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Spent fuel pool
OpenAlex ID:
C156342284
The Economics of Reprocessing versus Direct Disposal of Spent Nuclear Fuel
2005
·
Matthew Bunn
, John P. Holdren
, et al.
·
Nuclear Technology
·
131
Low cost, proliferation resistant, uranium–thorium dioxide fuels for light water reactors
2001
·
J.Stephen Herring
, Philip E MacDonald
, et al.
·
Nuclear Engineering and Design
·
121
Spent nuclear fuel interim dry storage; Design requirements, most common methods, and evolution: A review
2021
·
Moamen G. El-Samrah
, A.F. Tawfic
, et al.
·
Annals of Nuclear Energy
·
109
Reprocessing of spent nuclear fuel in India: Present challenges and future programme
2017
·
Rajamani Natarajan
·
Progress in Nuclear Energy
·
106
Fuel Behavior Under Loss-of-coolant Accident Situations
2005
·
Hee M. Chung
·
Nuclear Engineering and Technology
·
104
The design and simulation of a new spent fuel pool passive cooling system
2013
·
C. Ye
, M.G. Zheng
, et al.
·
Annals of Nuclear Energy
·
92
Reducing the Hazards from Stored Spent Power-Reactor Fuel in the United States
2003
·
Robert Alvarez
, Jan Beyea
, et al.
·
Science and Global Security
·
85
Reactor and fuel cycle performance of light water reactor fuel with 235U enrichments above 5%
2020
·
Joseph R. Burns
, Richard Hernandez
, et al.
·
Annals of Nuclear Energy
·
79
PDF
Reexamination of spent fuel shipment risk estimates
2000
·
Jeremy L. Sprung
·
66
Nuclear Fuel Behaviour in Loss-of-coolant Accident (LOCA) Conditions
2009
·
Kjell Pettersson
, H M Chung
, et al.
·
63
The Canadian Spent Fuel Storage Canister: Some Materials Aspects
1977
·
Derek G. Boase
, Tjalle T. Vandergraaf
·
Nuclear Technology
·
62
Utilization of 3D fuel modeling capability of BISON to derive new insights in performance of advanced PWR fuel concepts
2019
·
Yangbin Deng
, Koroush Shirvan
, et al.
·
Journal of Nuclear Materials
·
57
PDF
Characterization of spent fuel approved testing material: ATM-103
1988
·
R.J. Guenther
, D.E. Blahnik
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
57
Physics Study on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU (DUPIC)
1997
·
Hangbok Choi
, Bo W. Rhee
, et al.
·
Nuclear Science and Engineering
·
54
Determining initial enrichment, burnup, and cooling time of pressurized-water-reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden
2016
·
A. Favalli
, D. Vo
, et al.
·
Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment
·
53
PDF
Thermal-fluid flow analysis and demonstration test of a spent fuel storage system
2009
·
J.C. Lee
, W.S. Choi
, et al.
·
Nuclear Engineering and Design
·
52
Verification of Spent Nuclear Fuel in Sealed Dry Storage Casks via Measurements of Cosmic-Ray Muon Scattering
2018
·
J. M. Durham
, D. Poulson
, et al.
·
Physical Review Applied
·
51
PDF
Experimental study on heat pipe heat removal capacity for passive cooling of spent fuel pool
2015
·
Zhenqin Xiong
, Minglu Wang
, et al.
·
Annals of Nuclear Energy
·
50
The development of a three-dimensional transient CFD model for predicting cooling ability of spent fuel pools
2012
·
Tzu-Chen Hung
, Vijay K. Dhir
, et al.
·
Applied Thermal Engineering
·
48
Nuclide Composition Benchmark Data Set for Verifying Burnup Codes on Spent Light Water Reactor Fuels
2002
·
Yoshinori Nakahara
, Kenya Suyama
, et al.
·
Nuclear Technology
·
48
Integrated analysis of VVER-1000 fuel assembly fueled with accident tolerant fuel (ATF) materials
2021
·
Mohamed Y.M. Mohsen
, Mohamed A.E. Abdel-Rahman
, et al.
·
Annals of Nuclear Energy
·
47
Geometrical α- and β-dose distributions and production rates of radiolysis products in water in contact with spent nuclear fuel
2006
·
Fredrik Nielsen
, Mats Jonsson
·
Journal of Nuclear Materials
·
45
Fission product release from highly irradiated LWR fuel
1980
·
R.A. Lorenz
, J.L. Collins
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
44
Characterization of spent fuel approved testing material: ATM-106
1988
·
R.J. Guenther
, D.E. Blahnik
, et al.
·
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
·
43
Thermal and fluid analysis of dry cask storage containers over multiple years of service
2017
·
Yongjia Wu
, Jackson Klein
, et al.
·
Annals of Nuclear Energy
·
42
PDF
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3,111
Citation count:
7,179
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