TRAC-PF1/NEM Solutions of the OECD/NRC/PSU MSLB Benchmark (English)
- New search for: Beam, T. M.
- New search for: Ivanov, K. N.
- New search for: Baratta, A. J.
- New search for: Beam, T. M.
- New search for: Ivanov, K. N.
- New search for: Baratta, A. J.
In:
The physics of nuclear science and technology
;
1636-1646
;
1998
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ISBN:
- Conference paper / Print
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Title:TRAC-PF1/NEM Solutions of the OECD/NRC/PSU MSLB Benchmark
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Contributors:
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Conference:International conference, The physics of nuclear science and technology ; 1998 ; Hauppauge, NY
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Published in:The physics of nuclear science and technology ; 1636-1646
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Publisher:
- New search for: ANS
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Publication date:1998-01-01
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Size:11 pages
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ISBN:
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Type of media:Conference paper
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Type of material:Print
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Language:English
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Keywords:
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Source:
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Table of contents conference proceedings
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.
- 3
-
Two-Group Spectral Corrections for MOX CalculationsPalmtag, S. / Smith, K. et al. | 1998
- 9
-
Challenges to Nodal Diffusion Methods for Cores with Mixed Oxide FuelChao, Y. A. / Shatilla, Y. A. / Ida, T. / Tahara, Y. et al. | 1998
- 15
-
Influence of Boundary Conditions in Multigroup Calculations of the MOX Fuel Cell by the Surface Pseudosources MethodSultanov, N. V. / Karabanova, V. G. et al. | 1998
- 25
-
Effect of Void Distribution Parameter and Axial Power Profile on BWR Bifurcation Characteristicsvan Bragt, D. D. B. / Rizwan-Uddin / van der Hagen, T. H. J. J. et al. | 1998
- 34
-
Fast Dynamics Reconstruction Based on SVD, Application to BWR Stability AnalysisGinestar, D. / Verdu, G. / Vidal, V. et al. | 1998
- 40
-
BWR Stability Analysis at PSIHennig, D. et al. | 1998
- 51
-
New Cross Section Libraries for CASMO-4 Based on JEF-2 & ENDF/B-6Knott, D. / Edenius, M. / Forssen, B.-H. / Gragg, C. / Ekberg, K. et al. | 1998
- 58
-
Reactor Benchmark Testing for JENDL-3.2, JEF-2.2 and ENDF/B-VI.2Takano, H. / Akie, H. / Kaneko, K. et al. | 1998
- 66
-
Evaluation of the ENDF/B-VI Based New Multigroup Library for the WH Core Analysis Code SystemHuria, H. C. / Mayhue, L. T. / Tahara, Y. / Matsumoto, H. et al. | 1998
- 75
-
Incorporation of Neural Networks into Simulated Anealing Algorithm for Fuel Assembly Loading Pattern Optimization in a PWRLee, J. H. / Sim, H. J. / Jang, C. S. / Kim, C. H. et al. | 1998
- 84
-
A Comparison Between a One Point Reactor Model and a Two-Dimensional Core Model on Equilibrium Cycle Analyses of Pressurized Water ReactorsYamamoto, A. / Kimoto, T. et al. | 1998
- 91
-
In-Core Fuel Management Optimization by Incorporation of a Generalized Perturbation Theoretical Approach in a Heuristic Search Procedurevan Geemert, R. / Hoogenboom, J. E. / Quist, A. J. et al. | 1998
- 103
-
WIMS8-Speed with AccuracyHalsall, M. J. et al. | 1998
- 109
-
HOMERE: A New Homogenization and Transport-Diffusion Equivalence Methodology for PWR Neutronic Core CalculationGarzenne, C. / Kerkar, N. / Marginier, A.-M. et al. | 1998
- 118
-
PARAGON: The New Westinghouse Transport CodeOuisloumen, M. / Tahara, Y. et al. | 1998
- 127
-
Reactor Physics Aspects of Plutonium Recycling in PWRsKloosterman, J. L. et al. | 1998
- 135
-
CASMO-Simulate on MOX FuelEdenius, M. / Knott, D. / Smith, K. et al. | 1998
- 145
-
Features of the Monte Carlo Code MONK8Armishaw, M. J. / Hutton, J. L. / Smith, N. R. / Sidell, J. et al. | 1998
- 152
-
Stratified Source-Sampling Techniques for Monte Carlo Eigenvalue AnalysisMohamed, A. / Gelbard, E. M. et al. | 1998
- 160
-
Full Monte Carlo Simulation of a Hybrid Reactor Instability by Parallel Implementation of GEANTBacha, F. / Jejcic, A. / Maillard, J. / Maurel, G. / Silva, J. et al. | 1998
- 168
-
Application of the Midway Monte Carlo Method to Nuclear Bore Hole LoggingHoogenboom, J. E. et al. | 1998
- 177
