-
1
-
-
2342626275
-
Steam-water power reactor concept
-
July
-
Alekseev, P.N., Grishnanin, E.I., Zverkov, Yu.A. et al., 1989. Steam-water power reactor concept, Soviet-Japanese Seminar on Theoretical, Computational and Experimental Study of Physical Problems in Designing of Fast Reactors, July, pp. 90-97.
-
(1989)
Soviet-Japanese Seminar on Theoretical, Computational and Experimental Study of Physical Problems in Designing of Fast Reactors
, pp. 90-97
-
-
Alekseev, P.N.1
Grishnanin, E.I.2
Zverkov, Yu.A.3
-
2
-
-
2342530675
-
-
Report WCAP-2040, Westinghouse Electric Corporation, Atomic Power Department, Pittsburgh, Pennsylvania, USA, December
-
Bishop, A.A., Efferding, L.E., Tong, L.S., 1962. A review of heat transfer and fluid flow of water in the supercritical region and during "once-through" operation, Report WCAP-2040, Westinghouse Electric Corporation, Atomic Power Department, Pittsburgh, Pennsylvania, USA, December.
-
(1962)
A Review of Heat Transfer and Fluid Flow of Water in the Supercritical Region and during "Once-through" Operation
-
-
Bishop, A.A.1
Efferding, L.E.2
Tong, L.S.3
-
3
-
-
0012290931
-
-
Report WCAP-2056, Part IV, November, Westinghouse Electric Corp., Pittsburgh, USA
-
Bishop, A.A., Sandberg, R.O., Tong, L.S., 1964. Forced convection heat transfer to water at near-critical temperatures and supercritical pressures, Report WCAP-2056, Part IV, November, Westinghouse Electric Corp., Pittsburgh, USA.
-
(1964)
Forced Convection Heat Transfer to Water at Near-critical Temperatures and Supercritical Pressures
-
-
Bishop, A.A.1
Sandberg, R.O.2
Tong, L.S.3
-
4
-
-
84984088228
-
Heat transfer in the critical region
-
Bringer R.P., Smith J.M. Heat transfer in the critical region. AIChE J. 3(1):1957;49-55.
-
(1957)
AIChE J.
, vol.3
, Issue.1
, pp. 49-55
-
-
Bringer, R.P.1
Smith, J.M.2
-
5
-
-
0020732416
-
Relative increase in heat transfer in viscous-inertial regimes of flow of helium at supercritical pressure in a heated tube
-
Bogachev, V.A., Eroshenko, V.M., Yaskin, L.A., 1983. Relative increase in heat transfer in viscous-inertial regimes of flow of helium at supercritical pressure in a heated tube. J. Eng.-Phys. ( ), cTp. 544-548), 44 (4) 363-366.
-
(1983)
J. Eng.-phys.
, vol.44
, Issue.4
, pp. 363-366
-
-
Bogachev, V.A.1
Eroshenko, V.M.2
Yaskin, L.A.3
-
6
-
-
2342653860
-
Conceptual design for a supercritical-water-cooled CANDU
-
Global'99: Nuclear Technology: Bridging the Millennia. Jackson Hole, Wyoming, USA, August 29-September 3, Paper 103
-
Bushby, S.J., Dimmick, G.R., Duffey, R.B. et al., 1999. Conceptual design for a supercritical-water-cooled CANDU. In: Proceedings of the International Conference on Future Nuclear Systems, Global'99: Nuclear Technology: Bridging the Millennia. Jackson Hole, Wyoming, USA, August 29-September 3, Paper 103.
-
(1999)
Proceedings of the International Conference on Future Nuclear Systems
-
-
Bushby, S.J.1
Dimmick, G.R.2
Duffey, R.B.3
-
7
-
-
77952821826
-
Conceptual designs for advanced, high-temperature CANDU reactors
-
Tokyo, Japan, November 6-8, Paper 103
-
Bushby, S.J., Dimmick, G.R., Duffey, R.B. et al., 2000. Conceptual designs for advanced, high-temperature CANDU reactors. In: Proceedings of the First International Symposium on Supercritical Water-Cooled Reactor Design and Technology (SCR-2000), Tokyo, Japan, November 6-8, Paper 103.
-
(2000)
Proceedings of the First International Symposium on Supercritical Water-cooled Reactor Design and Technology (SCR-2000)
-
-
Bushby, S.J.1
Dimmick, G.R.2
Duffey, R.B.3
-
8
-
-
4644232901
-
-
Forschungszentrum Karlsruhe, Technik und Umwelt, Wissenschaftliche Berichte, FZKA 6609, Institute für Kern- und Energietechnik, Mai 2001
-
Cheng, X., Schulenberg, T., 2001. Heat transfer at supercritical pressures-literature review and application to a HPLWR, Forschungszentrum Karlsruhe, Technik und Umwelt, Wissenschaftliche Berichte, FZKA 6609, Institute für Kern- und Energietechnik, Mai 2001.
