1 |
An Overview of Rod-Bundle Thermal-Hydraulic Analysis
/
[
William T. Sha
] /
ANL-79-10
|
2 |
KALIMER Breakeven 노심의 핵연료 집합체 온도분포 해석
/
[
임현진(외)
] /
춘계학술발표회 논문집
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3 |
액체금속로 전노심 열유체 해석체계 구축방안 연구
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[
김영균(외)
] /
춘계학술발표회 논문집
|
4 |
An LMR Core Thermal-Hydraulics Code Based on the ENERGY Model
/
[
Yang, W.S.
] /
Journal of KNS
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5 |
KALIMER Breeder Equilibrium Core Conceptual Design and Analysis
/
[
김영인(외)
] /
LMR/CD120-ER-01 Rev. 0/99, Internal Document
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6 |
Nuclear and Thermal-hydraulic Characteristics for KALIMER Breakeven Equilibrium Core
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[
김영인(외)
] /
LMR/CD112-ER-01 Rev. 0/2000, Internal Document
|
7 |
액체금속로 설계개념 연구
/
[
박창규(외)
] /
KAERI/RR-1719/96
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8 |
Thermal Hydraulic Conceptual Deisgn of KALIMER Breeder Core with Its Configuration Development
/
[
Kim, Y.G.(et al.)
] /
NTHAS2
|
9 |
Inter-Assembly Heat Transfer Modeling for the Development of LMR Core Subchannel Code
/
[
Kim, W.S.(et al.)
] /
NTHAS2
|
10 |
COBRA-WC: A Version of COBRA for Single-Phase Multisubassembly Thermal Hydraulic Transient Analysis
/
[
George, T.L.(et al.)
] /
PNL-3259
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11 |
/
[
Kim, W.S.(et al.)
] /
A Subchannel Analysis Code MATRA-LMR for Wire-Wrapped Liquid Metal Cooled Reactor Subassembly, Annals of Nuclear Energy
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