-
Prompt Neutron Decay Constants and Subcritical Measurements for Material Control and Accountability in SHEBASanchez, R. / Jaegers, P. et al. | 1998
- 182
-
Benchmark Experiments of Effective Delayed Neutron Fraction beta~e~f~f in JAERI-FCASakurai, T. / Okajima, S. / Sodeyama, H. / Osugi, T. / Song, H. / Kim, Y.-I. / Martini, M. / Chaussonnet, P. / Philibert, H. / Spriggs, G. D. et al. | 1998
- 190
-
Preliminary Pulsing Experiments to Measure Delayed Neutron Emission ParametersCharlton, W. S. / Parish, T. A. / Raman, S. et al. | 1998
- 201
-
A Reload BWR Core Design for an Ultra-Long Operating CycleMcMahon, M. V. / Driscoll, M. J. et al. | 1998
- 209
-
Preliminary Study on Sensitivity of DUPIC Fuel Cycle Cost to Fuel CompositionChoi, H. / Choi, J. / Ko, W. I. / Lee, J. S. et al. | 1998
- 215
-
Study of DUPIC Fuel Cycle in CANDU 6 Reactor by DRAGON/DONJONShen, W. / Rozon, D. et al. | 1998
- 223
-
Study of Chinese 300 MWE PWR In-Core Fuel Management StrategyCheng, P. / Shen, W. / Huang, J. / Shen, L. et al. | 1998
- 233
-
The Effective Temperature for Doppler Broadening of Neutron Resonances in UO~2Meister, A. / Santamarina, A. et al. | 1998
- 240
-
Maximisation of the Doppler Effect in Thermal ReactorsBende, E. E. et al. | 1998
- 248
-
Assessment of DUPIC Physics Calculation by MCNPRoh, G. / Choi, H. et al. | 1998
- 257
-
Neutronics Benchmark of a MOX Assembly with Near-Weapons-Grade PlutoniumDifilippo, F. C. / Fisher, S. E. et al. | 1998
- 264
-
Depletion Analysis of Weapons-Grade and Reactor-Grade MOX Fuel Pins in LWRs and the Advanced Test ReactorChang, G. S. / Ryskamp, J. M. et al. | 1998
- 271
-
Analysis of a Partial MOX Core Design with Tritium Targets for LWRAnistratov, D. Y. / Adams, M. L. et al. | 1998
- 281
-
A Coupled Monte Carlo-Diffusion Theory Model for Regular Lattice ConfigurationsRahnema, F. / Ilas, G. / Zino, J. et al. | 1998
- 286
-
FIMUL-A Multigroup Submodule of Physical Module of the MCU-REA CodeChachin, D. V. et al. | 1998
- 293
-
Further Investigations on the Comparison and the Combination of Monte Carlo k~e~f~f EstimatorsNouri, A. / Dupas, J. / Reuss, P. / Carraro, L. et al. | 1998
- 303
-
Seven Surrogate Precursors for Modeling Delayed Neutron Decay and Predicting ReactivityLoaiza, D. J. / Haskin, F. E. et al. | 1998
- 309
-
Six-Group Accumulation of ENDF/B-VI Delayed Neutron Precursor Yields and Half-Lives for Thermal ^2^3^5U FissionFredin, B. et al. | 1998
- 313
-
Sensitivity of Reactivity and of Corresponding Uncertainty in Reactivity Arising from Uncertainty in Absolute Yield of Delayed Neutrons to Yield Evaluations and Measurements for a Fast and a Thermal Reactor CoreDas, S. et al. | 1998
- 323
-
An Optimal U-TH Mix Reactor to Maximise Fission Nuclear PowerJagannathan, V. / Jain, R. P. / Krishnani, P. D. / Pal, U. / Karthikeyan, R. et al. | 1998
- 331
-
Equilibrium Th-U Fuel Cycle of LWRs with Elements of Protection Against Fissile Materials ProliferationKoulikov, G. / Chmelev, A. / Glebov, V. / Apse, V. et al. | 1998
- 336
-
Conceptual Design of High Converting Pressure-Tube Type LWR CoreKim, M.-H. / Lee, K.-H. / Lim, J.-Y. et al. | 1998
- 343
-
Development of a Simple-Cell Model for Performing History-Based RFSP Simulations with WIMS-AECLDonnelly, J. V. et al. | 1998
- 351
-
A Finite Element Method for Boiling Water ReactorsNichita, E. / Rahnema, F. et al. | 1998
- 356
-
Void Reactivity Calculations in a Typical CANDU Cell Using MCNP and HELIOSRahnema, F. / Mosher, S. / Pitts, M. / McKinley, S. / Akhtar, P. / Serghiuta, D. / Stamm ler, R. J. J. et al. | 1998
- 365
-
The Coupled ANC-K/VIPRE Three Dimensional Kinetic PWR Core Analysis SystemChao, Y. A. / Sung, Y. X. et al. | 1998
- 372
-
Deterministic Sensitivity Analysis of Water Material Properties in Coupled Neutronics-Thermal-Hydraulic CodesIonescu-Bujor, M. / Cacuci, D. G. et al. | 1998
- 380
-
Benefits of Coupled Calculations in Steam Line Break: The Improvement of Physical Description in the Decoupled Methodology for Safety StudiesSalvatores, S. et al. | 1998
- 393
-
First Validation of Neutronic Lattice Parameters of Overmoderated 100% MOX Fueled PWR Cores on the Basis of the Mistral ExperimentCathalau, S. / Fougeras, P. / Santamarina, A. et al. | 1998
- 400
-
Present MOX Benchmark Programmes in VENUS and a Proposal for a Weapon-Grade MOX Programmevan der Meer, K. / Maldague, T. / Marloye, D. / D hondt, P. / Basselier, J. et al. | 1998
- 407
-
The Cyclic Characteristics MethodRoy, R. et al. | 1998
- 415
-
