BRAHMMA: A compact experimental accelerator driven subcritical facility using D-T/D-D neutron source (English)
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In:
Annals of Nuclear Energy
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75
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590-594
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2014
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ISSN:
- Article (Journal) / Electronic Resource
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Title:BRAHMMA: A compact experimental accelerator driven subcritical facility using D-T/D-D neutron source
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Contributors:Sinha, Amar ( author ) / Roy, Tushar ( author ) / Kashyap, Yogesh ( author ) / Ray, Nirmal ( author ) / Shukla, Mayank ( author ) / Patel, Tarun ( author ) / Bajpai, Shefali ( author ) / Sarkar, P.S. ( author ) / Bishnoi, S. ( author ) / Adhikari, P.S. ( author )
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Published in:Annals of Nuclear Energy ; 75 ; 590-594
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Publisher:
- New search for: Elsevier Ltd
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Publication date:2014-09-03
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Size:5 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 75
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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CFD analysis of flow and heat transfer in Canadian supercritical water reactor bundlePodila, K. / Rao, Y.F. et al. | 2014
- 11
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Preliminary studies of compact Brayton cycle performance for Small Modular High Temperature Gas-cooled Reactor systemBae, Seong Jun / Lee, Jekyoung / Ahn, Yoonhan / Lee, Jeong Ik et al. | 2014
- 20
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The effect of coolant quantity on local fuel–coolant interactions in a molten poolCheng, Songbai / Matsuba, Ken-ichi / Isozaki, Mikio / Kamiyama, Kenji / Suzuki, Tohru / Tobita, Yoshiharu et al. | 2014
- 26
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Uncertainty and correlation analysis of lead nuclear data on reactor parameters for the European Lead Cooled Training ReactorAlhassan, E. / Sjöstrand, H. / Helgesson, P. / Koning, A.J. / Österlund, M. / Pomp, S. / Rochman, D. et al. | 2014
- 38
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Study of power distribution in the CZP, HFP and normal operation states of VVER-1000 (Bushehr) nuclear reactor core by coupling nuclear codesRafiei Karahroudi, Mohsen / Mousavi Shirazi, Seyed Alireza et al. | 2014
- 44
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Transient thermal–hydraulic analysis of complete single channel blockage accident of generic 10MW research reactorSon, Hyung Min / Yang, Soo Hyung / Park, Cheol / Lee, Byung Chul et al. | 2014
- 54
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Analysis of anticipated transient without scram of a Super Fast Reactor with single flow pass coreSutanto / Oka, Yoshiaki et al. | 2014
- 64
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Pressurized water reactor in-core nuclear fuel management by tabu searchHill, Natasha J. / Parks, Geoffrey T. et al. | 2014
- 72
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Development of a phenomena identification ranking table for simulating a station blackout transient of a pressurized water reactor with a thermal-hydraulic integral effect test facilityKang, Kyoung-Ho / Bae, Byoung-Uhn / Kim, Jong-Rok / Park, Yu-Sun / Lee, Seung-Wook / Song, Chul-Hwa / Choi, Ki-Yong et al. | 2014
- 79
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Commercial thorium fuel manufacture and irradiation: Testing (Th,Pu) and (Th,U) in the “Seven-Thirty” programInsulander Björk, Klara / Drera, Saleem S. / Kelly, Julian F. / Vitanza, Carlo / Helsengreen, Christian / Tverberg, Terje / Sobieska, Matylda / Oberländer, Barbara C. / Tuomisto, Harri / Kekkonen, Laura et al. | 2014
