On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology (English)
- New search for: Alhassan, E.
- New search for: Sjöstrand, H.
- New search for: Helgesson, P.
- New search for: Österlund, M.
- New search for: Pomp, S.
- New search for: Koning, A.J.
- New search for: Rochman, D.
- New search for: Alhassan, E.
- New search for: Sjöstrand, H.
- New search for: Helgesson, P.
- New search for: Österlund, M.
- New search for: Pomp, S.
- New search for: Koning, A.J.
- New search for: Rochman, D.
In:
Progress in nuclear energy
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88
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43-52
;
2016
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ISSN:
- Article (Journal) / Print
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Title:On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology
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Contributors:Alhassan, E. ( author ) / Sjöstrand, H. ( author ) / Helgesson, P. ( author ) / Österlund, M. ( author ) / Pomp, S. ( author ) / Koning, A.J. ( author ) / Rochman, D. ( author )
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Published in:Progress in nuclear energy ; 88 ; 43-52
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Publisher:
- New search for: Elsevier Science B.V., Amsterdam.
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Publication date:2016-01-01
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Size:10 pages
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ISSN:
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Type of media:Article (Journal)
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Type of material:Print
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Language:English
- New search for: 333.7924
- Further information on Dewey Decimal Classification
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Classification:
DDC: 333.7924 -
Source:
© Metadata Copyright the British Library Board and other contributors. All rights reserved.
Table of contents – Volume 88
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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Corrosion mitigation in coolant systems in nuclear power plantsChajduk, Ewelina / Bojanowska-Czajka, Anna et al. | 2015
- 10
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Neutronic evaluation of coating and cladding materials for accident tolerant fuelsYounker, Ian / Fratoni, Massimiliano et al. | 2015
- 19
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Space independent xenon oscillations control in VVER reactor: A bifurcation analysis approachZarei, M. / Ghaderi, R. / Minuchehr, A. et al. | 2015
- 28
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Reactivity temperature coefficients for the HEU and LEU fuel of the MNSR reactorDawahra, S. / Khattab, K. / Saba, G. et al. | 2015
- 33
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On an improved box-scheme finite difference method based on the relative event probabilitiesVagheian, Mehran / Ochbelagh, Dariush Rezaei / Gharib, Morteza et al. | 2015
- 43
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On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodologyAlhassan, E. / Sjöstrand, H. / Helgesson, P. / Österlund, M. / Pomp, S. / Koning, A.J. / Rochman, D. et al. | 2015
- 53
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Application of vadose zone approach for prediction of radionuclide transfer from near-surface disposal facilityJakimavičiūtė-Maselienė, Vaidotė / Mažeika, Jonas / Motiejūnas, Stasys et al. | 2015
- 58
-
3D in-core fuel management optimization for breed-and-burn reactorsHou, Jason (Jia) / Qvist, Staffan / Kellogg, Roger / Greenspan, Ehud et al. | 2015
- 75
-
Modeling and simulation of radio-iodine released inside the containment as result of an accidentMehboob, Khurram / Aljohani, Mohammad S. et al. | 2015
- 88
-
Implementation of cyber security for safety systems of nuclear facilitiesPark, JaeKwan / Suh, YongSuk / Park, Cheol et al. | 2015
- 95
-
An evaluation of nuclide release from a trench-type LILW repositoryLee, Youn-Myoung / Choi, Heui-Joo et al. | 2015
- 104
-
PWR few-group constants parameterization analysisLi, Yunzhao / Gao, Shengnan / Wu, Hongchun / Cao, Liangzhi / Shen, Wei et al. | 2015
- 118
-
Monte Carlo and nodal neutron physics calculations of the IAEA MTR benchmark using Serpent/DYN3D code systemMargulis, Marat / Gilad, Erez et al. | 2015
- 134
-
Preliminary safety analysis on loss of flow accidents and external source transients for LBE cooled ADSR coreLu, Tianyu / Shan, Jianqiang / Gou, Junli / Zhang, Bin / Zhang, Bo / Ge, Li / Yuan, Yuan / Yang, Zijiang et al. | 2016
- 147
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Modeling analyses of radioactive aerosol flow and collection in mesoscopic impactor filtersNiu, Fenglei / Du, Xiaochao / Qi, Houbo / Yi, Mingqiang / Yang, Xu et al. | 2015
- 156
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Are shocks to nuclear energy consumption per capita permanent or temporary? A global perspectiveZhu, Huiming / Guo, Peng et al. | 2015
- 165
-