Exponential Characteristic Methods for Discretizing the Two-Dimensional Transport Equation on an Unstructured Grid of Triangular CellsEl Khettabi, F. et al. | 1998
- 425
-
Revised Evaluations of Fission-Product Cross SectionsWright, R. Q. et al. | 1998
- 431
-
Variation of Neutron Induced Fission Product Chain Yields with Incident Neutron EnergyMills, R. W. / Zimmerman, C. H. / Weaver, D. R. / James, M. F. et al. | 1998
- 438
-
Introduction of Model Calculated Beta-Ray Spectrum to ENDF/B-VI Fission Products Decay Data FileKatakura, J. / England, T. R. et al. | 1998
- 447
-
PWR Cores with Excessive Water Gaps; Modelling AspectsKurcyusz, E. / Holmlund-Pedersen, C. / Bejmer, K.-H. / Almberger, J. / Lefvert, T. et al. | 1998
- 454
-
A Study of PWR Quadrant Power TiltsHua, Y. Z. et al. | 1998
- 462
-
The Effect of Channel Flow Reduction on Thermal Performance of DUPIC Fuel Bundle Strings in the CANDU ReactorPark, J.-W. / Choi, H. et al. | 1998
- 469
-
Coupled Neutronic and Thermal-Hydraulic Code Benchmark Activities at the International Nuclear Safety CenterPodlazov, L. N. / Shagaliev, R. M. / Dunn, F. E. / Kavun, O. Y. / Krayushkin, A. V. / Cahalan, J. E. / Popykin, A. I. / Taiwo, T. A. / Khalil, H. S. et al. | 1998
- 477
-
Use of 3D Core Kinetics Methods for the Analysis of Reactivity Insertion Accidents in PWRsRome, M. / Agnoux, D. / Stelletta, S. / Subra, M. / Pelet, J. / Daudin, L. / Laurent, P. et al. | 1998
- 485
-
Analysis and Calculation of an Accident with Delayed Scram at NPP Greifswald Using the Coupled Code DYN3D/ATHLETKliem, S. et al. | 1998
- 495
-
Feasibility and Characteristics of Graphite-Filled MOX Fuel Design for Fully Loaded PWR CoresJo, C. K. / Cho, N. Z. / Kim, Y. H. et al. | 1998
- 501
-
Homogeneous or Heterogeneous Recycling of Americium in PWR/MOX Cores?Maldague, T. / Pilate, S. / Renard, A. / Harislur, A. / Mouney, H. / Rome, M. et al. | 1998
- 508
-
Enhancement of LWRs MOX-Fuel Cycle Proliferation Resistance by Plutonium DenaturingKoulikov, G. / Chmelev, A. / Glebov, V. / Apse, V. et al. | 1998
- 515
-
A Spectral Nodal Method for One-Speed X,Y-Geometry Discrete Ordinates Eigenvalue ProblemsFilho, H. A. / da Silva, F. C. / Barros, R. C. et al. | 1998
- 523
-
Fine Mesh 3-D Collision Probability Calculations Using the Lattice Code DRAGONMarleau, G. et al. | 1998
- 531
-
Coupling 2-D Cylindrical and 3-D X-Y-Z Transport ComputationsAbu-Shumays, I. K. / Yehnert, C. E. / Pitcairn, T. N. et al. | 1998
- 541
-
^1^6O Neutron Cross Section EvaluationCaro, E. et al. | 1998
- 549
-
R Matrix Analysis of the ^5^2CR Neutron Transmissions and Cross Sections Below 1.4 MeVBouland, O. et al. | 1998
- 557
-
Overview of Recent U235 Neutron Cross Section Evaluation WorkLubitz, C. et al. | 1998
- 567
-
Neutronics Studies for the Nuclear Power Plant Leibstadt Using Advanced MethodsHager, H. G. / Hollard, J.-M. / Krouthen, J. et al. | 1998
- 573
-
Application of the Advanced Methods of HELIOS & PRESTO-2 to BWRsFerri, A. A. / Patino, N. E. / Gheorghiu, H. N. / Sauar, T. O. / Tveiten, B. H. et al. | 1998
- 579
-
One-Dimensional Analysis of CANDU Primary Shield for DUPIC FuelRoh, G. / Choi, H. et al. | 1998
- 589
-
Numerical Modelling of Criticality in Fissile Liquids with Radiolytic Gas ProductionPain, C. C. / De Oliveira, C. R. E. / Goddard, A. J. H. / Carlsson-Sanders, C. et al. | 1998
- 597
-
Coupling Thermal Hydraulics with Neutronics for Pebble-Bed High Temperature Reactor CalculationsVerkerk, E. C. et al. | 1998
- 604
-
Simulation of Neutron Physical and Thermal Hydraulic Processes in Nuclear ReactorsVoronkov, A. / Zemskov, E. / Ionkin, A. / Strakhovskaya, L. / Sychugova, E. / Fedorenko, R. / Churbanov, A. et al. | 1998
- 612
-
Modeling of Design Basis Events in Passive ReactorsLevin, A. E. / Lois, L. et al. | 1998
- 619
-
An Overview of International Activities on the Use of Burnup Credit in Spent Fuel ManagementConde, J. M. / Crijns, M. J. / Dyck, H. P. / Lake, W. H. / Neuber, J. C. et al. | 1998
- 624
-
International Studies on Burnup Credit Criticality Safety by an OECD/NEA Working GroupBrady, M. C. / Okuno, H. / DeHart, M. D. / Nouri, A. / Sartori, E. et al. | 1998
- 631
-
Burnup Credit Applications to PWR and BWR Fuel Assembly Wet Storage SystemsNeuber, J.-C. et al. | 1998
- 641
-
Calculating gamma-Ray Induced DPA for Magnox Reactor Pressure VesselsMossop, J. R. / Edens, D. J. / Lewis, T. A. / Page, C. / Thornton, D. A. et al. | 1998
- 648
-
Operation for Critical Approach in ABWR Automated Control Rod Operation SystemFushimi, A. / Yokomura, T. / Ishii, Y. / Maruyama, H. / Miyamoto, Y. / Fukasawa, Y. / Tanikawa, N. / Ishii, K. et al. | 1998