- 87
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AP1000® SBLOCA simulations with TRACE codeMontero-Mayorga, J. / Queral, C. / Gonzalez-Cadelo, J. et al. | 2014
- 101
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Features of a subcritical nuclear reactorVega-Carrillo, Hector Rene / Esparza-Garcia, Isvi Ruben / Sanchez, Alvaro et al. | 2014
- 107
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The time dependence of the extinction probability with delayed neutronsWilliams, M.M.R. / Pázsit, I. et al. | 2014
- 116
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Analysis on isotopic plutonium barrier based on spent nuclear fuel of LWRPermana, Sidik / Novitrian / Ismail / Suzuki, Mitsutoshi / Saito, Masaki et al. | 2014
- 123
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3D simulations of the hydrodynamic deformation of melt droplets in a water poolThakre, Sachin / Ma, Weimin et al. | 2014
- 132
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Adsorption of uranium(VI) from sulphate solutions using Amberlite IRA-402 resin: Equilibrium, kinetics and thermodynamics studySolgy, Mostafa / Taghizadeh, Majid / Ghoddocynejad, Davood et al. | 2014
- 139
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The effect of changing enrichments on core performanceLevine, S. / Blyth, T. / Ivanov, K. et al. | 2014
- 146
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Measurement of multiple α-modes at the Delphi subcritical assembly by neutron noise techniquesSzieberth, Máté / Klujber, Gergely / Kloosterman, Jan Leen / de Haas, Dick et al. | 2014
- 158
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Simulation of boiling flow in evaporator of separate type heat pipe with low heat fluxKuang, Y.W. / Wang, Wen / Zhuan, Rui / Yi, C.C. et al. | 2014
- 168
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CUDA and MPI performances on the computation of Rossi-α distribution from pulsed neutron sourcesTalamo, Alberto et al. | 2014
- 176
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Investigation of the Self-Interrogation Neutron Resonance Densitometry applied to spent fuel using Monte Carlo simulationsRossa, Riccardo / Borella, Alessandro / van der Meer, Klaas et al. | 2014
- 184
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Linkage options between unit process to enhance proliferation resistance of pyroprocessingAhn, Seong-Kyu / Seo, Chung-Seok / Kwon, Eun-ha / Kim, Ho-Dong et al. | 2014
- 189
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Neutron kerma coefficients of compounds for shielding and dosimetrySingh, Vishwanath P. / Badiger, N.M. / Vega-Carrillo, Hector Rene et al. | 2014
- 193
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Methodology for the scoping assessment of radioactive releases during dismantling of RBMK-1500 reactor systems with low-level contaminationRagaišis, Valdas / Poškas, Povilas / Šimonis, Audrius et al. | 2014
- 199
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Evaluation of interfacial area transport equation in vertical bubbly two-phase flow in large diameter pipesTian, Daogui / Yan, Changqi / Sun, Licheng et al. | 2014
- 210
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Prototypic corium oxidation and hydrogen release during the Fuel–Coolant InteractionTyrpekl, Vaclav / Piluso, Pascal / Bakardjieva, Snejana / Nižňanský, Daniel / Rehspringer, Jean-Luc / Bezdička, Petr / Dugne, Olivier et al. | 2014
- 219
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Novel passive and active tungsten-based identifiers for maintaining the continuity of knowledge of spent nuclear fuel copper canistersChernikova, Dina / Axell, Kåre / Nordlund, Anders / Wirdelius, Håkan et al. | 2014