-
(2001)
Heat Transfer at Supercritical Pressures-literature Review and Application to a HPLWR
-
-
Cheng, X.1
Schulenberg, T.2
-
9
-
-
85135754233
-
Heat transfer to supercritical water
-
Dickinson N.L., Welch C.P. Heat transfer to supercritical water. Trans. of ASME. 80:1958;746-752.
-
(1958)
Trans. of ASME
, vol.80
, pp. 746-752
-
-
Dickinson, N.L.1
Welch, C.P.2
-
10
-
-
0006031535
-
An advanced CANDU reactor with supercritical water coolant: Conceptual design features
-
San Diego, California, USA, May 10-15, Paper-6501
-
Dimmick, G.R., Spinks, N.J., Duffey, R., 1998. An advanced CANDU reactor with supercritical water coolant: conceptual design features, Proceedings of the Sixth International Conference on Nuclear Engineering (ICONE-6), San Diego, California, USA, May 10-15, Paper-6501.
-
(1998)
Proceedings of the Sixth International Conference on Nuclear Engineering (ICONE-6)
-
-
Dimmick, G.R.1
Spinks, N.J.2
Duffey, R.3
-
11
-
-
0000816785
-
-
University of California Publications in English, Berkeley
-
Dittus, F.W., Boelter, L.M.K., 1930. Heat Transfer in Automobile Radiators of the Tubular Type, University of California Publications in English, Berkeley, vol. 2, pp. 443-461.
-
(1930)
Heat Transfer in Automobile Radiators of the Tubular Type
, vol.2
, pp. 443-461
-
-
Dittus, F.W.1
Boelter, L.M.K.2
-
12
-
-
14844313262
-
Conceptual design of a high temperature power reactor cooled and moderated by supercritical water
-
San Diego, California, USA, May 10-15, Paper 6232
-
Dobashi, K., Oka, Y., Koshizuka, S., 1998. Conceptual design of a high temperature power reactor cooled and moderated by supercritical water. In: Proceedings of the Sixth International Conference on Nuclear Engineering (ICONE-6), San Diego, California, USA, May 10-15, Paper 6232.
-
(1998)
Proceedings of the Sixth International Conference on Nuclear Engineering (ICONE-6)
-
-
Dobashi, K.1
Oka, Y.2
Koshizuka, S.3
-
13
-
-
2342639912
-
Wärmeübergang in kritischen und überkritischen Bereichen von Wasser in Rohren
-
Domin G. Wärmeübergang in kritischen und überkritischen Bereichen von Wasser in Rohren. Brennstoff-Warme-Fraft (BWK). 15(11):1963;527-532.
-
(1963)
Brennstoff-warme-fraft (BWK)
, vol.15
, Issue.11
, pp. 527-532
-
-
Domin, G.1
-
14
-
-
2342614518
-
Heat transfer and thermal resistance of tight seven-rod bundle, cooled with water flow at supercritical pressures
-
in Russian
-
Dyadyakin, B.V., Popov, A.S., 1977. Heat transfer and thermal resistance of tight seven-rod bundle, cooled with water flow at supercritical pressures, (in Russian). Trans. All-Union Heat Eng. Inst. ( ) 11, 244-253.
-
(1977)
Trans. All-union Heat Eng. Inst.
, vol.11
, pp. 244-253
-
-
Dyadyakin, B.V.1
Popov, A.S.2
-
15
-
-
2342570621
-
Description and evaluation of candidate water-cooled reactor systems
-
Technical Working Group 1-Advanced Water Reactors, Report, September 12
-
Generation IV Nuclear Energy Systems Roadmap, 2001. Description and evaluation of candidate water-cooled reactor systems, Technical Working Group 1-Advanced Water Reactors, Report, September 12.
-
(2001)
Generation IV Nuclear Energy Systems Roadmap
-
-
-
16
-
-
2342450275
-
-
1766, Institute of Physics and Power Engineering, Obninsk, Russia
-
Gorban', L.M., Pomet'ko, R.S., Khryaschev, O.A., 1990. Modeling of water heat transfer with Freon of supercritical pressure, (in Russian). -1766, Institute of Physics and Power Engineering ( ), Obninsk, Russia.
-
(1990)
Modeling of Water Heat Transfer with Freon of Supercritical Pressure, (in Russian)
-
-
Gorban, L.M.1
Pomet'ko, R.S.2
Khryaschev, O.A.3
-
17
-
-
0038651625
-
A European development program for a high performance light water reactor (HPLWR)
-
Tokyo, Japan, November 6-8, Paper 102
-
Heusener, G., Muller, U., Schulenberg, T., Squarer, D., 2000. A European development program for a high performance light water reactor (HPLWR). In: Proceedings of the First Internatiopnal Symposium on Supercritical Water-Cooled Reactor Design and Technology (SCR-2000), Tokyo, Japan, November 6-8, Paper 102.
-
(2000)
Proceedings of the First Internatiopnal Symposium on Supercritical Water-cooled Reactor Design and Technology (SCR-2000)
-
-
Heusener, G.1
Muller, U.2
Schulenberg, T.3
Squarer, D.4
-
18
-
-
2342590404
-
-
Taylor & Francis, New York, NY, USA
-
Hewitt, G.F., Collier, J.G., 2000. Introduction to Nuclear Power, 2nd ed., Taylor & Francis, New York, NY, USA, pp. 40, 67, 68.