- 656
-
Characterization of Irradiated LWR Fuel Assemblies with Long Cooling Time by Means of Gamma-Ray MeasurementsBacklin, A. / Hakansson, A. / Jansson, P. / Jacobsson, S. et al. | 1998
- 663
-
Spontaneous Fission Half-Lives and Their SystematicsHolden, N. E. et al. | 1998
- 671
-
Subbarrier Effects on the Evaluation of the Neutron Induced Fission Cross Sections of the Actinide NucleiVladuca, G. / Sin, M. et al. | 1998
- 678
-
Analysis of Nucleon-Induced Fission Cross Sections of Lead and Bismuth at Energies from 45 to 500 MeVProkofiev, A. V. / Mashnik, S. G. / Sierk, A. J. et al. | 1998
- 691
-
A Comparison of Three Techniques for Computing Probability TablesHebert, A. et al. | 1998
- 698
-
Parallel Algorithms for the Simultaneous Solution of Direct and Adjoint Multigroup ProblemsVarin, E. / Roy, R. et al. | 1998
- 704
-
Applicability of Design Window Search Procedure Using Neural Network to NeutronicsKugo, T. / Nakagawa, M. et al. | 1998
- 715
-
Radiation Dosimetry at the BNL High Flux Beam ReactorHolden, N. E. / Hu, J.-P. / Reciniello, R. N. et al. | 1998
- 720
-
LWR PROTEUS-New Experiments at a Zero-Power Facility Using Power Reactor FuelWilliams, T. / Chawla, R. / Grimm, P. / Joneja, O. P. / Seiler, R. / Ziver, A. K. et al. | 1998
- 728
-
Validation of Power Distribution and Coolant Void Coefficient in the HANARO Research ReactorSeo, C. G. / Lee, B. C. / Lee, C. S. / Kim, H. R. / Jun, B. J. et al. | 1998
- 735
-
Status of Burnup Credit in the United StatesLancaster, D. B. / Kang, C. / Lake, W. H. et al. | 1998
- 742
-
Studies on Burnup Credit at JAERIOkuno, H. / Nomura, Y. / Suyama, K. et al. | 1998
- 749
-
Taking Burnup into Account in Current and Future Criticality Studies-French Working Group on "Burnup Credit"Boudin, X. / Letang, E. / Guillou, E. et al. | 1998
- 759
-
Integral and Differential Experiments to Assess Fast Reactor Characteristics When Using Degraded PlutoniumSmith, P. / Rimpault, G. / Bouland, O. / Soule, R. / Fort, E. / Ohki, S. et al. | 1998
- 767
-
Characterization of Neutron Ionization Chambers Using a Generalization of Campbell's TheoremPontes, E. W. / Ferreira, A. et al. | 1998
- 772
-
Application of Unified Complex Activation Detectors for Measurements of Reactor Neutron SpectraEfimov, B. V. / Demidov, A. M. / Ionov, V. S. / Dikarev, V. S. et al. | 1998
- 779
-
The Continuum Effect in Multistep Reaction Calculations at Medium EnergiesAvrigeanu, M. / Stetcu, I. / Avrigeanu, V. et al. | 1998
- 784
-
New Approach for the Determination of the Nuclear Level Density ParametersMughabghab, S. F. / Dunford, C. L. et al. | 1998
- 790
-
Table of Isotopes for the 1998/99 Handbook of Chemistry & PhysicsHolden, N. E. et al. | 1998
- 799
-
A Nodal Green's Function Method for Cylindrical GeometryHu, Y. / Zhao, X. / Du, Q. et al. | 1998
- 803
-
Definition of Subcriticality Using the Importance Function for the Production of Fission NeutronsKobayashi, K. / Nishihara, K. et al. | 1998
- 811
-
Use of a Combined Method for Calculation of Secondary Coolant Activation in IHX and Circular Pump Components Activation of LMFBRKorobeinikov, V. V. / Grabezhnoj, V. A. / Popov, E. P. / Bass, L. P. / Khmylev, A. N. et al. | 1998
- 821
-
The Transition From Short to Long-Emitters for Fixed Incore Monitoring SystemsCreasy, J. L. et al. | 1998
- 826
-
Experience with Fixed Incore Detectors at Seabrook StationGorski, J. P. / Cacciapouti, R. J. et al. | 1998
- 833
-
Core Damage Severity Evaluation for Pressurized Water Reactors by Artificial Intelligence MethodsMironidis, T. / Lidofsky, L. / Grochowski, G. / Tsoukalas, L. et al. | 1998
- 843
-
Development of Nuclear Physics Applications Within BNFLPrice, J. / O Hare, A. / Garrett, B. / Mountford, A. / Hulse, P. et al. | 1998
- 851
-
Complex Multi-Task Analysis of the Nuclear Reactor Systems with the DENT-97 Computer Code SystemTsvetkov, P. V. / Chmelev, A. N. / Geraskin, N. I. et al. | 1998
- 857
-
New Methods and Computer Codes Developments for Neutron Reactor Physics CalculationsKochurov, B. P. / Kwaratzheli, A. Y. / Knyazev, A. P. et al. | 1998
- 867
-
An Asymptotic Analysis for the Homogenization of P.W.R. Assemblies-The Transport CaseBal, G. / Warin, X. et al. | 1998
- 875
-
Assessment of Numerical Methods for Time-Dependent Transport Calculations of Subcritical SystemsRavetto, P. / Larosa, A. M. / Coppa, G. G. M. / Lapenta, G. / Carta, M. et al. | 1998
- 883
-
The Computation of Energy and Angular Distribution of Neutrons in Horizontal Reactor ChannelStankovsky, E. Y. / Kurachenko, Y. A. / Starizny, Y. S. / Chatalov, A. V. et al. | 1998