- 228
-
Critical mass calculations using MCNP: An academic exerciseKastanya, Doddy et al. | 2014
- 232
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Transient performance analysis of pressurized safety injection tank with a partitionBae, Youngmin / Kim, Young In / Kim, Keung Koo et al. | 2014
- 239
-
A unified generic theory on discontinuity factors in diffusion, SP3 and transport calculationsYu, Lulin / Chao, Yung-An et al. | 2014
- 249
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Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactorTusheva, P. / Altstadt, E. / Willschütz, H.-G. / Fridman, E. / Weiß, F.-P. et al. | 2014
- 261
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Neutronics calculations for denatured molten salt reactors: Assessing resource requirements and proliferation-risk attributesAhmad, Ali / McClamrock, Edward B. / Glaser, Alexander et al. | 2014
- 268
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Determination of total mass attenuation coefficients, effective atomic numbers and electron densities for different shielding materialsElmahroug, Y. / Tellili, B. / Souga, C. et al. | 2014
- 275
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Using high temperature gas-cooled reactors for greenhouse gas reduction and energy neutral production of phosphate fertilizersHaneklaus, Nils / Schnug, Ewald / Tulsidas, Harikrishnan / Tyobeka, Bismark et al. | 2014
- 283
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On the second moment of a stochastic radiation fieldAyyoubzadeh, Seyed Mohsen / Vosoughi, Naser / Ayyoubzadeh, Seyed Mohammad et al. | 2014
- 292
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Safety, security and safeguardZakariya, Nasiru Imam / Kahn, M.T.E. et al. | 2014
- 303
-
The Laputa code for lattice physics analysesShe, Ding / Liu, Zhihong / Zhao, Jing et al. | 2014
- 309
-
Neutron irradiation performance of Zircaloy-4 under research reactor operating conditionsJin, Hyun Ju / Kim, Tae Kyu et al. | 2014
- 316
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Neutronic parameters of a low enrichment core in reactor LR-0 for MSR researchKošt’ál, Michal / Milčák, Ján / Juříček, Vlastimil / Rypar, Vojtěch / Losa, Evžen / Cvachovec, František / Jánský, Bohumil / Novák, Evžen et al. | 2014
- 323
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A new methodology for estimation of initial entrainment fraction in annular flow for improved dryout predictionDasgupta, A. / Chandraker, D.K. / Vishnoi, A.K. / Vijayan, P.K. et al. | 2014
- 331
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Subchannel analysis of fuel temperature and departure of nucleate boiling of TRIGA Mark IJohns, Jesse / Reece, W.D. et al. | 2014
- 340
-
A new mathematical adjoint for the modified SAAF- equationsSchunert, Sebastian / Wang, Yaqi / Martineau, Richard / DeHart, Mark D. et al. | 2014
- 353
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Explicit appropriate basis function method for numerical solution of stiff systemsChen, Wenzhen / Xiao, Hongguang / Li, Haofeng / Chen, Ling et al. | 2014
- 358
-
Comparison of algorithms for Doppler broadening pointwise tabulated cross sectionsRomano, Paul K. / Trumbull, Timothy H. et al. | 2014
- 365
-
Quantification of in-containment fission products source term for 1000MWe PWR under loss of coolant accidentMehboob, Khurram / Park, Kwangheon / Khan, Rehan et al. | 2014
- 377
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Coupling of system thermal–hydraulics and Monte-Carlo code: Convergence criteria and quantification of correlation between statistical uncertainty and coupled errorWu, Xu / Kozlowski, Tomasz et al. | 2014
- 388
-
Experimental investigation on pressure oscillation frequency for submerged sonic/supersonic steam jetQiu, Binbin / Yan, Junjie / Liu, Jiping / Chong, Daotong et al. | 2014
