no |
title |
author |
magazine |
year |
volume |
issue |
page(s) |
type |
1 |
Absolute burnup measurement of LEU silicide fuel plate irradiated in the RSG GAS multipurpose reactor by destructive radiochemical technique
|
Ginting, Aslina Br. |
|
2015 |
85 |
C |
p. 613-620 8 p. |
article |
2 |
A characteristic correlation for heat transfer over serrated finned tubes
|
Anoop, B. |
|
2015 |
85 |
C |
p. 1052-1065 14 p. |
article |
3 |
A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT
|
Aufiero, Manuele |
|
2015 |
85 |
C |
p. 245-258 14 p. |
article |
4 |
A correction and a clarification to “Optimizing variance reduction in Monte Carlo eigenvalue calculations that employ the source iteration approach”
|
Burn, Kenneth W. |
|
2015 |
85 |
C |
p. 776-777 2 p. |
article |
5 |
Adjustment method of deterministic control rods worth computation based on measurements and auxiliary Monte Carlo runs
|
Wang, Guan-bo |
|
2015 |
85 |
C |
p. 183-192 10 p. |
article |
6 |
A domain-specific analysis system for examining nuclear reactor simulation data for light-water and sodium-cooled fast reactors
|
Billings, Jay Jay |
|
2015 |
85 |
C |
p. 856-868 13 p. |
article |
7 |
A MELCOR model of Fukushima Daiichi Unit 1 accident
|
Sevón, Tuomo |
|
2015 |
85 |
C |
p. 1-11 11 p. |
article |
8 |
A method for including external feed in depletion calculations with CRAM and implementation into ORIGEN
|
Isotalo, A.E. |
|
2015 |
85 |
C |
p. 68-77 10 p. |
article |
9 |
Analysis of a fatal accident in a highly enriched uranium facility
|
Difilippo, Felix C. |
|
2015 |
85 |
C |
p. 909-916 8 p. |
article |
10 |
Analysis of AP1000 containment passive cooling system during a loss-of-coolant accident
|
Hung, Zhen-Yu |
|
2015 |
85 |
C |
p. 717-724 8 p. |
article |
11 |
Analysis of Doppler coefficients for typical PWR UO2 and MTR U3Si2-Al fuels using ENDF/B-VI and VII
|
Kim, Kyung-O |
|
2015 |
85 |
C |
p. 1024-1028 5 p. |
article |
12 |
Analysis of minor actinides transmutation for a Molten Salt Fast Reactor
|
Yu, Chenggang |
|
2015 |
85 |
C |
p. 597-604 8 p. |
article |
13 |
Analysis of propagating temperature perturbations in the primary circuit of PWRs
|
Kiss, Sándor |
|
2015 |
85 |
C |
p. 1167-1174 8 p. |
article |
14 |
Analysis of Westinghouse MB2 test using the Steam-generator Thermohydraulics Analysis code STAF
|
Cong, Tenglong |
|
2015 |
85 |
C |
p. 127-136 10 p. |
article |
15 |
Analysis on the characteristics of geologic disposal waste arising from various partitioning and conditioning options
|
Liang, Fan |
|
2015 |
85 |
C |
p. 371-379 9 p. |
article |
16 |
A neutronic design study of lead-bismuth-cooled small and safe ultra-long-life cores
|
Hong, Ser Gi |
|
2015 |
85 |
C |
p. 58-67 10 p. |
article |
17 |
An evaluation of the design and performance for a new neutron absorber based on an artificial rare-earth compound
|
Kim, Song Hyun |
|
2015 |
85 |
C |
p. 461-466 6 p. |
article |
18 |
A new approach to nuclear reactor design optimization using genetic algorithms and regression analysis
|
Kumar, Akansha |
|
2015 |
85 |
C |
p. 27-35 9 p. |
article |
19 |
An improved assembly homogenization approach for plate-type research reactor
|
Ma, Jimin |
|
2015 |
85 |
C |
p. 1003-1013 11 p. |
article |
20 |
A nonoverlapping local/global iterative method with 2-D/1-D fusion transport kernel and p-CMFD wrapper for transient reactor analysis
|
Cho, Bumhee |
|
2015 |
85 |
C |
p. 937-957 21 p. |
article |
21 |
An optimized process for tritium-containing waste water collection of High-Temperature Gas-cooled Reactor
|
Chang, Hua |
|
2015 |
85 |
C |
p. 311-316 6 p. |
article |
22 |