- 891
-
Implementation of the Probability Table Method in a Continuous-Energy Monte Carlo Code SystemSutton, T. M. / Brown, F. B. et al. | 1998
- 899
-
Reduction of U-238 Resonance Integral Further StudiesHuria, H. C. et al. | 1998
- 904
-
Cross-Section Adjustment RevisitedPerel, R. L. / Salmi, U. / Wagschal, J. J. / Yeivin, Y. et al. | 1998
- 912
-
A Method to Determine the Polarization of High Energy Gamma-RaysDepaola, G. O. / Kozameh, C. N. / Iglio, M. H. T. et al. | 1998
- 923
-
Evaluation of Flooded 2x2xN Arrays of Plutonium MetalPitts, M. / Rahnema, F. / Williamson, T. G. / Trumble, F. et al. | 1998
- 931
-
Analysis of the VENUS-3 Benchmark Experiment Using DORT and TORTMoon, B. J. / Kim, H. H. / Hwang, H. R. et al. | 1998
- 939
-
RB Reactor as the U-D~2O Benchmark Criticality SystemPesic, M. P. et al. | 1998
- 946
-
Critical Benchmark Experiments for the RBMK DesignBurlakov, E. V. / Jitarev, V. E. / Kachanov, V. M. / Kuzmin, A. N. et al. | 1998
- 957
-
Core Master™ 2 On-Line: A New Generation of Core Power Monitoring SystemsBollacasa, D. / Van de Berg, H. R. / Casal, J. / Jonsson, C. A. et al. | 1998
- 962
-
Reactor Dosimetry at the LVR-15 Research ReactorErben, O. / Marek, M. / Viererbl, L. et al. | 1998
- 973
-
A Variational Nodal Expansion Method for the Solution of Multigroup Neutron Diffusion EquationsTsuiki, M. / Yamamoto, M. et al. | 1998
- 980
-
Partial Current Based AFEN Formulation for Hexagonal-Z Neutronics Solver in MasterCho, B.-O. / Noh, J.-M. / Lee, C.-H. / Song, J.-S. / Park, S.-Y. / Zee, S.-Q. et al. | 1998
- 986
-
A New Nodal Method Based on Group Theory for the Multigroup Diffusion Calculation in Hexagonal GeometryZhang, S. / Xie, Z. et al. | 1998
- 994
-
Polynomial and Semi-Analytic Nodal Methods for Nonlinear Iteration ProcedureZimin, V. G. / Ninokata, H. / Pogosbekyan, L. R. et al. | 1998
- 1005
-
Gamma Radiation in a Dry Spent-Fuel StorageLazurik, V. T. / Moskvin, V. P. / Rogov, Y. V. / Rudychev, V. G. et al. | 1998
- 1012
-
Calculation of Radiation Fields at the Nuclear Power Plant During a Severe AccidentRudychev, V. G. / Adadurov, A. F. / Kalinichenko, A. I. / Lazurik, V. T. / Moskvin, V. P. / Pismeneskiy, S. A. / Rogov, Y. V. et al. | 1998
- 1018
-
Determination of Multigroup and Multi-Operator Reflector Constants Application to a Power Reactor Transport CalculationRichebois, E. / Fedon-Magnaud, C. / Magat, P. / Mathonniere, G. / Mengelle, S. / Nicolas, A. et al. | 1998
- 1029
-
Monte Carlo Testing of unresolved Resonance Treatment for Fast and Intermediate Critical AssembliesWeinman, J. P. et al. | 1998
- 1035
-
Resonance Parameters Adjustment Methodology Based on Integral Experiment AnalysisBlaise, P. / Fort, E. et al. | 1998
- 1043
-
Investigation of the Neutron Cross Section of ^9^9Tc in the Resonance RegionRaepsaet, C. / Bastian, C. / Brusegan, A. / Corvi, F. / Gonzalez, J. / Gunsing, F. / Lepretre, A. / Macavero, E. / Mounier, C. et al. | 1998
- 1053
-
Criticality Analysis in a Fuel Storage Pool Using the Monte Carlo MethodRodenas, J. / Lopez, M. C. / Verdu, G. et al. | 1998
- 1060
-
Comparison of the Criticality Experiment Calculation Results by the MCU-RFFI/A, MCNP, MONK and KENO CodesAlexeyev, N. I. / Bryzgalov, V. I. / Chachin, D. V. / Glushkov, A. E. / Gomin, A. E. / Gurevich, M. I. / Shkarovsky, D. A. et al. | 1998
- 1068
-
Validation of an Advanced Heterogeneous Model for LWR Detailed Pin-by-Pin CalculationsAvvakumov, A. / Malofeev, V. et al. | 1998
- 1079
-
Revision of ANS 19.3.4, "The Determination of Thermal Energy Deposition Rates in Nuclear Reactors"Boss, C. R. / Perry, R. T. et al. | 1998
- 1087
-
Development of a Standard for Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity in Water-Moderated Power ReactorsMosteller, R. D. / Apperson, C. E. / Gavin, P. H. / Hall, R. A. / Lancaster, D. B. / Robertson, S. T. / Young, E. H. et al. | 1998
- 1097
-
The Siemens 3-D Steady State BWR Core Simulator MICROBURN-B2Misu, S. / Moon, H. et al. | 1998
- 1106
-
Development of a Multigroup Nodal BWR Core Simulator, NEREUSIwamoto, T. / Yanamoto, M. et al. | 1998
- 1114
-
A Harmonic Analytic Nodal MethodJiang, G. / Downar, T. J. et al. | 1998
- 1122
-
A New Approach in Nodal MethodKeqiang, R. / Xiaogang, X. / Xuedong, F. et al. | 1998
- 1129
-
^2^5^2Cf-Source-Driven Noise Analysis Measurements with Annular High-Enriched Uranium Metal CastingsValentine, T. E. / Mattingly, J. K. / Mihalczo, J. T. et al. | 1998
- 1138
-
