Review study of virtual reality techniques used at nuclear issues with emphasis on Brazilian research (Englisch)
- Neue Suche nach: da Silva, Márcio Henrique
- Neue Suche nach: Legey, Ana Paula
- Neue Suche nach: Mól, Antônio Carlos de A.
- Neue Suche nach: da Silva, Márcio Henrique
- Neue Suche nach: Legey, Ana Paula
- Neue Suche nach: Mól, Antônio Carlos de A.
In:
Annals of Nuclear Energy
;
87
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192-197
;
2015
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ISSN:
- Aufsatz (Zeitschrift) / Elektronische Ressource
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Titel:Review study of virtual reality techniques used at nuclear issues with emphasis on Brazilian research
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Beteiligte:da Silva, Márcio Henrique ( Autor:in ) / Legey, Ana Paula ( Autor:in ) / Mól, Antônio Carlos de A. ( Autor:in )
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Erschienen in:Annals of Nuclear Energy ; 87 ; 192-197
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Verlag:
- Neue Suche nach: Elsevier Ltd
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Erscheinungsdatum:20.08.2015
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Format / Umfang:6 pages
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ISSN:
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DOI:
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Medientyp:Aufsatz (Zeitschrift)
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Format:Elektronische Ressource
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Sprache:Englisch
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Schlagwörter:
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Datenquelle:
Inhaltsverzeichnis – Band 87
Zeige alle Jahrgänge und Ausgaben
Die Inhaltsverzeichnisse werden automatisch erzeugt und basieren auf den im Index des TIB-Portals verfügbaren Einzelnachweisen der enthaltenen Beiträge. Die Anzeige der Inhaltsverzeichnisse kann daher unvollständig oder lückenhaft sein.
- 1
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Risk assessment on abnormal accidents from human errors during decommissioning of nuclear facilitiesJeong, KwanSeong / Choi, ByungSeon / Moon, JeiKwon / Hyun, DongJun / Lee, JongHwan / Kim, IkJune / Kim, GeunHo / Kang, ShinYoung et al. | 2015
- 1
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A method for the continuous monitoring of reactivity in subcritical source-driven systemsDulla, S. / Nervo, M. / Ravetto, P. et al. | 2014
- 7
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Establishment of the hazard reduction methodology to be taken into account for safety assessment during decommissioning of nuclear facilitiesJeong, KwanSeong / Choi, ByungSeon / Moon, JeiKwon / Hyun, Dongjun / Lee, Jonghwan / Kim, IkJune / Kim, GeunHo / Kang, ShinYoung et al. | 2015
- 12
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DRAGON5 and DONJON5, the contribution of École Polytechnique de Montréal to the SALOME platformHébert, Alain et al. | 2015
- 16
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A tightly coupled scheme for neutronics and thermal–hydraulics using open-source softwareWu, Hsingtzu / Rizwan-uddin et al. | 2015
- 21
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Qualification of gadolinium burnable poison: Interpretation of MELUSINE/GEDEON-II spent fuel analysisBernard, David / Santamarina, Alain et al. | 2015
- 23
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Impact of power density profile on passive decay heat removal in prismatic HTGRSambuu, Odmaa / Obara, Toru et al. | 2015
- 30
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3D/2D rotational plane slicing method for 3D whole-core transport calculationYoo, Han Jong / Cho, Nam Zin et al. | 2015
- 34
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New aspects in the implementation of the quasi-static method for the solution of neutron diffusion problems in the framework of a nodal methodCaron, D. / Dulla, S. / Ravetto, P. et al. | 2015
- 39
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Design and neutronic investigation of the Nano fluids application to VVER-1000 nuclear reactor with dual cooled annular fuelAnsarifar, G.R. / Ebrahimian, M. et al. | 2015
- 48
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Review calculations for the OECD/NEA Burn-up Credit Criticality Safety BenchmarkHerrero, José J. / Vasiliev, Alexander / Pecchia, Marco / Ferroukhi, Hakim / Caruso, Stefano et al. | 2015
- 49