A causal model explaining Chinese university students' acceptance of nuclear powerWang, Yongxiang / Li, Jingping et al. | 2016
- 175
-
Composition, decomposition and analysis of reactor antineutrino and electron spectra based on gross theory of β-decay and summation methodYoshida, Tadashi / Tachibana, Takahiro / Hagura, Naoto / Chiba, Satoshi et al. | 2015
- 183
-
Benchmarking verification of the control rod effects on the MTR core parameters using the MTR-PC and MCNP codes throughout 3D core modeling and rod-drop experimentHedayat, Afshin et al. | 2015
- 191
-
Control rod drop hydrodynamic analysis for a pressurized water reactorRabiee, Ataollah / Atf, Alireza et al. | 2015
- 198
-
Implicitly solving phase appearance and disappearance problems using two-fluid six-equation modelZou, Ling / Zhao, Haihua / Zhang, Hongbin et al. | 2015
- 211
-
Pressure distribution in the containment of VVER-1000 during the first seconds of large break LOCARahgoshay, M. / Hashemi-Tilehnoee, M. et al. | 2016
- 218
-
Adaptive burnup stepsize selection using control theory for 2-D lattice depletion simulationsWalter, Daniel J. / Manera, Annalisa et al. | 2016
- 231
-
Safety analysis of LBLOCA in BDBA scenarios for the Bushehr's VVER-1000 nuclear power plantPirouzmand, Ahmad / Ghasemi, Armin / Faghihi, Farshad et al. | 2016
- 240
-
Drying kinetics of thorium oxalate: Experimental investigation and modelingBeigi, Sadegh / Sobati, Mohammad Amin / Charkhi, Amir et al. | 2016
- 245
-
Considerations for severe accident management under extended station blackout conditions in nuclear power plantsPark, Jong Woon / Seol, Wook-Cheol et al. | 2016
- 257
-
Implementation of the batch composition preserving genetic algorithm for burn up extension of a typical PWRIlyas, Muhammad / Rauff, Abdul / Zia, Muhammad Gulfam / Ahmad, Siraj-ul-Islam / Ahmad, Masroor et al. | 2015
- 264
-
Estimation of the fast neutron fluence in Laguna Verde RPV-Steel specimens simulating their irradiation in a TRIGA reactorGalicia-Aragón, Juan / François-Lacouture, Juan Luis / Aguilar-Hernández, Fortunato et al. | 2015
- 277
-
Lumped pseudo fission products during burnup step in MCNP5-ORIGEN coupling systemBenkharfia, Hocine / Zidi, Tahar / Belgaid, Mohamed et al. | 2016
- 277
-
Lumped pseudo fission products during burnup step inBenkharfia, Hocine et al. | 2016
- 285
-
Microstructural evolution of as-cast Th–U alloysDas, Santanu / Roy, S.B. / Chaudhari, G.P. / Daniel, B.S.S. et al. | 2016
- 297
-
An approach based on Support Vector Machines and a K-D Tree search algorithm for identification of the failure domain and safest operating conditions in nuclear systemsDi Maio, Francesco / Bandini, Alessandro / Zio, Enrico / Alfonsi, Andrea / Rabiti, Cristian et al. | 2016
- 310
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A sensitivity analysis of thermal lattices kinetic parameters with respect to the spectral weighting function using ultrafine BN methodFallah, Vahid Farhang / Salehi, Ali Akbar / Vosoughi, Naser / Ayyoubzadeh, Seyed Mohsen et al. | 2016
- 310
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A sensitivity analysis of thermal lattices kinetic parameters with respect to the spectral weighting function using ultrafine BFallah, Vahid Farhang et al. | 2016
- 321
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Calculation of radial burnup and nuclides atom density distributions in a VVER-1000 fuel rod using Monte Carlo methodPirouzmand, Ahmad / Roosta, Fatemeh et al. | 2016
- 332
-
Dancoff factor analysis for pebble bed fluoride salt cooled high temperature reactorQin, Wei / Yang, Kun / Chen, Jingen / Cai, Xiangzhou et al. | 2016
- 340
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Forced convection condensation in the presence of noncondensable gas in a horizontal tube; experimental and theoretical studyXu, Huiqiang / Sun, Zhongning / Gu, Haifeng / Li, Hao et al. | 2016
- 352
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Calculation of six-group importance weighted delayed neutron fractions and prompt neutron lifetime of MTR research reactors based on Monte Carlo methodArkani, Mohammad / Hassanzadeh, Mostafa / Khakshournia, Samad et al. | 2015
- 364
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Nuclear energy, renewable energy, CO2 emissions, and economic growth for nine developed countries: Evidence from panel Granger causality testsSaidi, Kais / Ben Mbarek, Mounir et al. | 2016
- 364
-
Nuclear energy, renewable energy, COSaidi, Kais et al. | 2016
- 375
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Analyses of ACME integral test results on CAP1400 small-break loss-of-coolant-accident transientLi, Yu Quan / Chang, Hua Jian / Ye, Zi Shen / Fang, Fang Fang / Shi, Yan / Yang, Kai / Cui, Ming Tao et al. | 2016
- 398
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Effect of compensation error in drift-flux parameters on predictions of thermal-hydraulic parameters in nuclear safety system analysis codesOzaki, Tetsuhiro / Tsukamoto, Naofumi / Nakamura, Ryosuke / Miyaji, Takamasa / Suzuki, Riichiro / Hibiki, Takashi et al. | 2015
- IFC
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Editorial Board| 2016