- 395
-
Estimation of neutronics parameter sensitivity to nuclear data in random sampling-based uncertainty quantification calculationsChiba, Go / Kawamoto, Yosuke / Tsuji, Masashi / Narabayashi, Tadashi et al. | 2014
- 404
-
Verification of SAMG entry condition for APR1400Yun, Junghyun / Kim, Taewan / Kim, Jonghyun et al. | 2014
- 413
-
Development of semi-empirical model for tritium permeation under non-uniform temperature distribution at heat exchanger tube wallPark, Min Young / Kim, Byung Jun / Kim, Eung Soo et al. | 2014
- 421
-
Research of flow instability in OTSG under low load conditionsXia, Genglei / Peng, Minjun / Du, Xue et al. | 2014
- 428
-
Effect of geometric factors on performance of a sodium to air heat exchanger in a fast breeder reactorKannan, K. / Vinod, V. / Padmakumar, G. / Rudramoorthy, R. / Rajan, K.K. et al. | 2014
- 438
-
Seed and blanket thorium-reprocessed fuel ADS: Multi-cycle approach for higher thorium utilization and TRU transmutationVu, Thanh Mai / Kitada, Takanori et al. | 2014
- 443
-
Analysis of Phenix End-of-Life asymmetry test with multi-dimensional pool modeling of MARS-LMR codeJeong, H.-Y. / Ha, K.-S. / Choi, C.-W. / Park, M.-G. et al. | 2014
- 452
-
Modeling droplet-laden flows in moisture separators using k-d treesZhang, Huang / liu, Qianfeng / Qin, Benke / Bo, Hanliang et al. | 2014
- 462
-
Numerical simulation of temperature fluctuation reduction by a vortex breaker in an elbow pipe with thermal stratificationLu, T. / Han, W.W. / Zhai, H. et al. | 2014
- 468
-
Whole-core transport solution via deterministic SN transport/p-CMFD overlapping local/global calculation in hexagonal geometry problemYoo, Han Jong / Imron, Muhammad / Cho, Nam Zin et al. | 2014
- 476
-
Detailed evaluation of melt pool configuration in the lower plenum of the APR1400 reactor vessel during severe accidentsPark, Rae-Joon / Kang, Kyoung-Ho / Hong, Seong-Wan / Kim, Hwan-Yeol et al. | 2014
- 483
-
Experimental research on the thermal hydraulic characteristics of liquid sodium flowing in annuli with low Peclet numberQiu, Zicheng / Ma, Zaiyong / Wu, Yingwei / Qiu, Suizheng / Su, Guanghui et al. | 2014
- 492
-
Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systemsNikitin, E. / Fridman, E. / Mikityuk, K. et al. | 2014
- 498
-
Optimization method for the design of hexagonal fuel assembliesQvist, Staffan et al. | 2014
- 507
-
Experimental validation of RELAP5 predictions for subcooled leak flow through narrow circumferential slitsGhosh, Sandip / Saha, Samir Kumar et al. | 2014
- 516
-
Critical flow maps using an extended Henry–Fauske modelKim, Yeon-Sik et al. | 2014
- 521
-
Scaling analysis for the ocean motions in single phase natural circulationYan, B.H. / Wen, Q.L. et al. | 2014
- 527
-
Dry storage of spent nuclear fuel in UAE – Economic aspectAl Saadi, Sara / Yi, Yongsun et al. | 2014
- 536
-
Analysis of flow and heat transfer in a new latticeXiao, Hongguang / Yang, Lei / Yan, Binghuo et al. | 2014
- 542
-
Conceptual design of a passively safe thorium breeder Pebble Bed ReactorWols, F.J. / Kloosterman, J.L. / Lathouwers, D. / van der Hagen, T.H.J.J. et al. | 2014
- 559
-
Investigation of trans-critical CO2 horizontal mini-channel flow with multi-peak heat transfer behaviorsChen, Lin / Chen, Yi-Min / Sun, Meng-He / Zhang, Xin-Rong et al. | 2014
- 570
-
Experimental investigation of void distribution in suppression pool over the duration of a loss of coolant accident using steam–water two-phase mixtureRassame, Somboon / Griffiths, Matthew / Yang, Jun / Ju, Peng / Sharma, Subash / Hibiki, Takashi / Ishii, Mamoru et al. | 2014
- 581
-
CHF prediction model research for flat and hypervapotron heating surface in subcooled flow nucleate boilingLin, Meng / Li, Yankai / Zhong, Mingjun et al. | 2014
- 590
-
