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Dissolution Behavior of SrO into Molten LiCl for Heat Reduction in Used Nuclear Fuel
강도규
James T.M. Amphlett
최은영
배상은
최성열
2021년
활용도 Analysis
논문 Analysis
연구자 Analysis
활용도 Analysis
논문 Analysis
연구자 Analysis
활용도
공유도
영향력
논문상세정보
저자
강도규
James T.M. Amphlett
최은영
배상은
최성열
주제어
Fission products
Heat reduction process
Solubility
Molten-salt
Pyroprocessing
참고문헌( 27)
유사주제 논문( 103)
pyroprocessing 43건
Solubility 38건
molten-salt 17건
Fission products 5건
인용/피인용
Dissolution Behavior of SrO into Molten LiCl f ...
' Dissolution Behavior of SrO into Molten LiCl for Heat Reduction in Used Nuclear Fuel' 의 주제별 논문영향력
논문영향력 요약
주제
Fission products
Heat reduction process
Solubility
molten-salt
pyroprocessing
동일주제 총논문수
논문피인용 총횟수
주제별 논문영향력의 평균
108
0
0.0%
자세히
주제별 논문영향력
논문영향력
주제
주제별 논문수
주제별 피인용횟수
주제별 논문영향력
주제어
Fission products
6
0
0.0%
Heat reduction process
1
0
0.0%
Solubility
39
0
0.0%
molten-salt
18
0
0.0%
pyroprocessing
44
0
0.0%
계
108
0
0.0%
* 다른 주제어 보유 논문에서 피인용된 횟수
0
닫기
' Dissolution Behavior of SrO into Molten LiCl for Heat Reduction in Used Nuclear Fuel'
의 참고문헌
Underpotential deposition of Li in a molten LiCleLi2O electrolyte for the electrochemical reduction of U from uranium oxides
J. -M. Hur
[2010]
Treatment OF oxide spent fuel using the lithium reduction process
E. J. Karell
[1996]
Thermodynamic Calculations on the Chemical Behavior of SrO During Electrolytic Oxide Reduction
전민구
[2020]
Thermal Analyses of Spent Nuclear Fuel Repository Thermal Analyses of Spent Nuclear Fuel Repository
K. Ikonen
[2003]
Solubility of Li[sub 2]O in Molten LiCl–MCl[sub x] (M=Na, K, Cs, Ca, Sr, or Ba) Binary Systems
Yoshiharu Sakamura
[2010]
Solubility measurement of Li2O in LiCl molten salt for electro-reduction process
D. H. Kim
[2013]
Separations and transmutation criteria to improve utilization of a geologic repository
R. A. Wigeland
[2006]
Separation and recovery of uranium metal from spent light water reactor fuel via electrolytic reduction and electrorefining
S. D. Herrmann
[2010]
SEPARATION OF STRONTIUM AND CESIUM FROM TERNARY AND QUATERNARY LITHIUM CHLORIDE-POTASSIUM CHLORIDE SALTS VIA MELT CRYSTALLIZATION
AMMON N. WILLIAMS
[2015]
Preliminary conceptual design and cost estimation for Korea advanced pyroprocessing facility plus(KAPFþ)
W. Il Ko
[2014]
Performance modeling and analysis of spent nuclear fuel recycling
R. Gao
[2015]
On metal oxide solubilities in some molten alkali metal bromides at T ¼ 973 K
V. L. Cherginets
[2014]
On barium oxide solubility in barium-containing chloride melts
E. V. Nikolaeva
[2016]
Interaction of strontium oxide with Sr-Cl2-MCl melts
A. V. Volkovich
[2011]
Interaction between barium oxide and barium containing chloride melt
E. V. Nikolaeva
[2015]
Environmental life cycle risk modeling of nuclear waste recycling systems
S. Choi
[2016]
Environmental assessment of advanced partitioning, transmutation, and disposal based on long-term risk-informed regulation: PyroGreen
Hyo Sook Jung
[2012]
Electrolytic reduction of spent nuclear oxide fuel as part of an integral process to separate and recover actinides from fission products
S. D. Herrmann
[2006]
Electrolytic reduction of spent light water reactor fuel bench-scale experiment results
S. Herrmann
[2007]
Electrolytic reduction of a simulated oxide spent fuel and the fates of representative elements in a Li2O-LiCl molten salt
W. Park
[2016]
Electrochemical processing of spent nuclear fuels : an overview of oxide reduction in pyroprocessing technology
E. Y. Choi
[2015]
Dynamic assessments on high-level waste and low-and intermediate-level waste generation from open and closed nuclear fuel cycles in Republic of Korea
S. Choi
[2014]
Determination of oxide ion activity in molten LiCl using oxide ion electrode
J. Jeon
[2002]
Current status of pyroprocessing development at KAERI
H. Lee
[2013]
Concentrations of CsCl and SrCl2 from a simulated LiCl salt waste generated by pyroprocessing by using czochralski method
H. S. Lee
[2009]
Chapter 3 equilibria in “solid oxide-ionic melt” systems, compr
I. N. I. Solvents
[2005]
An Experimental Study on an Electrochemical Reduction of an Oxide Mixture in the Advanced Spent-Fuel Conditioning Process
정상문
[2010]
' Dissolution Behavior of SrO into Molten LiCl for Heat Reduction in Used Nuclear Fuel'
의 유사주제(
) 논문