A novel coordinated control for Integrated Pressurized Water Reactor
|
Zhao, Yuxin |
|
2015 |
85 |
C |
p. 1029-1034 6 p. |
article |
23 |
A Novel gamma emission tomography instrument for enhanced fuel characterization capabilities within the OECD Halden Reactor Project
|
Holcombe, Scott |
|
2015 |
85 |
C |
p. 837-845 9 p. |
article |
24 |
A numerical study on local fuel–coolant interactions in a simulated molten fuel pool using the SIMMER-III code
|
Cheng, Songbai |
|
2015 |
85 |
C |
p. 740-752 13 p. |
article |
25 |
AP1000® Large-Break LOCA BEPU analysis with TRACE code
|
Queral, C. |
|
2015 |
85 |
C |
p. 576-589 14 p. |
article |
26 |
Application of a new passive acoustic leak detection approach to recordings from the Dounreay prototype fast reactor
|
Marklund, Anders Riber |
|
2015 |
85 |
C |
p. 175-182 8 p. |
article |
27 |
Application of Data Reconciliation and Fault Detection and Isolation of Ion Chambers in Advanced Heavy Water Reactor
|
Yellapu, V.S. |
|
2015 |
85 |
C |
p. 1210-1225 16 p. |
article |
28 |
Application of MCNP for predicting power excursion during LOCA in Atucha-2 PHWR
|
Pecchia, Marco |
|
2015 |
85 |
C |
p. 271-278 8 p. |
article |
29 |
Application of the “best representativity” method to a PWR fuel calculation using the critical experiments at the Toshiba NCA facility
|
Umano, Takuya |
|
2015 |
85 |
C |
p. 78-92 15 p. |
article |
30 |
A two dimensional approach for temperature distribution in reactor lower head during severe accident
|
Cao, Zhen |
|
2015 |
85 |
C |
p. 467-480 14 p. |
article |
31 |
BELLA: a multi-point dynamics code for safety-informed design of fast reactors
|
Bortot, S. |
|
2015 |
85 |
C |
p. 228-235 8 p. |
article |
32 |
Boration modeling of the PWR biological shield using SCALE6.1 hybrid shielding methodology
|
Matijević, Mario |
|
2015 |
85 |
C |
p. 979-994 16 p. |
article |
33 |
Burnup-dependent core neutronics analysis of plate-type research reactor using deterministic and stochastic methods
|
Liu, Shichang |
|
2015 |
85 |
C |
p. 830-836 7 p. |
article |
34 |
Burnup instabilities in the full-core HTR model simulation
|
Kępisty, Grzegorz |
|
2015 |
85 |
C |
p. 652-661 10 p. |
article |
35 |
BWR Mark III containment analyses using a GOTHIC 8.0 3D model
|
Jimenez, Gonzalo |
|
2015 |
85 |
C |
p. 687-703 17 p. |
article |
36 |
BWR MARK I pressure suppression pool mixing and stratification analysis using GOTHIC lumped parameter modeling methodology
|
Ozdemir, Ozkan Emre |
|
2015 |
85 |
C |
p. 532-543 12 p. |
article |
37 |
Calculation of the spallation target neutronic parameters in Accelerator Driven Subcritical TRIGA reactor
|
Hassanzadeh, M. |
|
2015 |
85 |
C |
p. 326-330 5 p. |
article |
38 |
CFD analysis of hydrogen volumetric concentrations in a Hard Venting Containment System of a Mark II BWR
|
Gómez-Torres, Armando Miguel |
|
2015 |
85 |
C |
p. 552-565 14 p. |
article |
39 |
CFD simulation for thermal mixing of a SMART flow mixing header assembly
|
Kim, Young In |
|
2015 |
85 |
C |
p. 357-370 14 p. |
article |
40 |
Code development for eigenvalue total sensitivity analysis and total uncertainty analysis
|
Wan, Chenghui |
|
2015 |
85 |
C |
p. 788-797 10 p. |
article |
41 |
Comparative study of different concrete composition as gamma-ray shielding materials
|
Waly, El-Sayed A. |
|
2015 |
85 |
C |
p. 306-310 5 p. |
article |
42 |
Comparison of transient analysis of LBE-cooled fast reactor and ADS under loss of heat sink accident
|
Wang, Gang |
|
2015 |
85 |
C |
p. 494-500 7 p. |
article |
43 |
Computer analyses on loop seal clearing experiment at PWR PACTEL
|
Kauppinen, Otso-Pekka |
|
2015 |
85 |
C |
p. 47-57 11 p. |
article |
44 |