BRAHMMA: A compact experimental accelerator driven subcritical facility using D-T/D-D neutron sourceSinha, Amar / Roy, Tushar / Kashyap, Yogesh / Ray, Nirmal / Shukla, Mayank / Patel, Tarun / Bajpai, Shefali / Sarkar, P.S. / Bishnoi, S. / Adhikari, P.S. et al. | 2014
- 595
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Sensitivity and uncertainty analysis for UO 2 and MOX fueled PWR cellsFoad, Basma / Takeda, Toshikazu et al. | 2014
- 605
-
Modeling scheme of the Safety Injection Tank with Fluidic Device for best estimate calculation of LBLOCABang, Young Seok / Lee, Gong Hee / Woo, Sweng Woong et al. | 2014
- 611
-
Sliding mode control design for a PWR nuclear reactor using sliding mode observer during load following operationAnsarifar, G.R. / Akhavan, H.R. et al. | 2014
- 620
-
Neutron batch size optimisation methodology for Monte Carlo criticality calculationsTuttelberg, Kaur / Dufek, Jan et al. | 2014
- 627
-
Monte Carlo methods for reactor period calculationsZoia, Andrea / Brun, Emeric / Damian, Frédéric / Malvagi, Fausto et al. | 2014
- 635
-
Nuclear data sensitivity and uncertainty for the Canadian supercritical water-cooled reactor II: Full core analysisLangton, S.E. / Buijs, A. / Pencer, J. et al. | 2014
- 645
-
Application of Continuous and Structural ARMA modeling for noise analysis of a BWR coupled core and plant instability eventDemeshko, M. / Dokhane, A. / Washio, T. / Ferroukhi, H. / Kawahara, Y. / Aguirre, C. et al. | 2014
- 658
-
Operation characteristic of Integrated Pressurized Water Reactor under coordination control schemeDu, Xue / Xia, Genglei / He, Lihui et al. | 2014
- 665
-
Radiocarbon mass balance for a Magnox nuclear power stationMetcalfe, M.P. / Mills, R.W. et al. | 2014
- 672
-
Negative pressure difference evaluation of Lungmen ABWR containment by using GOTHICChen, Yen-Shu / Yuann, Yng-Ruey et al. | 2014
- 682
-
Multicriteria decision analysis based on analytic hierarchy process in GIS environment for siting nuclear power plant in EgyptAbudeif, A.M. / Abdel Moneim, A.A. / Farrag, A.F. et al. | 2014
- 693
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Evaluation of parameterization schemes in the Weather Research and Forecasting (WRF) model: A case study for the Kaiga nuclear power plant siteShrivastava, R. / Dash, S.K. / Oza, R.B. / Hegde, M.N. et al. | 2014
- 703
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Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactorsGeorge, Nathan Michael / Terrani, Kurt / Powers, Jeff / Worrall, Andrew / Maldonado, Ivan et al. | 2014
- 713
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NUSS: A tool for propagating multigroup nuclear data covariances in pointwise ACE-formatted nuclear data using stochastic sampling methodZhu, Ting / Vasiliev, Alexander / Ferroukhi, Hakim / Pautz, Andreas et al. | 2014
- 723
-
Nuclear waste transmutation performance assessment of an accelerator driven subcritical reactor for waste transmutation (ADS-NWT)Chen, Zhong / Wu, Yican / Yuan, Baoxin / Pan, Dongmei et al. | 2014
- 728
-
Higher order sliding mode controller design for a research nuclear reactor considering the effect of xenon concentration during load following operationAnsarifar, G.R. / Rafiei, M. et al. | 2014
- 736
-
Parameterized representation of macroscopic cross section for PWR reactorFiel, João Cláudio Batista / da Silva, Fernando Carvalho / Martinez, Aquilino Senra / Leal, Luiz C. et al. | 2014
- 742
-
Investigation of molten core–concrete interaction reactor benchmark test for VVER 1000Stefanova, A. / Gencheva, R. / Groudev, P. / Cranga, M. / Spengler, C. / Ivanov, I. / Foit, J. / Kostka, P. et al. | 2014
- 752
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Editors’ noteWilliams, M.M.R. / Pázsit, I. et al. | 2014
- IFC
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Editorial board| 2014
- iii
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Publisher Note| 2014