An evaluation on the cutting technologies for decommissioning of the large cylinder parts in the major components of NPPs (English)
- New search for: Jeong, KwanSeong
- New search for: Choi, ByungSeon
- New search for: Moon, JeiKwon
- New search for: Hyun, Dongjun
- New search for: Lee, Jonghwan
- New search for: Kim, IkJune
- New search for: Kim, GeunHo
- New search for: Seo, JaeSeok
- New search for: Jeong, SeongYoung
- New search for: Lee, JungJun
- New search for: Song, HaeSang
- New search for: Lee, SangWha
- New search for: Son, BongKi
- New search for: Jeong, KwanSeong
- New search for: Choi, ByungSeon
- New search for: Moon, JeiKwon
- New search for: Hyun, Dongjun
- New search for: Lee, Jonghwan
- New search for: Kim, IkJune
- New search for: Kim, GeunHo
- New search for: Seo, JaeSeok
- New search for: Jeong, SeongYoung
- New search for: Lee, JungJun
- New search for: Song, HaeSang
- New search for: Lee, SangWha
- New search for: Son, BongKi
In:
Annals of Nuclear Energy
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71
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340-342
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2014
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ISSN:
- Article (Journal) / Electronic Resource
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Title:An evaluation on the cutting technologies for decommissioning of the large cylinder parts in the major components of NPPs
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Contributors:Jeong, KwanSeong ( author ) / Choi, ByungSeon ( author ) / Moon, JeiKwon ( author ) / Hyun, Dongjun ( author ) / Lee, Jonghwan ( author ) / Kim, IkJune ( author ) / Kim, GeunHo ( author ) / Seo, JaeSeok ( author ) / Jeong, SeongYoung ( author ) / Lee, JungJun ( author )
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Published in:Annals of Nuclear Energy ; 71 ; 340-342
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Publisher:
- New search for: Elsevier Ltd
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Publication date:2014-04-15
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Size:3 pages
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ISSN:
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DOI:
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Type of media:Article (Journal)
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Type of material:Electronic Resource
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Language:English
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Keywords:
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Source:
Table of contents – Volume 71
The tables of contents are generated automatically and are based on the data records of the individual contributions available in the index of the TIB portal. The display of the Tables of Contents may therefore be incomplete.
- 1
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Recommended dispersing conditions for broths used in the preparation of uranium microspheres with carbonHunt, R.D. / Collins, J.L. et al. | 2014
- 6
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Biogeochemical changes at early stage after the closure of radioactive waste geological repository in South KoreaChoung, Sungwook / Um, Wooyong / Choi, Seho / Francis, Arokiasamy J. / Kim, Sungpyo / Park, Jin beak / Kim, Suk-Hoon et al. | 2014
- 11
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Thermal analysis of prismatic gas-cooled reactor core under coolant channel blockage accidentsLee, Sung Nam / Tak, Nam-il / Kim, Min Hwan / Noh, Jae Man et al. | 2014
- 23
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The ADOPT code for automated fast reactor core designQvist, Staffan / Greenspan, Ehud et al. | 2014
- 37
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Burnup estimation for plate type fuel assembly of research reactors through the least square fitting methodAlawneh, Luay M. / Park, Chang Je / Jaradat, Mustafa K. / Lee, Byungchul et al. | 2014
- 46
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Gamma and neutron attenuation behaviours of boron carbide–silicon carbide compositesBuyuk, Bulent / Tugrul, A. Beril et al. | 2014
- 52
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Development of a 1D transient electrorefiner model for pyroprocess simulationCumberland, Riley M. / Yim, Man-Sung et al. | 2014
- 60
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Goal-based angular adaptivity applied to the spherical harmonics discretisation of the neutral particle transport equationGoffin, Mark A. / Buchan, Andrew G. / Belme, Anca C. / Pain, Christopher C. / Eaton, Matthew D. / Smith, Paul N. / Smedley-Stevenson, Richard P. et al. | 2014
- 81
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Verification of the BISON fuel performance codeHales, J.D. / Novascone, S.R. / Spencer, B.W. / Williamson, R.L. / Pastore, G. / Perez, D.M. et al. | 2014