Computing adjoint-weighted kinetics parameters in Tripoli-4® by the Iterated Fission Probability method
|
Truchet, Guillaume |
|
2015 |
85 |
C |
p. 17-26 10 p. |
article |
45 |
Convex-based void filling method for CAD-based Monte Carlo geometry modeling
|
Yu, Shengpeng |
|
2015 |
85 |
C |
p. 380-385 6 p. |
article |
46 |
Design and performance of 2D and 3D-shuffled breed-and-burn cores
|
Qvist, Staffan |
|
2015 |
85 |
C |
p. 93-114 22 p. |
article |
47 |
Design and tuning of a Decentralized Fuzzy Logic Controller for a MIMO type Pressurized Heavy Water Reactor
|
Wallam, Fahad |
|
2015 |
85 |
C |
p. 1104-1114 11 p. |
article |
48 |
Detection of coolant void in lead-cooled fast reactors
|
Wolniewicz, Peter |
|
2015 |
85 |
C |
p. 1096-1103 8 p. |
article |
49 |
Development of a sensitivity and uncertainty analysis code for high temperature gas-cooled reactor physics based on the generalized perturbation theory
|
Han, Tae Young |
|
2015 |
85 |
C |
p. 501-511 11 p. |
article |
50 |
Development of a simulation platform for dynamic simulation and control studies of AP1000 nuclear steam supply system
|
Wan, Jiashuang |
|
2015 |
85 |
C |
p. 704-716 13 p. |
article |
51 |
Development of random geometry capability in RMC code for stochastic media analysis
|
Liu, Shichang |
|
2015 |
85 |
C |
p. 903-908 6 p. |
article |
52 |
Dynamic Monte Carlo calculation method by solving frequency domain transport equation using the complex-valued weight Monte Carlo method
|
Yamamoto, Toshihiro |
|
2015 |
85 |
C |
p. 426-433 8 p. |
article |
53 |
Editorial board
|
|
|
2015 |
85 |
C |
p. IFC- 1 p. |
article |
54 |
Effective atomic number of selected construction materials using gamma backscattering technique
|
Kiran, K.U. |
|
2015 |
85 |
C |
p. 1077-1084 8 p. |
article |
55 |
Effects of cross sections library parameters on the OECD/NEA Oskarshamn-2 benchmark solution
|
Balestra, P. |
|
2015 |
85 |
C |
p. 643-651 9 p. |
article |
56 |
Equivalent mechanical model for structural dynamic analysis of elevated tank like AP1000 PCCWST
|
Liu, Yu |
|
2015 |
85 |
C |
p. 1175-1183 9 p. |
article |
57 |
Estimating the response times of human operators working in the main control room of nuclear power plants based on the context of a seismic event – A case study
|
Park, Jinkyun |
|
2015 |
85 |
C |
p. 36-46 11 p. |
article |
58 |
Evaluation of RCS injection strategy by normal residual heat removal system in severe accident management
|
Zou, J. |
|
2015 |
85 |
C |
p. 166-174 9 p. |
article |
59 |
Evaluation of subcritical hybrid systems loaded with reprocessed fuel
|
Velasquez, Carlos E. |
|
2015 |
85 |
C |
p. 633-642 10 p. |
article |
60 |
Experimental and numerical investigations on roof slab of a pool type sodium cooled fast reactor based on model studies
|
Venugopal, Prabhu Raja |
|
2015 |
85 |
C |
p. 1085-1095 11 p. |
article |
61 |
Experimental investigation of heat removal performance of a concrete storage cask
|
Bang, Kyoung-Sik |
|
2015 |
85 |
C |
p. 679-686 8 p. |
article |
62 |
Fault detection and isolation for self powered neutron detectors based on Principal Component Analysis
|
Peng, Xingjie |
|
2015 |
85 |
C |
p. 213-219 7 p. |
article |
63 |
Feasibility assessment of the once-through thorium fuel cycle for the PTVM LWR concept
|
Rachamin, R. |
|
2015 |
85 |
C |
p. 1119-1130 12 p. |
article |
64 |
Fukushima Daiichi Unit 1 power plant containment analysis using GOTHIC
|
Ozdemir, Ozkan Emre |
|
2015 |
85 |
C |
p. 621-632 12 p. |
article |
65 |
Full Core modeling techniques for research reactors with irregular geometries using Serpent and PARCS applied to the CROCUS reactor
|
Siefman, Daniel J. |