Multivariate High Order Statistical Signatures for Enhanced Analysis of Source-Driven Subcritical MeasurementsMattingly, J. K. / Valentine, T. E. / Mihalczo, J. T. / Perez, R. B. et al. | 1998
- 1146
-
Measuring Subcriticality by an Inverse Kinetics MethodBlazquez, J. et al. | 1998
- 1153
-
Nuclear Data Requirements for Fission Reactor Neutronics CalculationsFinck, P. J. / Gruppelaar, H. / Konieczny, M. / Nordborg, C. / Rowlands, J. et al. | 1998
- 1160
-
Neutron Resonance Data for ApplicationsJaneva, N. B. et al. | 1998
- 1168
-
Nuclear Data Online at the NNDCMcLane, V. et al. | 1998
- 1172
-
Acceleration of Coupled Neutron-Gamma Calculations by DecouplingFeher, S. / de Leege, P. F. A. / Hoogenboom, J. E. et al. | 1998
- 1181
-
On the Estimation of Moderator Temperature Coefficient of Reactivity of PWR's Via Reactor Noise AnalysisHousiadas, C. / Antonopoulos-Domis, M. et al. | 1998
- 1189
-
Measurements of Mass Flow of Water with Pulsed Neutron Activation and Neural Networks-The Flow Act MethodLinden, P. / Pazsit, I. et al. | 1998
- 1197
-
Dynamic Analysis of Source Driven Sub-Critical Nuclear SystemsBurns, T. D. / Rydin, R. A. et al. | 1998
- 1207
-
Development of a Generalized Perturbation Program for a CANDU ReactorKim, D. H. / Kim, J. K. / Choi, H. / Roh, G. / Yang, W. S. et al. | 1998
- 1213
-
Coarse Mesh Finite Difference Computation with Replacement of Reflectors by Core-Reflector Boundary ConditionsKim, C. H. / Lee, E. K. / Bae, S. M. et al. | 1998
- 1220
-
Local Fine-Mesh Solution Based Transverse-Integrated Nodal Method for Hexagonal GeometryJoo, H. G. / Lee, C.-H. / Cho, B.-O. / Lee, K. / Zee, S.-Q. et al. | 1998
- 1228
-
Uncertainties and Sensitivities in Reactor Fuel Rod ModelingMirza, S. / Harris, D. R. et al. | 1998
- 1235
-
Efficient Use of Bayes' Equations for Fitting Neutron-Induced Cross Section and Integral DataLarson, N. M. / Leal, L. C. / Derrien, H. et al. | 1998
- 1241
-
Recent Developments Pertinent to Processing of ENDF/B6 Type Resonance Cross Section DataHwang, R. N. et al. | 1998
- 1251
-
The Effect of Resonance Scattering on the Ideal Gas Scattering KernelRothenstein, W. / Dagan, R. et al. | 1998
- 1261
-
Analysis of ANS LWR Physics Benchmark ProblemsTaiwo, T. A. / Blomquist, R. N. / Palmiotti, G. / Deen, J. R. et al. | 1998
- 1268
-
PWR Lattice Benchmark SolutionsMohanakrishnan, P. / Lee, S. M. et al. | 1998
- 1274
-
HELIOS Calculations for UO^2 Lattice BenchmarksMosteller, R. D. et al. | 1998
- 1282
-
ENDF/B-V and ENDF/B-VI Results for UO~2 Lattice Benchmark Problems Using MCNPMosteller, R. D. et al. | 1998
- 1290
-
PSI Contributions to the ANS PWR Lattice Benchmark ProblemsStanculescu, A. / Hollard, J.-M. et al. | 1998
- 1298
-
Summary of Results for the Uranium Benchmark Problem of the ANS Ad Hoc Committee on Reactor Physics BenchmarksParish, T. A. / Diamond, D. J. / Mosteller, R. D. / Gehin, J. C. et al. | 1998
- 1306
-
ANS Benchmark L1: PWR Lattice Benchmark ProblemsVerbeke, J. M. / Vujic, J. et al. | 1998
- 1315
-
The Role of the Nuclear Level Density in Spallation Neutron StudiesMughabghab, S. F. / Zucker, M. S. et al. | 1998
- 1320
-
Spallation Neutron Studies at SATURNELeray, S. / Boudard, A. / Legrain, R. / Terrien, Y. / Wlazlo, W. / Borne, F. / Boue, F. / Crespin, S. / Drake, D. / Frehaut, J. et al. | 1998
- 1327
-
Simulation of Thick Target Experiments for the Validation of Spallation CodesLandeyro, P. A. / Guidotti, M. / Silvani, V. / Neuhold, P. et al. | 1998
- 1334
-
Spallation Residue Cross-Sections in Reverse KinematicsTassan-Got, L. / Mustapha, B. / Farget, F. / Bernas, M. / Stephan, C. / Armbruster, P. / Benlliure, J. / Enqvist, T. / Schmidt, K. H. / Boudard, A. et al. | 1998
- 1341
-
Spallation Neutron Source for Multi-Purpose IrradiationsDeffain, J. P. / Bergeron, J. / Lenain, R. / Poitevin, Y. et al. | 1998
- 1351
-
Validation of HELIOS/CM-PRESTO for Fuel Management Analyses of Laguna Verde Nuclear Power PlantFrancois, J. L. / Esquivel, J. L. / Cortes, C. / Esquivias, J. / del Campo, C. M. / Ramos, J. C. / Blanco, J. / Torres, C. et al. | 1998
- 1359
-
A Contribution for Benchmarking ENDF/B-VI Isothermal Reactivity Coefficient Determinationdos Santos, A. / Fuga, R. / Jerez, R. / Abe, A. et al. | 1998
- 1369
-
NWIS Signatures for Identification of Weapons Components at the Oak Ridge Y-12 PlantMihalczo, J. T. / Mattingly, J. K. / Wyatt, M. S. / Valentine, T. E. / Mullens, J. A. / Hughes, S. S. et al. | 1998
- 1377
-
Characterization of Active Neutron Signatures in the Time DomainGinestar, D. / Perez, R. B. / Valentine, T. E. / Mattingly, J. K. / Mihalczo, J. T. / Weems, L. et al. | 1998
- 1385
-
