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Nuclear Technology Volume 180, 2012 - Issue 2
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Radioactive Waste Management and Disposal

Study of Fukushima Daiichi Nuclear Power Station Unit 4 Spent-Fuel Pool

Dean WangOak Ridge National Laboratory, 1 Bethel Valley Road #6167, Oak Ridge, Tennessee 37831
,
Ian C. GauldOak Ridge National Laboratory, 1 Bethel Valley Road #6167, Oak Ridge, Tennessee 37831
,
Graydon L. YoderOak Ridge National Laboratory, 1 Bethel Valley Road #6167, Oak Ridge, Tennessee 37831
,
Larry J. OttOak Ridge National Laboratory, 1 Bethel Valley Road #6167, Oak Ridge, Tennessee 37831
,
George F. FlanaganOak Ridge National Laboratory, 1 Bethel Valley Road #6167, Oak Ridge, Tennessee 37831
,
Matthew W. FrancisOak Ridge National Laboratory, 1 Bethel Valley Road #6167, Oak Ridge, Tennessee 37831
,
Emilian L. PopovOak Ridge National Laboratory, 1 Bethel Valley Road #6167, Oak Ridge, Tennessee 37831
,
Juan J. CarbajoOak Ridge National Laboratory, 1 Bethel Valley Road #6167, Oak Ridge, Tennessee 37831
,
Prashant K. JainOak Ridge National Laboratory, 1 Bethel Valley Road #6167, Oak Ridge, Tennessee 37831
,
John C. WagnerOak Ridge National Laboratory, 1 Bethel Valley Road #6167, Oak Ridge, Tennessee 37831
&
Jess C. GehinOak Ridge National Laboratory, 1 Bethel Valley Road #6167, Oak Ridge, Tennessee 37831
 show all
Pages 205-215 | Published online: 27 Mar 2017

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Mirza Mohammed Shah. (2018) Improved model for calculation of evaporation from water pools. Science and Technology for the Built Environment 24:10, pages 1064-1074.
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Bing Wang, Bin Wu, Rizwan uddin, Haijun Jia & Jinhua Wang. (2018) Development of a thermal-hydraulic analysis code TAC-DS for spent fuel dry-storage system for high-temperature pebble bed reactor. Journal of Nuclear Science and Technology 55:3, pages 301-318.
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Articles from other publishers (31)