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Optimized tracking strategies for step MOC calculations in extruded 3D axial geometriesSciannandrone, Daniele / Santandrea, Simone / Sanchez, Richard et al. | 2015
- 58
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Determination of the maximum speed of WWER-1000 nuclear reactor control rodsKhoshahval, Farrokh / Ahdavi, Abdol Aziz. et al. | 2015
- 61
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MRT methodologies for real-time simulation of nonproliferation and safeguards problemsHaghighat, Alireza / Royston, Katherine / Walters, William et al. | 2015
- 68
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Recent advances in accurate neutronic calculation of GEN-3 LWR reactorsSantamarina, A. / Bernard, D. / Blaise, P. / Leconte, P. / Vaglio, C. / Vidal, J.-F. et al. | 2015
- 69
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Theoretical basis of quantification for layer of protection analysis (LOPA)Jin, Jianghong / Shuai, Bing / Wang, Xiaodong / Zhu, Zuogang et al. | 2015
- 74
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Sodium flow measurement in large pipelines of sodium cooled fast breeder reactors with bypass type flow metersRajan, K.K. / Jayakumar, T. / Aggarwal, P.K. / Vinod, V. et al. | 2015
- 76
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A neutronic benchmark specification and COMET solution for the Advanced Burner Test ReactorUlmer, Richard M. / Rahnema, Farzad / Connolly, Kevin John et al. | 2015
- 81
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COPRA experiments on natural convection heat transfer in a volumetrically heated slice pool with high Rayleigh numbersZhang, Luteng / Zhang, Yapei / Zhou, Yukun / Su, G.H. / Tian, Wenxi / Qiu, Suizheng et al. | 2015
- 89
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Nodal collocation method for the multidimensional equations applied to neutron transport source problemsCapilla, M.T. / Talavera, C.F. / Ginestar, D. / Verdú, G. et al. | 2015
- 101
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Directional diffusion coefficients and leakage-corrected discontinuity factors: Implementation in Serpent and testsDorval, E. et al. | 2015
- 107
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Monte Carlo analysis of KRITZ-2 critical benchmarks on the reactivity temperature coefficient using ENDF/B-VII.1 and JENDL-4.0 nuclear data librariesEl Ouahdani, S. / Boukhal, H. / Erradi, L. / Chakir, E. / El Bardouni, T. / Hajjaji, O. / Boulaich, Y. / Benaalilou, K. / Kaddour, M. et al. | 2015
- 113
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New derivation of Blackshow–Murrays formula for the Doppler-broadened scattering kernel and calculation of the angular moments via Lagrange interpolationSanchez, Richard / Previti, Alberto / Mostacci, Domiziano et al. | 2015
- 126
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Quantifying the effects of depletion parameters on the PWR spent fuel reactivity based on nuclide sensitivity coefficientsSheu, Rong-Jiun / Lee, Min-Hua / Liang, Jenq-Horng et al. | 2015
- 137
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A new SPn theory formulation with self-consistent physical assumptions on angular fluxChao, Yung-An et al. | 2015
- 145
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Experimental study on fundamental phenomena in HTGR small break air-ingress accidentKim, Jae Soon / Hwang, Jin-Seok / Kim, Eung Soo / Kim, Byung Jun / Oh, Chang Ho et al. | 2015
- 157
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Pressure wave propagation phenomena in the pipe system of a nuclear power plantYi, Sung-Jae / Chung, Moon-Sun / Toth, Ivan et al. | 2015
- 162
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CAD-based Monte Carlo automatic modeling method based on primitive solidWang, Dong / Song, Jing / Yu, Shengpeng / Long, Pengcheng / Wang, Yongliang et al. | 2015
- 167
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Depletion benchmarks calculation of random media using explicit modeling approach of RMCLiu, Shichang / She, Ding / Liang, Jin-gang / Wang, Kan et al. | 2015
- 176
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Numerical simulation and experimental verification of microstructure evolution in large forged pipe used for AP1000 nuclear power plantsWang, Shenglong / Yang, Bin / Zhang, Mingxian / Wu, Huanchun / Peng, Jintao / Gao, Yang et al. | 2015
- 186
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Passive Non-Destructive Assay based on gamma-ray spectrometry to verify UO2 samples in the form of powder and pelletTohamy, M. / Abd El-Ghany, S. / El-Minyawi, S.M. / Fayez-Hassan, M. / El-hakim, Elham H. / El-Mongy, Sayed A. / Comsan, M.N.H. et al. | 2015
