'Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)' хайлтад зориулсан 34-н үр дүнгүүд 1 - 20-г харуулж байна, асуулгын хугацаа: 0.04s
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Investigation of Pressure-Tube and Calandria-Tube Deformation Following a Single Channel Blockage Event in ACR-700 -н Gerardi, Craig Douglas, Buongiorno, Jacopo
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
2
Effective Thermal Conductivity of Prismatic MHTGR Fuel -н Han, J. C., Driscoll, M. J., Todreas, N. E.
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
3
Conceptual Design of a Large, Passive Pressure-Tube Light Water Reactor -н Hejzlar, P., Todreas, N. E., Driscoll, M. J.
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
4
Conceptual Design of a Large, Passive Pressure-Tube Light Water Reactor -н Hejzlar, P., Todreas, N. E., Driscoll, M. J.
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
5
An Integrated Formal Approach for Developing High Quality Software for Safety-Critical Systems -н Ouyang, Meng, Golay, Michael W.
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
6
Use of Performance Monitoring to Improve Reliability of Emergency Generators Diesel -н Dulik, J. D., Golay, M. W.
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
7
Risk-Informed, Performance-Based Regulatory Implications of Improved Emergency Diesel Generator Reliability -н Utton, S., Golay, M. W.
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
8
A Semi-Passive Containment Cooling System Conceptual Design -н Liu, H., Todreas, N. E., Driscoll, M. J., Byun, C. S., Kim, Y. H., Grodzinsky, M.
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
9
Conceptual Reactor Physics Design of a Lead-Bismuth-Cooled Critical Actinide Burner -н Hejzlar, Pavel, Driscoll, Michael J., Kazimi, Mujid S.
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
10
MCNP4B Modeling of Pebble-Bed Reactors -н Lebenhaft, Julian Robert
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
11
Plant Design and Cost Estimation of a Natural Circulation Lead-Bismuth Reactor with Steam Power Conversion Cycle -н Kim, D., Todreas, N. E., Kazimi, Mujid S., Driscoll, M. J.
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
12
Modular Pebble Bed Reactor -н Kadak, Andrew C., Ballinger, Ronald G., Driscoll, Michael J., Yip, Sidney, Wilson, David Gordon, No, Hee Cheon, Wang, Jing, MacLean, Heather, Galen, Tamara, Wang, Chunyun, Lebenhaft, Julian, Zhai, Tieliang, Petti, David A., Terry, William K., Gougar, Hans D., Ougouag, Abderrafi M., Oh, Chang H., Moore, Richard L., Miller, Gregory K., Maki, John T., Smolik, Galen R., Varacalle, Dominic J.
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
13
Plant Design and Cost Estimation of a Natural Circulation Lead-Bismuth Reactor with Helium Power Conversion Cycle -н Kim, D., Todreas, N. E., Kazimi, Mujid S., Driscoll, M. J.
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
14
Comparison Between Air and Helium for Use as Working Fluids in the Energy-Conversion Cycle of the MPBR -н Galen, T. A., Wilson, D. G., Kadak, A. C.
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
15
Conceptual Design of a Lead-Bismuth Cooled Fast Reactor with In-Vessel Direct-Contact Steam Generation -н Buongiorno, J., Todreas, N. E, Kazimi, Mujid S., Czerwinski, K. R.
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
16
Plant Design and Cost Assessment of Forced Circulation Lead-Bismuth Cooled Reactor with Conventional Power Conversion Cycles -н Dostal, Vaclav, Hejzlar, Pavel, Todreas, Neil E., Kazimi, Mujid S.
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
17
A Super Critical Carbon Dioxide Cycle for Next Generation Nuclear Reactors -н Dostal, Vaclav, Driscoll, Michael J., Hejzlar, Pavel
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
18
Design of Compact Intermediate Heat Exchangers for Gas Cooled Fast Reactors -н Gezelius, K., Driscoll, Michael J. ;, Hejzlar, Pavel
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
19
Analysis Of Flow Instabilities In Supercritical Watercooled Nuclear Reactors -н Zhao, J., Saha, P., Kazimi, Mujid S.
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report -
20
Using Risk-Based Regulations for Licensing Nuclear Power Plants: Case Study of the Gas-cooled Fast Reactor -н Jourdan, G., Golay, M. W.
Хэвлэсэн 2011Бусад зохиолчид: “…Advanced Nuclear Power Technology Program (Massachusetts Institute of Technology)…”
Technical Report