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2.( . . " " " # A %#-%# C #% " # " C " " ?$ E// % " # % . ~ A C # . — 2010. | 2. E. 55—63.

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1.1 0.1., = . . < ""> C ## $ 8 > A&- " # . — .: C 8#% , 1985. 288 ".

2.+G ! . . $& !#%# $& / # 8 / A C # . E? # - ? $ # / &-. €. . %8 . — % *: % . !#&. " . A C. #-, 1998, 338 ".

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1. 1 !" & $C 88 « % # # 8 C A C$8>D& C 8$& " ""## 2007 — 2010 C > # $"$# 2015 C », -$" & # 8 < # &*" • 6 ? 2006 C. | 605.

2. The Future of Nuclear Power: an interdisciplinary MIT study, 2003.

3. The Future of Nuclear Fuel Cycle: an interdisciplinary MIT study, 2010.

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1. Caldarola L. A theoretical model for the molten fuel-sodium interaction in a nuclear fast reactor // Nuclear Engineering and Design 22. 1972. . 175—211.

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L = /g/( — C)+LF( F— C)/( — C)+L<( — <)/( — C)+Lt, (1) C L — >" ; — C# # 8#-" "$# & # "- C ; g — " # " ? C $# ; — $& " * $&- "# & # @ % ; C — $& " * $& "# & > #% # / % >; LF — >" # / % >; F — " # C &* $& " * $& "# & # / % ; L< — " $& ?- 8 > ? $C ; < — " # C &* $& " * $&- "# & $C ; Lt — >" " C >&* # ? && C / #.

$#8 &* " ? $& >8 & 35 000 ( #". 2). % &* $#8#% ## $ $#&* " * >? ! 8> &- & , $& " # ? > " # $% & %8 " # * ? & 20 000 ? # 8 & / $& = # $! # / " #, ? > "- # &* "! # " / ! 8> — ? & 19 000 ? #%-% " / " # % / [1] .

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1. . ., # . ., U! . . < C & '' -E " "! # " #8# && 8# // > 17-/ / ! ## "-# "$# . ., 2011.

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! E « » " A "$#8 &* "-E , 8 @= $" / " " / $ & # 8 ('' ), " #"$&*% # 8 8 # #""& # $"" $8- D# # : " & / # 8$/. ' 2012—2013 CC. $& # " $ - " # C$$> A "$#8 : 1) #8> " $/ $" / " & @= / > E F; 2) #8>, 8 @=# $"$& ## / % > $? # " #% C# % $ $# ""- & ## " " / # & ##.

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1.Smith B.L. Assessment of CFD Codes Used in Nuclear Reactor Safety Simulations // Nuclear Engineering and Technology. 2010. V.42. No.4.

2.Ansys Fluent 12.0. Theory Guide. Ansys, Inc. 2009.

20