- 192
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Review study of virtual reality techniques used at nuclear issues with emphasis on Brazilian researchda Silva, Márcio Henrique / Legey, Ana Paula / Mól, Antônio Carlos de A. et al. | 2015
- 198
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A multi-physics reduced order model for the analysis of Lead Fast Reactor single channelSartori, Alberto / Cammi, Antonio / Luzzi, Lelio / Rozza, Gianluigi et al. | 2015
- 209
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Heat transfer of water flowing upward in vertical annuli with spacers at high pressure conditionsZhao, M. / Gu, H.Y. / Li, H.B. / Cheng, X. et al. | 2015
- 217
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Transient identification by clustering based on Integrated Deterministic and Probabilistic Safety Analysis outcomesDi Maio, Francesco / Vagnoli, Matteo / Zio, Enrico et al. | 2015
- 228
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Computing eigenvalue sensitivity coefficients to nuclear data by adjoint superhistory method and adjoint Wielandt method implemented in RMC codeQiu, Yishu / Shang, Xiaotong / Tang, Xiao / Liang, Jingang / Wang, Kan et al. | 2015
- 242
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Thermal neutron scattering cross sections of beryllium and magnesium oxidesAl-Qasir, Iyad / Jisrawi, Najeh / Gillette, Victor / Qteish, Abdallah et al. | 2015
- 252
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Stability analysis of the Backward Euler time discretization for the pin-resolved transport transient reactor calculationZhu, Ang / Xu, Yunlin / Downar, Thomas et al. | 2015
- 267
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Re-evaluation of spent nuclear fuel assay data for the Three Mile Island unit 1 reactor and application to code validationGauld, I.C. / Giaquinto, J.M. / Delashmitt, J.S. / Hu, J. / Ilas, G. / Haverlock, T.J. / Romano, C. et al. | 2015
- 282
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Solving the multigroup integro-differential equation of the neutron diffusion kinetics in 3D-Cartesian geometryQuintero-Leyva, Barbaro et al. | 2015
- 290
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Human error and the associated recovery probabilities for soft control being used in the advanced MCRs of NPPsJang, Inseok / Jung, Wondea / Seong, Poong Hyun et al. | 2015
- 299
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Small break LOCA analysis without emergency core cooling systems using the RELAP5/SCDAP code in VVER-1000 reactorSalehi, Mohsen / Jahanfarnia, Gholamreza et al. | 2015
- 308
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Control rod drop transient analysis with the coupled parallel code pCTF-PARCSv2.7Ramos, Enrique / Roman, Jose E. / Abarca, Agustín / Miró, Rafael / Bermejo, Juan A. et al. | 2015
- 318
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Micro-Pocket Fission Detectors (MPFDs) for in-core neutron detectionReichenberger, Michael A. / Unruh, Troy C. / Ugorowski, Philip B. / Ito, Takashi / Roberts, Jeremy A. / Stevenson, Sarah R. / Nichols, Daniel M. / McGregor, Douglas S. et al. | 2015
- 324
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Evaluation method of iodine re-evolution from an in-containment water pool after a loss of coolant accident, Part I: pH estimation of a solution with various chemicalsKim, Tae Hyeon / Jeong, Ji Hwan et al. | 2015
- 331
-
Characterization of velocity and temperature fields in a 217 pin wire wrapped fuel bundle of sodium cooled fast reactorNaveen Raj, M. / Velusamy, K. et al. | 2015
- 350
-
Development of a portable heavy-water leak sensor based on laser absorption spectroscopyLee, Lim / Park, Hyunmin / Kim, Taek-Soo / Kim, Minho / Jeong, Do-Young et al. | 2015
- 356
-
Assessment of assembly homogenized two-steps core dynamic calculations using direct whole core transport solutionsHursin, Mathieu / Downar, Thomas J. / Yoon, Joo Il / Joo, Han Gyu et al. | 2015
- 366
-
Code improvement and model validation for Ascó-II Nuclear Power Plant model using a coupled 3D neutron kinetics/thermal–hydraulic codePericas, R. / Ivanov, K. / Reventós, F. / Batet, L. et al. | 2015
- 375
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PSA model with consideration of the effect of fault-tolerant techniques in digital I&C systemsLee, Seung Jun / Jung, Wondea / Yang, Joon-Eon et al. | 2015
- 385
-
Introducing time in derivation of the scaling factor for MCNP criticality calculationsYang, Yang / Chen, Min / Lu, Chunhai et al. | 2015
- 388
-
