Analyses of decay heat removal tests with PRACS and DRACS of a sodium loop using the NETFLOW++ code (English)
- New search for: Mochizuki, Hiroyasu
- Further information on Mochizuki, Hiroyasu:
- https://orcid.org/0000-0002-6030-4781
- New search for: Mochizuki, Hiroyasu
- Further information on Mochizuki, Hiroyasu:
- https://orcid.org/0000-0002-6030-4781
In:
Nuclear Engineering and Design
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322
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345-359
;
2017
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ISSN:
- Article (Journal) / Electronic Resource
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Title:Analyses of decay heat removal tests with PRACS and DRACS of a sodium loop using the NETFLOW++ code
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Contributors:Mochizuki, Hiroyasu ( author )
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Published in:Nuclear Engineering and Design ; 322 ; 345-359
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Publisher:
- New search for: Elsevier B.V.
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Publication date:2017-07-12
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Size:15 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:AC , air cooler , CFD , computational fluid dynamics , DHX , direct heat exchanger , DRACS , direct reactor auxiliary cooling system , FBR , fast breeder reactor , HTS , heat transport system , IHX , intermediate heat exchanger , IRACS , intermediate reactor auxiliary cooling system , JSFR , Japan Sodium-cooled Fast Reactor , PLANDTL , Plant Dynamics Test Loop , PRACS , primary reactor auxiliary cooling system , SA , subassembly , Sodium loop , Air cooler , Decay heat removal tests , Analyses , NETFLOW++ code
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Source:
Table of contents – Volume 322
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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Multi objective loading pattern optimization of PWRs with Fuzzy logic controller based Gravitational Search AlgorithmAghaie, M. / Mahmoudi, S.M. et al. | 2017
- 14
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Mechanical Shim core operational strategy designed for CPR1000 nuclear power plantZhang, Y.W. / Zeng, W.J. et al. | 2017
- 27
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Thermal properties of prototype corium of fast reactorMukhamedov, N. / Skakov, M. / Deryavko, I. / Kukushkin, I. et al. | 2017
- 32
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Thermal mixing of flows in horizontal T-junctions with low branch velocitiesSelvam, P. Karthick / Kulenovic, Rudi / Laurien, Eckart / Kickhofel, John / Prasser, Horst-Michael et al. | 2017
- 55
-
Investigations of natural convection and circulation in Passive Moderator Cooling System of an advanced reactor in a scaled test facilityKumar, Mukesh / Nayak, A.K. / Joshi, J.B. et al. | 2017
- 68
-
Nuclear containment structure subjected to commercial aircraft crash and subsequent vibrations and fireLin, Feng / Tang, Hai et al. | 2017
- 81
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Experimental & analytical study of passive thermal sensing system developed for cooling water injection into AHWR core catcherSultan, Tipu / Sapra, M.K. / Kundu, S. / Kadam, A.V. / Kulkarni, Parimal P. / Rama Rao, A. et al. | 2017
- 92
-
Numerical study on the effect of the diffuser blade trailing edge profile on flow instability in a nuclear reactor coolant pumpNi, Dan / Yang, Minguan / Gao, Bo / Zhang, Ning / Li, Zhong et al. | 2017
- 104
-
Development and validation of a PWR on-line power-distribution monitoring system NECP-ONIONLi, Zhuo / Cao, Liangzhi / Wu, Hongchun / Li, Yunzhao / Liu, Zhouyu / Shen, Wei / Yang, Wen et al. | 2017
- 116
-
Analysis of composition and temperature of debris bed based on settling characteristics of relocated core debris in pool type SFRMuthu Saravanan, S. / David, Dijo K. / Mangarjuna Rao, P. / Nashine, B.K. / Selvaraj, P. et al. | 2017