- 91
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Measurement of isothermal temperature reactivity coefficient at research reactor with IRT-4M fuelBily, Tomas / Sklenka, Lubomir et al. | 2014
- 97
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On an analytical representation for the solution of the neutron point kinetics equation free of stiffnessWollmann da Silva, M. / Bogado Leite, S. / Vilhena, M.T. / Bodmann, B.E.J. et al. | 2014
- 103
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Technical design and engineering prototype experiment of active magnetic bearing for helium blower of HTR-PMYang, Guojun / Shi, Zhengang / Mo, Ni et al. | 2014
- 111
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A fuel depletion analysis of the MSRE and three conceptual small molten-salt reactors for Mo-99 productionSheu, R.J. / Chao, C.C. / Feynberg, O. / Liu, Y.-W.H. et al. | 2014
- 118
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Experimental verification on the integrity and performance of the passive residual heat removal system for a SMART design with VISTA-ITLMin, Byung-Yeon / Park, Hyun-Sik / Shin, Yong-Chul / Yi, Sung-Jae et al. | 2014
- 125
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Effectiveness of source term optimization for higher disposal density of spent fuels in a deep geological repositoryCho, Dong-Keun / Jeong, Jongtae et al. | 2014
- 130
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Development of the HELIOS/CAPP code system for the analysis of pebble type VHTR coresLee, Hyun Chul / Han, Tae Young / Jo, Chang Keun / Noh, Jae Man et al. | 2014
- 145
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Coupling of COBAYA3/SUBCHANFLOW inside the NURESIM platform and validation using selected benchmarksCalleja, M. / Sanchez, V. / Jimenez, J. / Imke, U. / Stieglitz, R. / Macián, R. et al. | 2014
- 159
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An assessment of prompt neutron reproduction time in a reflector dominated fast critical system: ELECTRASuvdantsetseg, E. / Wallenius, J. et al. | 2014
- 166
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SAC-CFR computer code verification with Experimental Breeder Reactor II loss-of-primary-flow-without-scram tests dataGuo, Chao / Lu, Daogang / Sui, Danting / Zhang, Xun et al. | 2014
- 174
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The complex nonlinear dynamics in the multiple boiling channels coupling with multi-point reactors with constant total flow rateLee, Jin Der / Pan, Chin et al. | 2014
- 190
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Experimental and numerical testing of an innovative steam generator tube plugging procedureNicolici, S. / Gyongyosi, T. / Prisecaru, I. et al. | 2014
- 198
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Monitoring and preventing numerical oscillations in 3D simulations with coupled Monte Carlo codesKotlyar, D. / Shwageraus, E. et al. | 2014
- 206
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Improvement on the calculation of D2O moderated critical systems with new thermal neutron scattering librariesMárquez Damián, J.I. / Granada, J.R. / Roubtsov, D. et al. | 2014
- 211
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Sensitivity analysis of CHF parameters under flow instability by using a neural network methodLi, Jingjing / Zhou, Tao / Ju, Zhongyun / Huo, Qijun / Xiao, Zejun et al. | 2014
- 217
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Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kineticsSartori, Alberto / Baroli, Davide / Cammi, Antonio / Chiesa, Davide / Luzzi, Lelio / Ponciroli, Roberto / Previtali, Ezio / Ricotti, Marco Enrico / Rozza, Gianluigi / Sisti, Monica et al. | 2014
- 230
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Economic analysis of two nuclear fuel cycle optionsZhou, Chaoran / Liu, Xuegang / Gu, Zhongmao / Wang, Yugang et al. | 2014
- 237
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Design and analysis of operation performance of parameters of the integrated valve under the high temperature conditionLiu, Qian-feng / Bo, Han-liang et al. | 2014
- 245
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Stability improvement of noise analysis method in the case of random noise contamination for subcriticality measurementsKong, Chidong / Lee, Deokjung / Lee, Eunki et al. | 2014
- 254
-
Three-dimensional single-channel thermal analysis of fully ceramic microencapsulated fuel via two-temperature homogenized modelLee, Yoonhee / Cho, Nam Zin et al. | 2014
- 272
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Large scale applicability of a Fully Adaptive Non-Intrusive Spectral Projection technique: Sensitivity and uncertainty analysis of a transientPerkó, Zoltán / Lathouwers, Danny / Kloosterman, Jan Leen / van der Hagen, Tim et al. | 2014