-
(2000)
Introduction to Nuclear Power, 2nd Ed.
, pp. 40
-
-
Hewitt, G.F.1
Collier, J.G.2
-
20
-
-
2342528776
-
Consideration of the heat transfer properties of supercritical pressure water in connection with the cooling of advanced nuclear reactors
-
Shenzhen City, China, October 21-25
-
Jackson, J.D., 2002. Consideration of the heat transfer properties of supercritical pressure water in connection with the cooling of advanced nuclear reactors. In: Proceedings of the 13th Pacific Basin Nuclear Conference, Shenzhen City, China, October 21-25.
-
(2002)
Proceedings of the 13th Pacific Basin Nuclear Conference
-
-
Jackson, J.D.1
-
22
-
-
0018310602
-
Forced convection heat transfer to fluids at supercritical pressure
-
Kakaç, S., Spalding, D.B. (Eds.). Hemisphere Publishing Corp., New York, USA
-
Jackson, J.D., Hall, W.B., 1979. Forced convection heat transfer to fluids at supercritical pressure. In: Kakaç, S., Spalding, D.B. (Eds.), Turbulent Forced Convection in Channels and Bundles, vol. 2. Hemisphere Publishing Corp., New York, USA, pp. 563-612.
-
(1979)
Turbulent Forced Convection in Channels and Bundles
, vol.2
, pp. 563-612
-
-
Jackson, J.D.1
Hall, W.B.2
-
23
-
-
2342515105
-
Design of an indirect-cycle fast breeder reactor cooled by supercritical steam
-
Jevremovich T., Oka Y., Koshizuka S. Design of an indirect-cycle fast breeder reactor cooled by supercritical steam. Nucl. Eng. Des. 144:1993;337-344.
-
(1993)
Nucl. Eng. Des.
, vol.144
, pp. 337-344
-
-
Jevremovich, T.1
Oka, Y.2
Koshizuka, S.3
-
24
-
-
68349120833
-
Heat and mass transfer at supercritical parameters (The short review of researches in Russia. Theory and experiments)
-
Tokyo, Japan, November 6-8, Paper 105
-
Kirillov, P.L., 2000. Heat and mass transfer at supercritical parameters (The short review of researches in Russia. Theory and experiments), In: Proceedings of the First International Symposium on Supercritical Water-Cooled Reactor Design and Technology (SCR-2000), Tokyo, Japan, November 6-8, Paper 105.
-
(2000)
Proceedings of the First International Symposium on Supercritical Water-cooled Reactor Design and Technology (SCR-2000)
-
-
Kirillov, P.L.1
-
25
-
-
0004296727
-
-
Energoatomizdat Publishing House, Moscow, Russia
-
Kirillov, P.L., Yur'ev, Yu.S., Bobkov, V.P., 1990. Handbook of Thermal-Hydraulics Calculations, (in Russian), Energoatomizdat Publishing House, Moscow, Russia, pp. 66-67, 130-132.
-
(1990)
Handbook of Thermal-hydraulics Calculations, (in Russian)
, pp. 66-67
-
-
Kirillov, P.L.1
Yur'ev, Yu.S.2
Bobkov, V.P.3
-
26
-
-
0006705475
-
Refinement of transient criteria and safety analysis for a high temperature reactor cooled by supercritical water
-
Tokyo, Japan, April 19-23, Paper-7234
-
Kitoh, K., Koshizuka, S., Oka, Yo., 1999. Refinement of transient criteria and safety analysis for a high temperature reactor cooled by supercritical water. In: Proceedings of the Seventh International Conference on Nuclear Engineering (ICONE-7), Tokyo, Japan, April 19-23, Paper-7234.
-
(1999)
Proceedings of the Seventh International Conference on Nuclear Engineering (ICONE-7)
-
-
Kitoh, K.1
Koshizuka, S.2
Oka, Y.3
-
27
-
-
2342487648
-
Heat transfer and hydraulic resistance with supercritical water flowing in tubes
-
Kondrat'ev N.S. Heat transfer and hydraulic resistance with supercritical water flowing in tubes. Thermal Eng. (., cTp. 49-51) 16(8):1969;73-77.
-
(1969)
Thermal Eng.
, vol.16
, Issue.8
, pp. 73-77
-
-
Kondrat'ev, N.S.1
-
28
-
-
2342618523
-
Heat transfer at supercritical region in flow of carbon dioxide and water in tubes
-
Krasnoshchekov, E.A., Protopopov, V.S., 1959. Heat transfer at supercritical region in flow of carbon dioxide and water in tubes, (In Russian). Thermal Eng. ( ) 12, 26-30.
-
(1959)
Thermal Eng.
, vol.12
, pp. 26-30
-
-
Krasnoshchekov, E.A.1
Protopopov, V.S.2
-
29
-
-
2342622392
-
About heat transfer in flow of carbon dioxide and water at supercritical region of state parameters
-
Krasnoshchekov, E.A., Protopopov, V.S., 1960. About heat transfer in flow of carbon dioxide and water at supercritical region of state parameters, (in Russian). Thermal Eng. ( ) 10, 94.
