Pressure Tube Reactor (PLPTR) (November 1991). |
| Abstract |
MIT-ANP-TR-008 |
J.R. Tang, N.E.
Todreas, and M.J. Driscoll, Concepts for a Pressure Tube Light Water
Reactor with Passive Safety Features (September 1991). |
| Abstract |
MIT-ANP-TR-007 |
W.R. Hollaway and
L.M. Lidsky, The Combined Hybrid System Ç A Symbiotic Thermal
Reactor/Fast Reactor System for Power Generation and Radioactive Waste
Toxicity Reduction (August 1991). |
| Abstract |
MIT-ANP-TR-006 |
A.A. Dehbi, M.W.
Golay, and M.S. Kazimi, Passive Containment Cooling for a 900 MWe
Reactor (August 1991). |
| Abstract |
MIT-ANP-TR-005 |
J-C Han, M.J.
Driscoll and N.E. Todreas, The Effect of Thermal Conductivity of
Prismatic MHTGR Fuel (September 1989). |
| Abstract |
MIT-ANP-TR-004 |
A.A. Dehbi, M.W.
Golay, and M.S. Kazimi, The Effects of Non-Condensable Gases on Steam
Condensation under Turbulent Natural Convection Conditions (June
1991). |
| Abstract |
MIT-ANP-TR-003 |
P. Hejzlar, N.E.
Todreas, and M.J. Driscoll, Passive Decay Heat Removal in Advanced
Reactor Concepts, Vols I & II (May 1991). |
| Abstract |
MIT-ANP-TR-002 |
M.G. Houts and
D.D. Lanning, Out-of-Core Thermionic Space Nuclear Reactors: Design
and Control Considerations (January 1991). |
| Abstract |
MIT-ANP-TR-001 |
W.R. Hollaway,
L.M. Lidsky, and M.M. Miller, The Role of Actinide Burning and the
Integral Fast Reactor in the Future of Nuclear Power (December
1990). |