- 293
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On-line method to identify control rod drops in Pressurized Water ReactorsSouza, T.J. / Martinez, A.S. / Medeiros, J.A.C.C. / Palma, D.A.P. / Gonçalves, A.C. et al. | 2014
- 298
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Boiling heat transfer and dryout in helically coiled tubes under different pressure conditionsChung, Young-Jong / Bae, Kyoo-Hwan / Kim, Keung Koo / Lee, Won-Jae et al. | 2014
- 304
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Alternative off-site power supply improves nuclear power plant safetyGjorgiev, Blaže / Volkanovski, Andrija / Kančev, Duško / Čepin, Marko et al. | 2014
- 313
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Development of Monte Carlo-based pebble bed reactor fuel management codeSetiadipura, Topan / Obara, Toru et al. | 2014
- 322
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Numerical analysis of freezing controlled penetration behavior of the molten core debris in an instrument tube with MPSChen, Ronghua / Oka, Yoshiaki et al. | 2014
- 333
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UWB1 – Fast nuclear fuel depletion codeLovecký, M. / Piterka, L. / Prehradný, J. / Škoda, R. et al. | 2014
- 340
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An evaluation on the cutting technologies for decommissioning of the large cylinder parts in the major components of NPPsJeong, KwanSeong / Choi, ByungSeon / Moon, JeiKwon / Hyun, Dongjun / Lee, Jonghwan / Kim, IkJune / Kim, GeunHo / Seo, JaeSeok / Jeong, SeongYoung / Lee, JungJun et al. | 2014
- 343
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Design of a model predictive load-following controller by discrete optimization of control rod speed for PWRsKim, Jae Hwan / Park, Soon Ho / Na, Man Gyun et al. | 2014
- 352
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A simplified approach to evaluating severe accident source term for PWRHuang, Gaofeng / Tong, Lili / Cao, Xuewu et al. | 2014
- 361
-
Dynamic sequence analysis for feed-and-bleed operation in an OPR1000Kim, Bo Gyung / Yoon, Ho Joon / Kim, Sang Ho / Kang, Hyun Gook et al. | 2014
- 376
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Numerical modelling of low-Reynolds number direct contact condensation in a suppression pool test facilityPatel, G. / Tanskanen, V. / Kyrki-Rajamäki, R. et al. | 2014
- 388
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The max–min ant system and tabu search for pressurized water reactor loading pattern designLin, Chaung / Chen, Ying-Hsiu et al. | 2014
- 399
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Numerical simulations of air–water cap-bubbly flows using two-group interfacial area transport equationWang, Xia / Sun, Xiaodong et al. | 2014
- 411
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On-the-fly sampling of temperature-dependent thermal neutron scattering data for Monte Carlo simulationsPavlou, Andrew T. / Ji, Wei et al. | 2014
- 427
-
Comparisons of prediction methods for peak cladding temperature and effective thermal conductivity in spent fuel assemblies of transportation/storage casksKim, Hyungjin / Kwon, Oh Joon / Kang, Gyeong-Uk / Lee, Dong-Gyu et al. | 2014
- 436
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Evaluation of the performance of peridotite aggregates for radiation shielding concreteWang, Jinjun / Li, Guofeng / Meng, Dechuan et al. | 2014
- 440
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A novel extension of chord length sampling method for TRISO-type fueled reactor applicationsLiang, Chao / Ji, Wei et al. | 2014
- 451
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G4-STORK: A Geant4-based Monte Carlo reactor kinetics simulation codeRussell, Liam / Buijs, Adriaan / Jonkmans, Guy et al. | 2014
- 462
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Calculation of radiation heat transfer view factors among fuel rod bundles based on CFD methodYang, Lei / Chen, Wenzhen / Luo, Lei / Zhao, Xinwen et al. | 2014
- 467
-
Neutronic and thermal hydraulic analyses of LEU targets irradiated in a research reactor for Molybdenum-99 productionJo, Daeseong / Lee, Kyung-Hoon / Kim, Hong-Chul / Chae, Heetaek et al. | 2014
- 475
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The scenario-based system of workers training to prevent accidents during decommissioning of nuclear facilitiesJeong, KwanSeong / Choi, ByungSeon / Moon, JeiKwon / Hyun, DongJun / Lee, JongHwan / Kim, IkJune / Kim, GeunHo / Seo, JaeSeok et al. | 2014
- 480
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A new concept of Monte Carlo kinetics parameter calculation using complex-valued perturbationYamamoto, Toshihiro / Sakamoto, Hiroki et al. | 2014
- IFC
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Editorial board| 2014