-
(1960)
Thermal Eng.
, vol.10
, pp. 94
-
-
Krasnoshchekov, E.A.1
Protopopov, V.S.2
-
30
-
-
0000674489
-
Experimental study of heat exchange in carbon dioxide in the supercritical range at high temperature drops
-
Krasnoshchekov E.A., Protopopov V.S. Experimental study of heat exchange in carbon dioxide in the supercritical range at high temperature drops. High Temperatures (., cTp. 389-398) 4(3):1966;375-382.
-
(1966)
High Temperatures
, vol.4
, Issue.3
, pp. 375-382
-
-
Krasnoshchekov, E.A.1
Protopopov, V.S.2
-
31
-
-
2342481462
-
Some results of an experimental investigation of heat transfer to carbon dioxide at supercritical pressure and temperature heads of up to 850°C
-
Krasnoshchekov E.A., Protopopov V.S., Parkhovnik I.A., Silin V.A. Some results of an experimental investigation of heat transfer to carbon dioxide at supercritical pressure and temperature heads of up to 850°C. High Temperatures (., cTp. 1081-1084) 9(5):1971;992-995.
-
(1971)
High Temperatures
, vol.9
, Issue.5
, pp. 992-995
-
-
Krasnoshchekov, E.A.1
Protopopov, V.S.2
Parkhovnik, I.A.3
Silin, V.A.4
-
32
-
-
0013771634
-
Experimental investigation of heat transfer for carbon dioxide in the supercritical region
-
Gazley, Jr., C., Hartnett, J.P., Ecker, E.R.C. (Eds.), Minsk, Belarus, May, 1964, Published as Rand Report R-451-PR
-
Krasnoshchekov, E.A., Protopopov, V.S., Van Fen and Kuraeva, I.V., 1967. Experimental investigation of heat transfer for carbon dioxide in the supercritical region. In: Gazley, Jr., C., Hartnett, J.P., Ecker, E.R.C. (Eds.), Proceedings of the Second All-Soviet Union Conference on Heat and Mass Transfer, Minsk, Belarus, May, 1964, Published as Rand Report R-451-PR, vol. 1, pp. 26-35.
-
(1967)
Proceedings of the Second All-Soviet Union Conference on Heat and Mass Transfer
, vol.1
, pp. 26-35
-
-
Krasnoshchekov, E.A.1
Protopopov, V.S.2
Van Fen3
Kuraeva, I.V.4
-
33
-
-
0003243454
-
Supercritical fluids: Their properties and applications
-
Kiran, E. et al. (Eds.), Supercritical Fluids. NATO Advanced Study Institute on Supercritical Fluids - Fundamentals and Application, Kluwer Academic Publishers, The Netherlands (Chapter 1)
-
Levelt Sengers, J.M.H.L., 2000. Supercritical fluids: their properties and applications. In: Kiran, E., et al. (Eds.), Supercritical Fluids. NATO Advanced Study Institute on Supercritical Fluids - Fundamentals and Application, NATO Science Series, Series E, Applied Sciences, Kluwer Academic Publishers, The Netherlands, vol. 366. pp. 1-29 (Chapter 1).
-
(2000)
NATO Science Series, Series E, Applied Sciences
, vol.366
, pp. 1-29
-
-
Levelt Sengers, J.M.H.L.1
-
34
-
-
2342511253
-
-
Report ANL-6202, Argonne National Laboratory, August
-
Marchaterre, J.F., Petrick, M., 1960. Review of the status of supercritical water reactor technology, Report ANL-6202, Argonne National Laboratory, August.
-
(1960)
Review of the Status of Supercritical Water Reactor Technology
-
-
Marchaterre, J.F.1
Petrick, M.2
-
35
-
-
0004268517
-
-
McGraw-Hill, New York, NY, USA
-
McAdams, W.H., 1942. Heat Transmission, 2nd edition, McGraw-Hill, New York, NY, USA.
-
(1942)
Heat Transmission, 2nd Edition
-
-
McAdams, W.H.1
-
36
-
-
85136986657
-
Heat transfer to superheated steam at high pressures
-
McAdams W.H., Kennel W.E., Addoms J.N. Heat transfer to superheated steam at high pressures. Trans. ASME. 72(4):1950;421-428.
-
(1950)
Trans. ASME
, vol.72
, Issue.4
, pp. 421-428
-
-
McAdams, W.H.1
Kennel, W.E.2
Addoms, J.N.3
-
37
-
-
2342475453
-
Heat transfer with a flow of medium at supercritical pressure in curvilinear channels
-
Miropol'skii Z.L., Pikus V.Yu., Kovalevskii V.B. Heat transfer with a flow of medium at supercritical pressure in curvilinear channels. Thermal Eng. (cTp. 70-72) 17(11):1970;101-104.
-
(1970)
Thermal Eng.