- 131
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Control rod drop dynamic analysis in the TMSR – SF1 based on numerical simulation and experimentLin, Zuokang / Zhai, Lifang / Zhu, Lin / Wang, Xiao / Zhang, Xiaochun / Cao, Yun / Wang, Naxiu et al. | 2017
- 138
-
Effect of second hardening on floor response spectrum of a base-isolated nuclear power plantJung, Jae-Wook / Jang, Heung Woon / Kim, Jung Han / Hong, Jung-Wuk et al. | 2017
- 148
-
Parametric analyses of major nuclear components and reinforced concrete structures under FCI-induced explosive conditionKim, Seung Hyun / Chang, Yoon-Suk / Cho, Yong-Jin et al. | 2017
- 159
-
Effect of ion exchange membrane on the removal efficiency of continuous electrodeionization (CEDI) during low level radioactive wastewater treatmentLi, Fuzhi / Zhang, Xue / Zhao, Xuan et al. | 2017
- 165
-
CFD-simulation of boiling in a heated pipe including flow pattern transitions using the GENTOP conceptHöhne, T. / Krepper, E. / Montoya, G. / Lucas, D. et al. | 2017
- 177
-
Comparative study of turbulence model predictions of upward supercritical fluid flow in vertical rod bundle subchannelsBergmann, Cale M. / Ormiston, Scott J. / Chatoorgoon, Vijay et al. | 2017
- 192
-
Extending the reactivity initiated accident (RIA) fuel performance code SCANAIR for boiling water reactor (BWR) applicationsArkoma, Asko et al. | 2017
- 204
-
Experimental studies on metallic fuel relocation in a single-pin core structure of a sodium-cooled fast reactorKim, Taeil / Harbaruk, Dzmitry / Gerardi, Craig / Farmer, Mitchell / Chang, Yoon Il et al. | 2017
- 215
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Effect of temperature, chloride and dissolved oxygen concentration on the open circuit and transpassive potential values of 316L stainless steel at high-temperature pressurized waterArjmand, Farzin / Zhang, Lefu / Wang, Jiamei et al. | 2017
- 227
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Hyperbolicity and numerics in SYS-TH codes: The FONESYS point of viewAhn, S.H. / Aksan, N. / Austregesilo, H. / Bestion, D. / Chung, B.D. / Coscarelli, E. / D'Auria, F. / Emonot, P. / Gandrille, J.L. / Sauvage, J.Y. et al. | 2017
- 240
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Experimental investigation of 3-D ERVC process for IVR strategy – CHF limits and visualization of boiling phenomenaLu, Wei / Cheung, F.B. / Hu, Teng / Liu, Hao / Zhang, Xiang / Chang, Huajian et al. | 2017
- 256
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Fatigue assessment for seismic loads considering material degradation due to stress corrosion crackingKamaya, Masayuki et al. | 2017
- 266
-
Effect of user interface layout on the operators’ mental workload in emergency operating procedures in nuclear power plantsYan, Shengyuan / Tran, Cong Chi / Chen, Yu / Tan, Ke / Habiyaremye, Jean Luc et al. | 2017
- 277
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Numerical investigation of turbulent natural convection in the lower plenum of sodium cooled fast reactor under core relocation scenarioDavid, Dijo K. / Mangarjuna Rao, P. / Nashine, B.K. / Selvaraj, P. et al. | 2017
- 291
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Variance reduction for global response problem based on forward Monte Carlo calculationShi, Tao / Ma, Jimin / Huang, Hongwen / Qiu, Youheng / Zeng, Herong / Li, Zhenghong / Qian, Dazhi et al. | 2017
- 301
-
A numerical simulation method for molten material behavior in nuclear reactorsYamashita, Susumu / Ina, Takuya / Idomura, Yasuhiro / Yoshida, Hiroyuki et al. | 2017
- 313
-
Probabilistic and non-probabilistic failure assessment curves of primary coolant pipe contained internal circumferential surface crack in pressurized water reactor nuclear power plantTian, Yun / Zhang, Guodong / Miao, Xinting / Wen, Leilei / Qu, Wenjun / Xue, Fei / Zhou, Changyu et al. | 2017
- 324
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Delayed hydride cracking assessment of PWR spent fuel during dry storageHong, Jong-Dae / Kim, Hyo-Chan / Kim, Ju-Seong / Yang, Yong-Sik / Kook, Dong-Hak et al. | 2017
