-
1
-
-
39549092533
-
-
Fratoni, M., Kim, L., Mattafirri, S., Petroski, R., Greenspan, E., 2007. Preliminary feasibility study of the heat-pipe ENHS Reactor. In: Proceedings of International Conference on Emerging Nuclear Energy Systems, ICENES 2007, Istanbul, Turkey, June 3-8.
-
Fratoni, M., Kim, L., Mattafirri, S., Petroski, R., Greenspan, E., 2007. Preliminary feasibility study of the heat-pipe ENHS Reactor. In: Proceedings of International Conference on Emerging Nuclear Energy Systems, ICENES 2007, Istanbul, Turkey, June 3-8.
-
-
-
-
2
-
-
39549093710
-
-
Greenspan, E., and the ENHS Project Team, 2002. The long-life core encapsulated nuclear heat source (ENHS) generation IV reactor. In: Proc. Int. Congress on Advanced Nuclear Power Plants (ICAPP), Holywood, FL, June 9-13.
-
Greenspan, E., and the ENHS Project Team, 2002. The long-life core encapsulated nuclear heat source (ENHS) generation IV reactor. In: Proc. Int. Congress on Advanced Nuclear Power Plants (ICAPP), Holywood, FL, June 9-13.
-
-
-
-
3
-
-
39549109938
-
-
Greenspan, E., April 2005. Solid-core heat-pipe nuclear battery type reactor. Research Proposal Submitted for the DOE Nuclear Engineering Education Research (NEER) Program.
-
Greenspan, E., April 2005. Solid-core heat-pipe nuclear battery type reactor. Research Proposal Submitted for the DOE Nuclear Engineering Education Research (NEER) Program.
-
-
-
-
4
-
-
39549114947
-
-
Greenspan, E., 2006. ENHS general information, technical features, and operating characteristics. IAEA Status Report on Innovative Small and Medium-Sized Reactors (SMRs).
-
Greenspan, E., 2006. ENHS general information, technical features, and operating characteristics. IAEA Status Report on Innovative Small and Medium-Sized Reactors (SMRs).
-
-
-
-
5
-
-
14644437830
-
The encapsulated nuclear heat source (ENHS) reactor core design
-
Hong S.G., Greenspan E., and Kim Y.I. The encapsulated nuclear heat source (ENHS) reactor core design. Nuclear Technology 149 (2005)
-
(2005)
Nuclear Technology
, vol.149
-
-
Hong, S.G.1
Greenspan, E.2
Kim, Y.I.3
-
7
-
-
39549115170
-
-
Hong, S.G., Greenspan, E., 2004. Power flattening options for the ENHS (encapsulated nuclear heat source) core. In: Proceedings of the International Symposium on Innovative Nuclear Energy Systems, Tokyo, Japan, October 31-November 4.
-
Hong, S.G., Greenspan, E., 2004. Power flattening options for the ENHS (encapsulated nuclear heat source) core. In: Proceedings of the International Symposium on Innovative Nuclear Energy Systems, Tokyo, Japan, October 31-November 4.
-
-
-
-
8
-
-
39549115369
-
-
Hong, S.G., Greenspan, E., 2005. Use of minor actinides for reduced power ENHS reactor core design. In: Proceedings of GLOBAL'05, Tsukuba, Japan, October 9-13.
-
Hong, S.G., Greenspan, E., 2005. Use of minor actinides for reduced power ENHS reactor core design. In: Proceedings of GLOBAL'05, Tsukuba, Japan, October 9-13.
-
-
-
-
9
-
-
0027206934
-
-
Hattori, S., Minato, A., 1993. Current status of 4S plant design. In: Proceedings of the Second ASME-JSME International Conference on Nuclear Engineering: ICONE-2, CA, March 21-24.
-
Hattori, S., Minato, A., 1993. Current status of 4S plant design. In: Proceedings of the Second ASME-JSME International Conference on Nuclear Engineering: ICONE-2, CA, March 21-24.
-
-
-
-
10
-
-
39549121692
-
Multi-recycling in the ENHS and the equilibrium core
-
Monti L., Greenspan E., Sumini M., Fratoni M., and Rocchi F. Multi-recycling in the ENHS and the equilibrium core. Progress in Nuclear Energy 50 2-6 (2008) 262-268
-
(2008)
Progress in Nuclear Energy
, vol.50
, Issue.2-6
, pp. 262-268
-
-
Monti, L.1
Greenspan, E.2
Sumini, M.3
Fratoni, M.4
Rocchi, F.5
-
11
-
-
0035387774
-
Long-life water cooled small reactor with U-Np-Pu fuel
-
Nikitin K., Saito M., Kawashima M., Artisyuk V., and Shmelev A. Long-life water cooled small reactor with U-Np-Pu fuel. Journal of Nuclear Science and Technology 38 1-12 (2001)
-
(2001)
Journal of Nuclear Science and Technology
, vol.38
, Issue.1-12
-
-
Nikitin, K.1
Saito, M.2
Kawashima, M.3
Artisyuk, V.4
Shmelev, A.5
-
14
-
-
22344444177
-
Nuclear design of the SAFE-400 space fission reactor
-
Poston D.I. Nuclear design of the SAFE-400 space fission reactor. Nuclear News (December 2002)
-
(2002)
Nuclear News
-
-
Poston, D.I.1
-
15
-
-
39549122918
-
-
Sieniki, J.J., Moisseytsev, A.V., 2005. SSTAR lead-cooled, small modular fast reactor for deployment at remote sites - system thermal hydraulic development. In: Proc. of ICAPP'05, Seoul, Korea, May 15-19.
-
Sieniki, J.J., Moisseytsev, A.V., 2005. SSTAR lead-cooled, small modular fast reactor for deployment at remote sites - system thermal hydraulic development. In: Proc. of ICAPP'05, Seoul, Korea, May 15-19.
-
-
-
-
16
-
-
39549112421
-
-
Stewart, J.S., Lamont, A.D., Rothwell, G.S, Smith, C.F., Greenspan, E., Brown, N., Barak, A., March 1, 2002. An economic analysis of generation iv small modular reactors. Lawrence Livermore National Laboratory Report UCRL-ID-148437.
-
Stewart, J.S., Lamont, A.D., Rothwell, G.S, Smith, C.F., Greenspan, E., Brown, N., Barak, A., March 1, 2002. An economic analysis of generation iv small modular reactors. Lawrence Livermore National Laboratory Report UCRL-ID-148437.
-
-
-
-
17
-
-
39549091214
-
-
Susplugas, A., Greenspan, E., 2005. Implementation of the ENHS thermal hydraulic optimization code for recent ENHS design improvements. UCBNE Internal Report UCB-NE-5104.
-
Susplugas, A., Greenspan, E., 2005. Implementation of the ENHS thermal hydraulic optimization code for recent ENHS design improvements. UCBNE Internal Report UCB-NE-5104.
-
-
-
-
18
-
-
39549089421
-
-
Susplugas, A., Greenspan, E., November 2006. ENHS reactor power level enhancement possibilities. In: Proceedings of the Second COE-INES International Symposium on Innovative Nuclear Energy Systems, INES-2, Yokohama, Japan, 26-30.
-
Susplugas, A., Greenspan, E., November 2006. ENHS reactor power level enhancement possibilities. In: Proceedings of the Second COE-INES International Symposium on Innovative Nuclear Energy Systems, INES-2, Yokohama, Japan, 26-30.
-
-
-
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