, vol.17
, Issue.11
, pp. 101-104
-
-
Miropol'skii, Z.L.1
Pikus, V.Yu.2
Kovalevskii, V.B.3
-
38
-
-
0347542649
-
Heat transfer to water and steam at variable specific heat (at near-critical region) (in Russian)
-
Miropol'skii Z.L., Shitsman M.E. Heat transfer to water and steam at variable specific heat (at near-critical region) (in Russian). J. Tech. Phys. (. ) XXVII(10):1957;2359-2372.
-
(1957)
J. Tech. Phys.
, vol.27
, Issue.10
, pp. 2359-2372
-
-
Miropol'skii, Z.L.1
Shitsman, M.E.2
-
39
-
-
2342526855
-
Investigation of heat transfer to water and steam at pressures up to 280 ata
-
Dollezhal' N.A. (Ed.). Atomizdat Publishing House, Moscow, Russia
-
Miropol'skii, Z.L., Shitsman, M.E., 1958. Investigation of heat transfer to water and steam at pressures up to 280 ata, (in Russian). In: Dollezhal' N.A. (Ed.), Investigation of Heat Transfer to Steam and Water Boiling in Tubes at High Pressures. Atomizdat Publishing House, Moscow, Russia, pp. 54-70.
-
(1958)
Investigation of Heat Transfer to Steam and Water Boiling in Tubes at High Pressures
, pp. 54-70
-
-
Miropol'skii, Z.L.1
Shitsman, M.E.2
-
40
-
-
2342586363
-
About calculation methods of heat transfer to water and steam at near-critical region
-
Miropol'skii, Z.L., Shitsman, M.E., 1958. About calculation methods of heat transfer to water and steam at near-critical region. (in Russian). Soviet Energy Technology ( ), vol. 1. pp. 8-11.
-
(1958)
Soviet Energy Technology
, vol.1
, pp. 8-11
-
-
Miropol'Skii, Z.L.1
Shitsman, M.E.2
-
41
-
-
0003423899
-
NIST/ASME Steam Properties
-
(on diskette: executable with source), Ver. 2.2, U.S. Department of Commerce
-
NIST/ASME Steam Properties, 1996. NIST Standard Reference Database 10 (on diskette: executable with source). In: Harvey, A.H., Peskin, A.P., Klein, S.A. (Eds.), Ver. 2.2, U.S. Department of Commerce.
-
(1996)
NIST Standard Reference Database
, vol.10
-
-
Harvey, A.H.1
Peskin, A.P.2
Klein, S.A.3
-
42
-
-
0003423899
-
NIST/ASME Steam Properties
-
(on diskette: executable with source), Ver. 2.11., U.S. Department of Commerce
-
NIST/ASME Steam Properties, 1997. NIST Standard Reference Database 10 (on diskette: executable with source), Ver. 2.11. In: Harvey, A.H., Peskin, A.P., Klein, S.A. (Eds.), U.S. Department of Commerce.
-
(1997)
NIST Standard Reference Database
, vol.10
-
-
Harvey, A.H.1
Peskin, A.P.2
Klein, S.A.3
-
43
-
-
54249090159
-
NIST Reference Fluid Thermodynamic and Transport Properties - REFPROP
-
(on diskette: Executable with Source), Ver. 7.0. U.S. Department of Commerce, August
-
NIST Reference Fluid Thermodynamic and Transport Properties - REFPROP. In: Lemmon, E.W., McLinden, M.O., Huber, M.L. (Eds.), NIST Standard Reference Database 23 (on diskette: Executable with Source), Ver. 7.0. U.S. Department of Commerce, August 2002.
-
(2002)
NIST Standard Reference Database
, vol.23
-
-
Lemmon, E.W.1
McLinden, M.O.2
Huber, M.L.3
-
44
-
-
0040707492
-
Development of ultra super critical PF power plants in Denmark
-
Houston, Texas, USA, September 13-18
-
Noer, M., Kjaer, S., 1998. Development of ultra super critical PF power plants in Denmark. In: Proceedings of the Seventeenth Congress of the World Energy Council, Houston, Texas, USA, September 13-18, pp. 295-311.
-
(1998)
Proceedings of the Seventeenth Congress of the World Energy Council
, pp. 295-311
-
-
Noer, M.1
Kjaer, S.2
-
45
-
-
0041035420
-
Review of high temperature water and steam cooled reactor concepts
-
Tokyo, Japan, November 6-8, Paper 104
-
Oka, Y., 2000. Review of high temperature water and steam cooled reactor concepts. In: Proceedings of the First International Symposium on Supercritical Water-Cooled Reactor Design and Technology (SCR-2000), Tokyo, Japan, November 6-8, Paper 104.
-
(2000)
Proceedings of the First International Symposium on Supercritical Water-cooled Reactor Design and Technology (SCR-2000)
-
-
Oka, Y.1
-
46
-
-
0027666626
-
Concept and design of a supercritical-pressure, direct-cycle light water cooled reactor
-
Oka, Yo., Koshizuka, S., 1993. Concept and design of a supercritical-pressure, direct-cycle light water cooled reactor. Nucl. Technol. 103, 295-302.
-
(1993)
Nucl. Technol.