- 331
-
Thermophysical properties of Alloy 709Smith, D.S. / Lybeck, N.J. / Wright, J.K. / Wright, R.N. et al. | 2017
- 336
-
Gaseous swelling of U3Si2 during steady-state LWR operation: A rate theory investigationMiao, Yinbin / Gamble, Kyle A. / Andersson, David / Ye, Bei / Mei, Zhi-Gang / Hofman, Gerard / Yacout, Abdellatif M. et al. | 2017
- 345
-
Analyses of decay heat removal tests with PRACS and DRACS of a sodium loop using the NETFLOW++ codeMochizuki, Hiroyasu et al. | 2017
- 360
-
Improvement of separator performance with modified pick-off ring and swirlerFunahashi, H. / Hayashi, K. / Hosokawa, S. / Tomiyama, A. et al. | 2017
- 368
-
Extension of the sub-channel code ANTEO+ to the mixed convection regimeLodi, F. / Grasso, G. et al. | 2017
- 379
-
In-structure response spectra considering nonlinearity of RCC structures: Experiments and analysisKothari, P. / Parulekar, Y.M. / Reddy, G.R. / Gopalakrishnan, N. et al. | 2017
- 397
-
Thermal-hydraulic analysis of the LORELEI test design by means of CATHARE2 V2.5Battistoni, P. / Tarabelli, D. / Ferry, L. / Gonnier, C. / Manservisi, S. / Sumini, M. et al. | 2017
- 412
-
Thermal stress analysis of silo in radioactive waste repository considering construction conditionsCha, Sang-Lyul / Lee, Yun / Kim, Jin-Keun et al. | 2017
- 427
-
PLAYGO: Program for BWR LP-CRP Automatic Yielding by using GA OptimizationChen, Chien-Hsiang / Lin, Po-Feng / Huang, Yao-Nan et al. | 2017
- 444
-
Nodal models of Pressurized Water Reactor core for control purposes – A comparison studyPuchalski, Bartosz / Rutkowski, Tomasz A. / Duzinkiewicz, Kazimierz et al. | 2017
- 464
-
Comparative analysis of different fidelity fuel performance models for fuel temperature predictionsRaja, Faisal / Mankosa, Michael / Avramova, Maria et al. | 2017
- 474
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Numerical study on cooling characteristics in granular and liquid spallation targetsHu, Liang / Zhang, Yapei / Su, G.H. / Tian, Wenxi / Qiu, Suizheng et al. | 2017
- 485
-
On the use of a dedicated ballast pellet for a prompt self-ejection mechanism after a temperature transient in lead-cooled fast reactorsArias, Francisco J. et al. | 2017
- 492
-
Radiological assessment of the decontaminated and decommissioned Korea Research Reactor-1 buildingMin, Jae Seong / Lee, Ki Won / Kim, Hee Reyoung / Lee, Choong Wie et al. | 2017
- 497
-
Resuspension of multilayer graphite dust particles in a high temperature gas-cooled reactorZhang, Tianqi / Yu, Suyuan / Peng, Wei / Sun, Qi / Jiang, Yueyuan / Shi, Qian et al. | 2017
- 504
-
Interpretation of energy deposition data from historical operation of the transient test facility (TREAT)DeHart, Mark D. / Baker, Benjamin A. / Ortensi, Javier et al. | 2017
- 522
-
Modeling and analysis of molten fuel vaporization and expansion for a sodium fast reactor severe accidentManchon, X. / Bertrand, F. / Marie, N. / Lance, M. / Schmitt, D. et al. | 2017
- 536
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A proposal for an alternative use of prompt-Self Powered Neutron Detectors: Online spectral-deconvolution for monitoring high-intensity neutron flux in LFRsLepore, Luigi / Remetti, Romolo / Pietropaolo, Antonino et al. | 2017
- 547
-
Flow-induced vibration analysis of a helical coil steam generator experiment using large eddy simulationYuan, Haomin / Solberg, Jerome / Merzari, Elia / Kraus, Adam / Grindeanu, Iulian et al. | 2017
- 563
-
Heat deposition analysis for the High Flux Isotope Reactor’s HEU and LEU core modelsDavidson (née Sunny), Eva E. / Betzler, Benjamin R. / Chandler, David / Ilas, Germina et al. | 2017
- 577
-
Numerical simulations for determination of minimum representative bundle size in wire wrapped tube bundlesBrockmeyer, Landon / Carasik, Lane B. / Merzari, Elia / Hassan, Yassin et al. | 2017
- 591
-
Investigation of thermo mechanical behaviour in the scaled PHWR stepped calandria vessel during severe accidentPrasad, Sumit V. / Nayak, A.K. et al. | 2017