A Software Package for Nuclear Analysis Guidance by a Relational DatabaseSchubert, A. / Janssen, G. / Koch, L. / Peerani, P. / Bibilashvili, Y. K. / Chorokhov, N. A. / Dolgov, Y. N. et al. | 1998
- 1393
-
Physics of Enriched Uranyl Fluoride Deposit Characterizations Using Active Neutron and Gamma Interrogation Techniques with ^2^5^2CFWyatt, M. S. / Uckan, T. / Mihalczo, J. T. / Valentine, T. E. / Hannon, T. F. et al. | 1998
- 1401
-
Calculation of Resonance Self-Shielding for ^2^3^5U from 0 to 2250 eVLeal, L. C. / Larson, N. M. / Santos, G. R. / Derrien, H. et al. | 1998
- 1410
-
Analysis, Processing and Integral Testing of the ^2^3^5U Leal-Derrien-Larson's EvaluationMounier, C. et al. | 1998
- 1413
-
Benchmark Calculations for Uranium 235Dean, C. J. / Hanlon, D. / Perry, R. J. et al. | 1998
- 1420
-
The New Set of Resonance Parameters for ^2^3^5UKopach, Y. N. / Popov, A. B. / Furman, W. I. / Gonin, N. N. / Kozlovsky, L. K. / Tambovtsev, D. I. / Kliman, J. et al. | 1998
- 1429
-
Coupled Neutronics-Thermalhydraulics Code Systems RELAP5/PANBOX and RELAP5/HEXTIME for Integrated Safety AnalysisKnoll, A. / Boer, R. / Finnemann, H. / Van de Velde, A. et al. | 1998
- 1437
-
3-D Core Model in APROS Multifunctional Simulation EnvironmentPuska, E. K. et al. | 1998
- 1444
-
Calculation of BWR Transients with the 3D Dynamics Code TRAB-3DKaloinen, E. / Kyrki-Rajamaki, R. / Rary, H. et al. | 1998
- 1455
-
Monte Carlo Calculation of Relativistic Protons Interaction with Extended Targets and Transmutation of Iodine-129 and Neptunium-237Chigrinov, S. E. / Rakhno, I. L. / Kievitskaia, A. I. et al. | 1998
- 1462
-
Benchmark Problems on Transmutation Calculation by the OECD/NEA Task Force on Physics Aspects of Different Transmutation ConceptsTakano, H. / Rulko, R. P. / Broeders, C. / Wakabayashi, T. / Sasa, T. / Iwasaki, T. / Lutz, D. / Mukaiyama, T. / Nordborg, C. et al. | 1998
- 1470
-
Status of Pulsed Neutron Source Source Based on 100-MeV Electron Linac in KoreaKim, G. N. / Park, S. J. / Kang, H. S. / Choi, J. Y. / Baek, W. Y. / Cho, M. H. / Ko, I. S. / Namkung, W. / Chang, J. H. et al. | 1998
- 1479
-
Monte Carlo Calculations for Enhancement of the Neutron Field in the Thermal Column of RPI for BNCTGoncalves, I. F. / Ramalho, A. J. G. / Goncalves, I. C. / Salgado, J. F. et al. | 1998
- 1482
-
The "SWAN" Approach to Neutron Beam Optimization for BNCT and Other ApplicationsGreenspan, E. / Karni, Y. et al. | 1998
- 1491
-
Neutronic Design of the Novel Annular Low-Low Power Reactor (ALLPR) for Boron Neutron Capture TherapyPetrovic, B. / Levine, S. H. et al. | 1998
- 1499
-
Validation of Decay Heat Data from ENDF/B-VI, JEF-2.2, and JNDC FP Nuclear Data Libraries (second version)de Leege, P. F. A. / Hoogenboom, J. E. / Kloosterman, J. L. et al. | 1998
- 1506
-
Effect of Newest Fission Product Decay Data on the Calculated Heat Transient Arising After a Power TransientHegedus, C. J. / Kereszturi, A. / Vertes, P. et al. | 1998
- 1511
-
VVER-440 Specific Nuclear Library for the ORIGEN2 Computer CodeMaraczy, C. / Vertes, P. et al. | 1998
- 1521
-
Analysis of Rapid Boron Dilution Consequences for PWRs with the ARROTTA CodeCheng, H. W. / Johanson, E. / Sehgal, B. R. et al. | 1998
- 1529
-
ATWS Analyses with 3D Neutronics Considering Inherent Boron DilutionKyrki-Rajamaki, R. / Miettinen, J. / Antila, M. et al. | 1998
- 1537
-
Results of a 3D Reactor Dynamics Benchmark Problem on Boron Dilution in the CoreRajamaki, R. K. et al. | 1998
- 1547
-
Subcriticality Level Analysis in Accelerator Driven Systems by Harmonic Modulation of the External SourceCarta, M. / D Angelo, A. et al. | 1998
- 1555
-
Monte Carlo Calculation of Burn Up for an Accelerator-Driven ReactorTakahashi, H. / Yang, Y. / Cetnar, J. / Zhang, J. et al. | 1998
- 1563
-
Feasibility Study of Constant Composition TRU Feeding in an Accelerator-Driven Fluid-Fueled Thermal Reactor SystemKim, D. S. / Cho, N. Z. / Park, W. S. et al. | 1998
- 1571
-
Benchmarking of Square and Hexagonal Pitch Critical Assemblies Using WIMSPowney, D. / Franklin, B. et al. | 1998
- 1579
-
HELIOS: Benchmarking Against Hexagonal TIC ExperimentsSzabo, S. P. / Stamm ler, R. J. J. et al. | 1998
- 1587
-
Analysis of KUCA Critical Experiments Using MVP Code and JENDL-3.2Unesaki, H. / Shiroya, S. et al. | 1998
- 1595
-
Radiation Dosimetry at the BNL Medical Research ReactorHolden, N. E. / Reciniello, R. N. / Greenberg, D. D. / Hu, J.-P. et al. | 1998
- 1600
-
Designing an Epithermal Neutron Beam for Boron Neutron Capture Therapy for the Fusion Reactions ^2H (d, n)^3He and ^3H (d, n)^4HeVerbeke, J. M. / Costes, S. V. / Bleuel, D. / Vujic, J. / Leung, K. N. et al. | 1998