Kan Sun, Yongjia Wu, Feng Qian, Hyunjun Jung, Suresh Kaluvan, He Huijin, Cheng Zhang, F. Kyle Reed, M. Nance Ericson, Haifeng Zhang & Lei Zuo. (2022) Self-powered Through-wall communication for dry cask storage monitoring. Annals of Nuclear Energy 177, pages 109306.
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Ruslan M. Sledkov, Valery Ye. Karnaukhov, Oleg Ye. Stepanov, Mark M. Bedretdinov & Igor A. Chusov. (2022) Results of validation and cross-verification of the ROK/B design code on the problem of loss of cooling in the spent fuel pool *. Nuclear Energy and Technology 8:2, pages 107-113.
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Mirza M Shah. (2021) Evaluation of methods for prediction of evaporation from water pools. Journal of Building Physics 45:5, pages 629-648.
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G. Brillant & J. Martin. (2021) Void fraction in a co-current two-phase flow through a prototypical PWR spent fuel assembly. Nuclear Engineering and Design 383, pages 111401.
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M Bedretdinov & O Stepanov. (2021) KORSAR/GP AND SOCRAT/V1 CODES’ VALIDATION FOR THE LOSS OF COOLING AT SPENT FUEL POOL CONDITIONS. PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS 2021:3, pages 213-226.
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Tobias Hanisch, Patrick Zedler, Antonio Hurtado, Frank Rüdiger & Jochen Fröhlich. (2021) Numerical and experimental analysis of flow and heat transfer in a fuel assembly mock-up with transverse flow above the rods. International Journal of Heat and Fluid Flow 89, pages 108809.
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Wasin Vechgama & Kampanart Silva. (2021) Assessment of Cesium Compound Behavior during Simultaneous Failure of Reactor Pressure Vessels and Spent Fuel Pools Using Modified ART Mod 2: Fukushima Daiichi Accident Simulation. Science and Technology of Nuclear Installations 2021, pages 1-16.
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M.M. Bedretdinov, O.E. Stepanov, R.M. Sledkov & C. Schuster. (2021) KORSAR/GP and SOCRAT/V1 codes’ validation for the loss of cooling at spent fuel pool conditions. Nuclear Engineering and Design 375, pages 111089.
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David A. Hakobyan & Victor I. Slobodchuk. (2021) Temperature conditions in the RBMK spent fuel pool in the event of disturbances in its cooling mode. Nuclear Energy and Technology 7:1, pages 9-13.
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Mizra Mohammad Shah. 2021. Two‐Phase Heat Transfer. Two‐Phase Heat Transfer 279 310 .
T. Höhne. (2020) Simulation of coolant mixing in a BWR spent fuel storage pool and flood chamber. Nuclear Engineering and Design 359, pages 110468.
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Xue Wang, Hongchao Wang, Wenbin Su, Teng Wang, María A. Madre, Jinze Zhai, Tingting Chen, Andres Sotelo & Chunlei Wang. (2020) A novel multilayer composite structured thermoelectric module with high output power. Journal of Materials Chemistry A 8:6, pages 3379-3389.
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Mirza M. Shah. (2019) Calculation of Evaporation From Fukushima Nuclear Power Plant Spent Fuel Pools. Journal of Nuclear Engineering and Radiation Science 5:4.
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Li Zhandong, Li Jingkui, Chen Ping, Wang Wei & Chen Xi. (2019) Design of Thrust Attachment Underwater Robot System in Nuclear Power Station Pool. Design of Thrust Attachment Underwater Robot System in Nuclear Power Station Pool.
Rosli Darmawan. (2019) Investigation on the gamma sources integrity inside a dry pit storage. IOP Conference Series: Materials Science and Engineering 555:1, pages 012014.
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J.C. de la Rosa Blul, P. McMinn & A. Grah. (2019) Analysis of the inherent response of nuclear spent fuel pools. Annals of Nuclear Energy 124, pages 295-326.
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Douglas L. Van Bossuyt & Bryan M. O’Halloran. (2019) A Method to Choose Between Automation and Human Operators for Recovery Actions During a Cyber Attack. Procedia Computer Science 153, pages 352-360.
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Ronald Oertel, T. Hanisch, E. Krepper, D. Lucas, F. Rüdiger & J. Fröhlich. (2019) Two-scale CFD analysis of a spent fuel pool involving partially uncovered fuel storage racks. Nuclear Engineering and Design 341, pages 432-450.
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O. Coindreau, B. Jäckel, F. Rocchi, F. Alcaro, D. Angelova, G. Bandini, M. Barnak, M. Behler, D.F. Da Cruz, R. Dagan, P. Drai, S. Ederli, L.E. Herranz, T. Hollands, G. Horvath, A. Kaliatka, I. Kljenak, O. Kotsuba, T. Lind, C. López, K. Mancheva, P. Matejovic, M. Matkovič, M. Steinbrück, M. Stempniewicz, R. Thomas, V. Vileiniskis, D.C. Visser, P. Vokáč, Y. Vorobyov & O. Zhabin. (2018) Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool. Annals of Nuclear Energy 120, pages 880-887.
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Marin Constantin, Minodora Apostol & Alina Constantin. (2018) Analysis of the releases produced by CANDU type irradiated fuel bundles accidentally remained in the air. Progress in Nuclear Energy 108, pages 351-357.
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Yen-Shu Chen. (2018) Thermal analysis for the integrated spent fuel pool of the Chinshan plant in the decommissioning process. Annals of Nuclear Energy 119, pages 163-174.
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Christine Partmann, Christoph Schuster & Antonio Hurtado. (2018) Experimental investigation of the thermal hydraulics of a spent fuel pool under loss of active heat removal conditions. Nuclear Engineering and Design 330, pages 480-487.
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M. Quinn Brewster. (2018) Evaporation of water at high mass-transfer rates by natural convection air flow with application to spent-fuel pools. International Journal of Heat and Mass Transfer 116, pages 703-714.
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Yen-Shu Chen & Yng-Ruey Yuann. (2017) Evaluation of cooling capacity with more fuel stored in the spent fuel pool of the Kuosheng plant. Annals of Nuclear Energy 109, pages 120-134.
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Matthew T. Davis, Michael D. Proctor & Buder Shageer. (2017) Disaster factor screening using SoS conceptual modeling and an LVC simulation framework. Reliability Engineering & System Safety 165, pages 368-375.
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Rinah Kim, Chan Hee Park, Wook Jae Yoo & Joo Hyun Moon. (2017) Development and characterization of a fiber-optic monitoring system for the key environment variables of the spent nuclear fuel pool at a nuclear power plant. Annals of Nuclear Energy 99, pages 183-192.
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Dong Pan, Ruiqian Zhang, Hui Wang, Chao Lu & Yunming Liu. (2016) Formation and stability of oxide layer in FeCrAl fuel cladding material under high-temperature steam. Journal of Alloys and Compounds 684, pages 549-555.
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Yen-Shu Chen & Yng-Ruey Yuann. (2016) Accident mitigation for spent fuel storage in the upper pool of a Mark III containment. Annals of Nuclear Energy 91, pages 156-164.
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Bernd S. Jäckel. (2015) Status of the spent fuel in the reactor buildings of Fukushima Daiichi 1–4. Nuclear Engineering and Design 283, pages 2-7.
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Xiaoli Wu, Wei Li, Yapei Zhang, Wenxi Tian, Guanghui Su & Suizheng Qiu. (2015) Analysis of accidental loss of pool coolant due to leakage in a PWR SFP. Annals of Nuclear Energy 77, pages 65-73.
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Xiaoli Wu, Wei Li, Yapei Zhang, Wenxi Tian, Guanghui Su & Suizheng Qiu. (2014) Analysis of the loss of pool cooling accident in a PWR spent fuel pool with MAAP5. Annals of Nuclear Energy 72, pages 198-213.
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