, vol.103
, pp. 295-302
-
-
Oka, Y.1
Koshizuka, S.2
-
47
-
-
2342538730
-
Status and prospects of high temperature (supercritical-pressure) light water cooled reactor research and development
-
Shenzhen City, China, October 21-25
-
Oka, Yo., Koshizuka, S., 2002. Status and prospects of high temperature (supercritical-pressure) light water cooled reactor research and development. In: Proceedings of the Thirteenth Pacific Basin Nuclear Conference, Shenzhen City, China, October 21-25.
-
(2002)
Proceedings of the Thirteenth Pacific Basin Nuclear Conference
-
-
Oka, Y.1
Koshizuka, S.2
-
48
-
-
0000501132
-
Design concepts of light water cooled rectors operating at supercritical pressure for technological innovation
-
Kobe, Japan, October 20-25
-
Oka, Y., Koshizuka, S., Okano, Y., et al. 1996. Design concepts of light water cooled rectors operating at supercritical pressure for technological innovation. In: Proceedings of the Tenth Pacific Basin Nuclear Conference, Kobe, Japan, October 20-25.
-
(1996)
Proceedings of the Tenth Pacific Basin Nuclear Conference
-
-
Oka, Y.1
Koshizuka, S.2
Okano, Y.3
-
49
-
-
2342639911
-
The research of temperature conditions of small diameter parallel tubes cooled by water under supercritical pressures
-
Paper B 8.11, Elsevier, Amsterdam
-
Ornatsky, A.P., Glushchenko, L.P., Siomin, E.T., et al. 1970. The research of temperature conditions of small diameter parallel tubes cooled by water under supercritical pressures. In: Proceedings of the Fourth International Heat Transfer Conference, Paris-Versailles, France, vol. VI. Paper B 8.11, Elsevier, Amsterdam.
-
(1970)
Proceedings of the Fourth International Heat Transfer Conference, Paris-Versailles, France
, vol.6
-
-
Ornatsky, A.P.1
Glushchenko, L.P.2
Siomin, E.T.3
-
50
-
-
0015434975
-
An experimental study of heat transfer in externally-heated annuli at supercritical pressures
-
Ornatskiy A.P., Glushchenko L.F., Gandzyuk O.F. An experimental study of heat transfer in externally-heated annuli at supercritical pressures. Heat Transfer Soviet Res. 4(6):1972;25-29.
-
(1972)
Heat Transfer Soviet Res.
, vol.4
, Issue.6
, pp. 25-29
-
-
Ornatskiy, A.P.1
Glushchenko, L.F.2
Gandzyuk, O.F.3
-
51
-
-
0002648172
-
About heat transfer at turbulent fluid flow in tubes
-
Petukhov, B.S., Kirillov, 1958. About heat transfer at turbulent fluid flow in tubes, (In Russian). Thermal Eng. ( ) 4, 63-68.
-
(1958)
Thermal Eng.
, vol.4
, pp. 63-68
-
-
Petukhov, B.S.1
Kirillov2
-
52
-
-
0010325812
-
An investigation of heat transfer to fluids flowing in pipes under supercritical conditions
-
International Developments in Heat Transfer, Papers Presented at the, ASME, University of Colorado, Boulder, CO, USA, January 8-12, Part III, Paper 67
-
Petukhov, B.S., Krasnoshchekov, E.A., Protopopov, V.S., 1961. An investigation of heat transfer to fluids flowing in pipes under supercritical conditions. In: International Developments in Heat Transfer, Papers Presented at the 1961 International Heat Transfer Conference, ASME, University of Colorado, Boulder, CO, USA, January 8-12, Part III, Paper 67, pp. 569-578.
-
(1961)
1961 International Heat Transfer Conference
, pp. 569-578
-
-
Petukhov, B.S.1
Krasnoshchekov, E.A.2
Protopopov, V.S.3
-
53
-
-
2342632220
-
New approach to calculation of heat transfer with supercritical pressures of the heat-transfer medium
-
Petukhov B.S., Polyakov A.F., Rosnovskii S.V. New approach to calculation of heat transfer with supercritical pressures of the heat-transfer medium. High Temperatures (cTp. 1326-1329) 14(6):1976;1189-1192.
-
(1976)
High Temperatures
, vol.14
, Issue.6
, pp. 1189-1192
-
-
Petukhov, B.S.1
Polyakov, A.F.2
Rosnovskii, S.V.3
-
54
-
-
2642535257
-
Experimental heat transfer to water flowing in channels at supercritical pressures (survey)
-
Embedded Topical Meeting GLOBAL 2003 "Advanced Nuclear Energy and Fuel Cycle Systems", New Orleans, Louisiana, USA, November 16-20
-
Pioro, I., Duffey, R., 2003. Experimental heat transfer to water flowing in channels at supercritical pressures (survey). In: Proceedings of the ANS/ENS International Winter Meeting and Nuclear Technology Expo, Embedded Topical Meeting GLOBAL 2003 "Advanced Nuclear Energy and Fuel Cycle Systems", New Orleans, Louisiana, USA, November 16-20.