CRUD, boron, and burnable absorber layer 2-D modeling requirements using MOC neutron transportWalter, Daniel J. / Manera, Annalisa et al. | 2015
- 400
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Modeling the thermal stress of heat transfer tubes with tube support plate gaps in a steam generatorSun, Baozhi / Shi, Jianxin / Yang, Liu / Yang, Longbin / Li, Yanjun / Liu, Shanghua et al. | 2015
- 411
-
Identification and categorisation of safety issues for ESNII reactor concepts. Part I: Common phenomena related to materialsTuček, K. / Hermsmeyer, S. / Ammirabile, L. / Blanc, D. / Wattelle, E. / Burgazzi, L. / Frogheri, M. / Mansani, L. / Ehster-Vignoud, S. / Carluec, B. et al. | 2015
- 426
-
Performance of iodide vapour absorption in the venturi scrubber working in self-priming modeZhou, Yanmin / Sun, Zhongning / Gu, Haifeng / Miao, Zhuang et al. | 2015
- 435
-
Comparison of critical flow models for SBLOCA tests of the ATLAS facilityKim, Yeon-Sik / Kwon, Tae-Soon / Bae, Sung-Won / Euh, Dong-Jin / Park, Hyun-Sik / Cho, Seok / Yi, Sung-Jae / Kang, Kyoung-Ho / Choi, Ki-Yong et al. | 2015
- 443
-
System scaling analysis for modeling small break LOCA using the FULL SPECTRUM LOCA evaluation modelLiao, Jun et al. | 2015
- 454
-
Numerical analysis of the dust distribution during LOVATong, L.L. et al. | 2015
- 462
-
Simulation of the airborne radioactive substance distribution and monitoring of coolant leakage in a typical Nuclear Reactor ContainmentZheng, Ya / Hu, Dongshuai / Dai, Yiping et al. | 2015
- 471
-
Design concept for a small pebble bed reactor with ROX fuelHo, Hai Quan / Obara, Toru et al. | 2015
- 479
-
The neutron point kinetics equation: Suppression of fractional derivative effects by temperature feedbackSchramm, M. / Bodmann, B.E.J. / Alvim, A.C.M. / Vilhena, M.T. et al. | 2015
- 486
-
The application of transient analysis code to estimation of total released energy in a two-fuel-solution-tank systemKikuchi, Haruka / Obara, Toru et al. | 2015
- 494
-
Criticality validation of SuperMC with ICSBEPZhang, Binhang / Song, Jing / Sun, Guangyao / Chen, Chaobin / Hu, Liqin et al. | 2015
- 500
-
Ultimate analysis of PWR prestressed concrete containment under long-term prestressing lossHu, Hsuan-Teh / Lin, Jun-Xu et al. | 2015
- 511
-
Development strategy and conceptual design of China Lead-based Research ReactorWu, Yican / Bai, Yunqing / Song, Yong / Huang, Qunying / Zhao, Zhumin / Hu, Liqin et al. | 2015
- 517
-
High Conversion Th–U233 fuel for current generation of PWRs: Part III – Fuel availability and utilization considerationsBaldova, D. / Fridman, E. / Shwageraus, E. et al. | 2015
- 527
-
Flow and heat transfer in laminar–turbulent transitional flow regime under rolling motionYuan, Hongsheng / Tan, Sichao / Zhuang, Nailiang / Lan, Shu et al. | 2015
- 537
-
Impact of proof test interval and coverage on probability of failure of safety instrumented functionJin, Jianghong / Pang, Lei / Hu, Bin / Wang, Xiaodong et al. | 2015
- 541
-
Investigations of single-phase flow mixing characteristics in a wire-wrapped 37-pin bundle for a sodium-cooled fast reactorKim, Hyungmo / Bae, Hwang / Ko, Yung Joo / Choi, Sun Rock / Chang, Seok-Kyu / Lee, Dong-Won / Choi, Hae Seob / Euh, Dong-Jin / Lee, Hyeong-Yeon et al. | 2015
- 547
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Development of a PWR-W GOTHIC 3D model for containment accident analysisBocanegra, Rafael / Jimenez, Gonzalo / Fernández-Cosials, Mikel Kevin et al. | 2015
- 561
-
Three higher order analytical nodal methods for multigroup neutron diffusion equationsGuessous, Najib et al. | 2015
- 569
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Nanoscopic designs of radiological protection in environmental scale for the Fukushima nuclear accident: Strategy by dispersion, dissolution, and filtrationWoo, Tae Ho et al. | 2015
- 575
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Transient analyses of the Jordanian 5MW research reactor under LOEP accidentAl-Yahia, Omar S. / Lee, Ho / Jo, Daeseong et al. | 2015
- 584
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Monte Carlo modeling of the Pakistan Research Reactor-1 (PARR-1)Ali, M. Rizwan / Khan, R. / Chaudri, K.S. / Stummer, T. et al. | 2015
- 591
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A comparison of Monte Carlo methods for neutron leakage at assembly levelDorval, E. et al. | 2015
- 601
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Study of graphite reactivity worth on well-defined cores assembled on LR-0 reactorKošťál, Michal / Rypar, Vojtěch / Milčák, Ján / Juříček, Vlastimil / Losa, Evžen / Forget, Benoit / Harper, Sterling et al. | 2015