- 1608
-
Evaluation of Normal Concentrations of Trace Elements in Human Tissues by Neutron Activation AnalysisSaiki, M. / Rogero, S. O. / Arauz, L. J. / Aguiar, A. R. et al. | 1998
- 1613
-
The Use of ^9^9^mTc as Fluorescing Sources in X-Ray Fluorescence AnalysisBassari, A. / Gencay, S. et al. | 1998
- 1621
-
Two-Fluid Thermal Hydraulics Capabilities of RAMONA-5Grandi, G. / Hoyer, N. / Belblidia, L. et al. | 1998
- 1629
-
An Enhanced Method of Calculating Coupled Reactor Power and Thermal HydraulicsLynas, S. W. / de Oliveira, C. R. E. / Goddard, A. J. H. / Hewitt, G. F. / Jones, J. R. et al. | 1998
- 1636
-
TRAC-PF1/NEM Solutions of the OECD/NRC/PSU MSLB BenchmarkBeam, T. M. / Ivanov, K. N. / Baratta, A. J. et al. | 1998
- 1647
-
Comparison of Measured and Calculated Composition of Irradiated EBR-II Blanket AssembliesGrimm, K. N. / Stillman, J. A. / Hill, R. N. / McKnight, R. D. / Toppel, B. J. / Khalil, H. S. et al. | 1998
- 1653
-
The CIRANO Experimental Programme for the Characterisation of Highly Enriched Plutonium Oxide Fuel in Fast ReactorsRimpault, G. / Jacqmin, R. / Martini, M. / Soule, R. / Smith, P. / Ohki, S. et al. | 1998
- 1661
-
Incorporation of Measurement Data from Irradiated Fuel Samples into the MTG System at FCFMcKnight, R. D. et al. | 1998
- 1668
-
Studies of Sodium Plenum Fast Reactor Layout Using Fuel Subassembly Detailed PictureChebeskov, A. N. / Korobeinikov, V. V. / Ilyunin, V. G. / Korobeinikova, L. V. et al. | 1998
- 1679
-
Study on Breeding Characteristics of Fast Spectrum BWRYokoyama, T. / Yoshioka, R. / Sakashita, Y. et al. | 1998
- 1685
-
Spectral Shift Benefit on ABWR Core DesignsChiang, R.-T. / Sardjono, Y. / Fawcett, R. M. et al. | 1998
- 1689
-
Conceptual Design of a Light Water Cooled PHWRKim, M.-H. / Park, D.-H. et al. | 1998
- 1697
-
Nuclear Design of Fission Moly Target in HANAROKim, M.-H. / Cho, D.-K. / Sohn, D.-S. et al. | 1998
- 1703
-
Image Reconstruction in Emission Computed Tomography Via Multigrid Wavelet-Based Natural Pixel MethodPark, C. J. / Cho, N. Z. et al. | 1998
- 1711
-
Measurement and Analysis of NP237 Capture Reaction Rate in Various Thermal Neutron Fields at the Kyoto University Critical Assembly and Thermal ColumnIwasaki, T. / Horiuchi, T. / Fujiwara, D. / Hirakawa, N. / Hayashi, M. / Nakamura, H. / Shiroya, S. / Unesaki, H. / Shinohara, N. et al. | 1998
- 1719
-
The Thermal Neutron Capture Cross Section of ^2^4^2^g^sAm; A Critical Parameter for the Transmutation of ^2^4^1AmCribier, M. / Bolognese, T. / Fioni, G. / Gunsing, F. / Lelievre, F. / Marie, F. / Martino, J. / Pluguet, A. / Spiro, M. / Veyssiere, C. et al. | 1998
- 1726
-
Fission, Total and Neutron Capture Cross Section Measurements at ORELA for ^2^3^3U, ^2^7AL and Natural ChlorineGuber, K. H. / Spencer, R. R. / Leal, L. C. / Larson, D. C. / Dos Santos, G. / Harvey, J. A. / Hill, N. W. et al. | 1998
- 1730
-
Neutron Total and Capture Cross Section Measurements and Resonance Parameter Analysis of Tungsten from 0.01 to 200 eVBlock, R. C. / Slovacek, R. E. / Werner, C. J. / Burke, J. A. / Drindak, N. J. / Leinweber, G. et al. | 1998
- 1739
-
The Experimental Realization and Investigation of the Phenomenon of Controlling the Spontaneous Nuclear Gamma-Decay and the Life-Time of Gamma-Excited NucleiVysotskii, V. I. / Bugrov, V. P. / Kornilova, A. A. / Reiman, S. I. et al. | 1998
- 1744
-
On the Effectiveness of Nuclei Excitation by Nonthermal Laser Produced Subrelativistic Oscillating Electrons During Action of Short Powerful Polarized Optical Laser Pulse on Perfect CrystalVysotskii, V. I. et al. | 1998
- 1748
-
The Method and the Theory of Controlling the Spontaneous Nuclear Gamma-Decay and Life-Time of Radioactive and Excited NucleiVysotskii, V. I. et al. | 1998
- 1755
-
Application of the Coupled Code System ATHLET and QUABOX/CUBBOX to an ATWS Transient `Total Loss-of-Feedwater' in RBMKClemente, M. / Kusnetsov, P. / Langenbuch, S. / Schmidt, K.-D. / Stenbock, I. / Velkov, K. et al. | 1998
- 1761
-
Detailed Calculation of a Neutron Spectrum in a Cell of a Nuclear ReactorDavidenko, V. D. / Tsybulsky, V. P. et al. | 1998
- 1768
-
Verification and Validation of Core Analysis Code System SAPFIR_VVR95-RCElchine, A. V. / Ivanov, A. S. / Piskaryov, A. V. / Karpov, A. S. / Artemov, V. G. / Obuhov, V. V. / Shemaev, Y. P. et al. | 1998
- 1774
-
Study of alpha-Particle Injection Effect on Superconductors YBa~2Cu~3O~7~-~d~e~l~t~a TypeSantos, G. R. / Leal, L. C. et al. | 1998