-
(2003)
Proceedings of the ANS/ENS International Winter Meeting and Nuclear Technology Expo
-
-
Pioro, I.1
Duffey, R.2
-
55
-
-
2342596114
-
Hydraulic resistance of fluids flowing in channels at supercritical pressures (survey)
-
Embedded Topical Meeting GLOBAL 2003 "Advanced Nuclear Energy and Fuel Cycle Systems", New Orleans, Louisiana, USA, November 16-20
-
Pioro, I., Duffey, R., Dumouchel, T., 2003. Hydraulic resistance of fluids flowing in channels at supercritical pressures (survey). In: Proceedings of the ANS/ENS International Winter Meeting and Nuclear Technology Expo, Embedded Topical Meeting GLOBAL 2003 "Advanced Nuclear Energy and Fuel Cycle Systems", New Orleans, Louisiana, USA, November 16-20.
-
(2003)
Proceedings of the ANS/ENS International Winter Meeting and Nuclear Technology Expo
-
-
Pioro, I.1
Duffey, R.2
Dumouchel, T.3
-
56
-
-
2342656720
-
Heat transfer at supercritical pressures (survey)
-
Shinjuku, Tokyo, Japan, April 20-23, Paper No. 36454
-
Pioro, I.L., Khartabil, H.F., Duffey, R.B., 2003. Heat transfer at supercritical pressures (survey). In: Proceedings of the 11th International Conference on Nuclear Engineering (ICONE-11), Shinjuku, Tokyo, Japan, April 20-23, Paper No. 36454.
-
(2003)
Proceedings of the 11th International Conference on Nuclear Engineering (ICONE-11)
-
-
Pioro, I.L.1
Khartabil, H.F.2
Duffey, R.B.3
-
57
-
-
0004038766
-
-
Begell House, New York, NY, USA
-
Pioro, L.S., Pioro, I.L., 1997. Industrial Two-Phase Thermosyphons, Begell House, New York, NY, USA, p. 4.
-
(1997)
Industrial Two-phase Thermosyphons
, pp. 4
-
-
Pioro, L.S.1
Pioro, I.L.2
-
58
-
-
0016948266
-
Modes of "normal" and "deteriorated" heat exchange in the single-phase near-critical region in the turbulent flow of helium in tubes
-
cTp. 606-612
-
Pron'ko V.G., Malyshev G.P., Migalinskaya L.N. Modes of "normal" and "deteriorated" heat exchange in the single-phase near-critical region in the turbulent flow of helium in tubes. J. Eng.-Phys. (. ), cTp. 606-612 30(4):1976;389-395.
-
(1976)
J. Eng.-phys.
, vol.30
, Issue.4
, pp. 389-395
-
-
Pron'ko, V.G.1
Malyshev, G.P.2
Migalinskaya, L.N.3
-
59
-
-
2342582433
-
Wärmetransport durch natürliche konvection in Stoffen bei Kritischen zustand
-
Schmidt E. Wärmetransport durch natürliche konvection in Stoffen bei Kritischen zustand. Int. J. Heat Mass Transfer. 1(1):1960;92-101.
-
(1960)
Int. J. Heat Mass Transfer
, vol.1
, Issue.1
, pp. 92-101
-
-
Schmidt, E.1
-
60
-
-
82955234210
-
Heat transfer by liquids near the critical state
-
Air Materials Command, Wright Field, Dayton, OH, USA, April
-
Schmidt, E., Eckert, E., Grigull, V., 1946. Heat transfer by liquids near the critical state, AFF Translation, No. 527, Air Materials Command, Wright Field, Dayton, OH, USA, April.
-
(1946)
AFF Translation
, vol.527
-
-
Schmidt, E.1
Eckert, E.2
Grigull, V.3
-
61
-
-
2342545749
-
Heat transfer to water, oxygen and carbon dioxide in near critical region
-
Shitsman, M.E., 1959. Heat transfer to water, oxygen and carbon dioxide in near critical region (In Russian). Thermal Eng. ( ) 1, 68-72.
-
(1959)
Thermal Eng.
, vol.1
, pp. 68-72
-
-
Shitsman, M.E.1
-
62
-
-
0001547367
-
Impairment of the heat transmission at supercritical pressures
-
Shitsman M.E. Impairment of the heat transmission at supercritical pressures. High Temperatures (. cTp. 267-275) 1(2):1963;237-244.
-
(1963)
High Temperatures
, vol.1
, Issue.2
, pp. 237-244
-
-
Shitsman, M.E.1
-
63
-
-
1842683738
-
Heat transfer to supercritical helium, carbon dioxide, and water: Analysis of thermodynamic and transport properties and experimental data
-
Shitsman M.W. Heat transfer to supercritical helium, carbon dioxide, and water: analysis of thermodynamic and transport properties and experimental data. Cryogenics. 14(2):1974;77-83.
-
(1974)
Cryogenics
, vol.14
, Issue.2
, pp. 77-83
-
-
Shitsman, M.W.1
-
64
-
-
0000234726
-
The light water integral reactor with natural circulation of the coolant at supercritical pressure B-500 SKDI
-
Silin V.A., Voznesensky V.A., Afrov A.M. The light water integral reactor with natural circulation of the coolant at supercritical pressure B-500 SKDI. Nucl. Eng. Des. 144:1993;327-336.