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Thermal–hydraulic modeling and transient analysis of helium-cooled tungsten target coupled with ADS corePeng, Tianji / Zhou, Zhiwei / Xiao, Sicong / Sheng, Xuanyu / Gu, Long et al. | 2015
- 621
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Adoption of nitrogen power conversion system for small scale ultra-long cycle fast reactor eliminating intermediate sodium loopSeo, Seok Bin / Seo, Han / Bang, In Cheol et al. | 2015
- 630
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and formulations of the linear transport equation in heterogeneous mediaCoppa, G. et al. | 2015
- 637
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Improvements to the Transmutation Trajectory Analysis of depletion evaluationHuang, Kai / Wu, Hongchun / Cao, Liangzhi / Li, Yunzhao / Shen, Wei et al. | 2015
- 648
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Evaluation of burnable absorber rods effect on neutronic performance in fuel assembly of WWER-1000 reactorKhoshahval, Farrokh / Foroutan, Shima Sheikh / Zolfaghari, Ahmad / Minuchehr, Hamid et al. | 2015
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A unified methodology for single- and multiobjective in-core fuel management optimisation based on augmented Chebyshev scalarisation and a harmony search algorithmSchlünz, E.B. / Bokov, P.M. / Prinsloo, R.H. / van Vuuren, J.H. et al. | 2015
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In-phase instabilities in BWR with sub-cooled boiling, direct heating, and spacers effectsMuñoz-Cobo, José L. / Escrivá, Alberto / Domingo, María-Dolores et al. | 2015
- 687
-
Control parameter optimization for AP1000 reactor using Particle Swarm OptimizationWang, Pengfei / Wan, Jiashuang / Luo, Run / Zhao, Fuyu / Wei, Xinyu et al. | 2015
- 696
-
Implementation of condition-dependent probabilistic risk assessment using surveillance data on passive componentsLewandowski, Radoslaw / Denning, Richard / Aldemir, Tunc / Zhang, Jinsuo et al. | 2015
- 707
-
Numerical implementation, verification and validation of two-phase flow four-equation drift flux model with Jacobian-free Newton–Krylov methodZou, Ling / Zhao, Haihua / Zhang, Hongbin et al. | 2015
- 720
-
Measurement of sub-critical reactivity in a heavy water reactor by neutron noise methods using a time stamping data acquisition systemKumar, Rajeev / Degweker, S.B. / Singh, K.P. / Ali, M. Yakub et al. | 2015
- 728
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Use of discontinuity factors in high-order finite element methodsVidal-Ferràndiz, A. / González-Pintor, S. / Ginestar, D. / Verdú, G. / Asadzadeh, M. / Demazière, C. et al. | 2015
- 739
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An integrated approach to sensor FDI and signal reconstruction in HTGRs – Part II: Case studiesUren, Kenneth R. / van Schoor, George / du Rand, Carel P. / Botha, Anrika et al. | 2015
- 750
-
An integrated approach to sensor FDI and signal reconstruction in HTGRs – Part I: Theoretical frameworkUren, Kenneth R. / van Schoor, George / du Rand, Carel P. / Botha, Anrika et al. | 2015
- 761
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Static and transient analysis of a medium-sized sodium cooled fast reactor loaded with oxide, nitride, carbide and metallic fuelsZhang, Youpeng / Mikityuk, Konstantin et al. | 2015
- 772
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Features of MCNP6Goorley, T. / James, M. / Booth, T. / Brown, F. / Bull, J. / Cox, L.J. / Durkee, J. / Elson, J. / Fensin, M. / Forster, R.A. et al. | 2015
- 784
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Thermal stability investigation technique for uranium nitrideBaranov, V.G. / Tenishev, A.V. / Kuzmin, R.S. / Pokrovskiy, S.A. / Mikhalchik, V.V. / Astafyev, V.A. / Taubin, M.L. / Solntseva, E.S. et al. | 2014
- 793
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Safety analysis of MTR type research reactor during postulated beam tube break inducing positive reactivityKhakim, Azizul et al. | 2014
- 799
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Thermal conductivity of perspective fuel based on uranium nitrideSolntceva, E.S. / Taubin, M.L. / Vybyvanets, V.I. / Galyov, I.E. / Baranov, V.G. / Homyakov, O.V. / Tenishev, A.V. et al. | 2014
- 803
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Computational fluid dynamics study on cross flow pressure drop for triangular array rod assemblies with wirePramuditya, Syeilendra / Takahashi, Minoru / Ninokata, Hisashi et al. | 2014
- IFC
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Editorial board| 2015
- iii
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Foreword| 2015