-
(1993)
Nucl. Eng. Des.
, vol.144
, pp. 327-336
-
-
Silin, V.A.1
Voznesensky, V.A.2
Afrov, A.M.3
-
65
-
-
2342618521
-
-
Institute of Atomic Energy by the name of I.V. Kurchatov, Moscow, Russia
-
Skvortsov, S.A., Feinberg, S.M., 1961. Use of supercritical parameters steam in the pressurized water power reactors (in Russian), Institute of Atomic Energy by the name of I.V. Kurchatov ( AH CCCP), Moscow, Russia.
-
(1961)
Use of Supercritical Parameters Steam in the Pressurized Water Power Reactors
-
-
Skvortsov, S.A.1
Feinberg, S.M.2
-
66
-
-
2342594225
-
Ultra-supercritical CHP: Getting more competitive
-
Smith, D., 1999. Ultra-supercritical CHP: getting more competitive, Modern Power Systems, pp. 21-32.
-
(1999)
Modern Power Systems
, pp. 21-32
-
-
Smith, D.1
-
67
-
-
2342596113
-
-
Report HW-59684, Prepared by the staff of Reactor Engineering Development Operation, Hanford Atomic Products Operation, Richland, Washington, USA, March 18.
-
Supercritical pressure power reactor. A conceptual design, 1959. Report HW-59684, Prepared by the staff of Reactor Engineering Development Operation, Hanford Atomic Products Operation, Richland, Washington, USA, March 18.
-
(1959)
Supercritical Pressure Power Reactor. A Conceptual Design
-
-
-
68
-
-
85012708666
-
Heat transfer to supercritical water in smooth-bore tubes
-
Swenson H.S., Carver J.R., Karakala C.R. Heat transfer to supercritical water in smooth-bore tubes. J. Heat Transfer, Trans. ASME, Ser. C. 87(4):1965;477-484.
-
(1965)
J. Heat Transfer, Trans. ASME, Ser. C
, vol.87
, Issue.4
, pp. 477-484
-
-
Swenson, H.S.1
Carver, J.R.2
Karakala, C.R.3
-
69
-
-
2342651719
-
-
Energoizdat Publishing House, Moscow, Russia
-
Thermal and Nuclear Power Plants, Handbook (in Russian), 1982. In: Grigor'ev, V.A., Zorin, V.M. (Eds.), Energoizdat Publishing House, Moscow, Russia, pp. 230, 282.
-
(1982)
Thermal and Nuclear Power Plants, Handbook (in Russian)
, pp. 230
-
-
Grigor'ev, V.A.1
Zorin, V.M.2
-
70
-
-
0031988712
-
Where did the Dittus and Boelter equation come from?
-
Winterton R.H.S. Where did the Dittus and Boelter equation come from? Int. J. Heat Mass Transfer. 41(4/5):1998;809-810.
-
(1998)
Int. J. Heat Mass Transfer
, vol.41
, Issue.4-5
, pp. 809-810
-
-
Winterton, R.H.S.1
-
71
-
-
2342622391
-
Status and application of supercritical-water reactor coolant
-
Wright J.H., Patterson J.F. Status and application of supercritical-water reactor coolant. Proc. Am. Power Conf. 28:1966;139-149.
-
(1966)
Proc. Am. Power Conf.
, vol.28
, pp. 139-149
-
-
Wright, J.H.1
Patterson, J.F.2
-
72
-
-
0015482943
-
Forced convective heat transfer to supercritical water flowing in tubes
-
Yamagata K., Nishikawa K., Hasegawa S., et al. Forced convective heat transfer to supercritical water flowing in tubes. Int. J. Heat Mass Transfer. 15(12):1972;2575-2593.
-
(1972)
Int. J. Heat Mass Transfer
, vol.15
, Issue.12
, pp. 2575-2593
-
-
Yamagata, K.1
Nishikawa, K.2
Hasegawa, S.3
-
73
-
-
0017544684
-
A correlation for heat transfer to superphysical helium in turbulent flow in small channels
-
Yaskin L.A., Jones M.C., Yeroshenko V.M., et al. A correlation for heat transfer to superphysical helium in turbulent flow in small channels. Cryogenics. 17(10):1977;549-552.
-
(1977)
Cryogenics
, vol.17
, Issue.10
, pp. 549-552
-
-
Yaskin, L.A.1
Jones, M.C.2
Yeroshenko, V.M.3
-
74
-
-
0019530881
-
Applicability of various correlations for the prediction of turbulent heat transfer of supercritical helium
-
Yeroshenko V.M., Yaskin L.A. Applicability of various correlations for the prediction of turbulent heat transfer of supercritical helium. Cryogenics. 21(2):1981;94-96.
-
(1981)
Cryogenics
, vol.21
, Issue.2
, pp. 94-96
-
-
Yeroshenko, V.M.1
Yaskin, L.A.2
|