|
2015 |
85 |
C |
p. 434-443 10 p. |
article |
66 |
Fuzzy probability based fault tree analysis to propagate and quantify epistemic uncertainty
|
Purba, Julwan Hendry |
|
2015 |
85 |
C |
p. 1189-1199 11 p. |
article |
67 |
Heterogeneous BN equations and symmetries
|
Tommasi, J. |
|
2015 |
85 |
C |
p. 145-158 14 p. |
article |
68 |
Hydraulic lift-off issues for application of high performance annular fuels in pressurized water reactors
|
Rahman, Mohammad Mizanur |
|
2015 |
85 |
C |
p. 1018-1023 6 p. |
article |
69 |
Identifying objective criterion to determine a complicated task – A comparative study
|
Park, Jinkyun |
|
2015 |
85 |
C |
p. 205-212 8 p. |
article |
70 |
Impact of the moderation ratio over the performance of different BWR fuel assemblies
|
Alonso, Gustavo |
|
2015 |
85 |
C |
p. 670-678 9 p. |
article |
71 |
Improved diffusion layer model based on real gas state equation for high pressure condensation
|
Wu, Lei |
|
2015 |
85 |
C |
p. 444-452 9 p. |
article |
72 |
Investigation of a long term passive cooling system using two-phase thermosyphon loops for the nuclear reactor spent fuel pool
|
Fu, Wen |
|
2015 |
85 |
C |
p. 346-356 11 p. |
article |
73 |
Investigation of different scenarios of thorium–uranium fuel distribution in the VVER-1200 first core
|
Dwiddar, Mohammed S. |
|
2015 |
85 |
C |
p. 605-612 8 p. |
article |
74 |
Kinematics analysis and verification of In-Vessel Fuel Handling System for China Lead-based Research Reactor
|
Zeng, Meihua |
|
2015 |
85 |
C |
p. 301-305 5 p. |
article |
75 |
Linear regression and sensitivity analysis in nuclear reactor design
|
Kumar, Akansha |
|
2015 |
85 |
C |
p. 798-811 14 p. |
article |
76 |
Measurement and simulation of the neutron flux distribution in the TRIGA Mark II reactor core
|
Chiesa, Davide |
|
2015 |
85 |
C |
p. 925-936 12 p. |
article |
77 |
Modeling and experimental studies on mixing and stratification during natural convection in containments
|
Zhang, He |
|
2015 |
85 |
C |
p. 317-325 9 p. |
article |
78 |
Modeling of the radiation doses during dismantling of RBMK-1500 reactor emergency core cooling system large diameter pipes
|
Simonis, Audrius |
|
2015 |
85 |
C |
p. 159-165 7 p. |
article |
79 |
Model of the IBR-2M pulsed reactor dynamics for investigating transition processes in a wide range of power variation
|
Pepyolyshev, Yu.N. |
|
2015 |
85 |
C |
p. 488-493 6 p. |
article |
80 |
Monte Carlo simulations of periodic pulsed reactor with moving geometry parts
|
Cao, Yan |
|
2015 |
85 |
C |
p. 236-244 9 p. |
article |
81 |
Monte Carlo solver for UWB1 nuclear fuel depletion code
|
Lovecký, M. |
|
2015 |
85 |
C |
p. 778-787 10 p. |
article |
82 |
More conservative governing equations in RELAP5: Derivation of equations
|
Fu, Zheng |
|
2015 |
85 |
C |
p. 523-531 9 p. |
article |
83 |
MOX fuel enrichment prediction in PWR using polynomial models
|
Mouginot, B. |
|
2015 |
85 |
C |
p. 812-819 8 p. |
article |
84 |
Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions
|
Wu, Xu |
|
2015 |
85 |
C |
p. 763-775 13 p. |
article |
85 |
Neutron spectrum kinetics in the infinite homogeneous reactor
|
Dall’Osso, Aldo |
|
2015 |
85 |
C |
p. 662-669 8 p. |
article |
86 |
Novel modular natural circulation BWR design and safety evaluation
|
Ishii, Mamoru |
|
2015 |
85 |
C |
p. 220-227 8 p. |
article |
87 |
Nuclear power plant instabilities analysis
|
Gavilan Moreno, Carlos J. |
|
2015 |
85 |
C |
p. 279-289 11 p. |
article |
88 |
Numerical investigation and modeling of two-phase flow sweeping in rod bundles with mixing vane grid spacers
|
Zimmermann, Markus |
|
2015 |
85 |
C |
p. 403-417 15 p. |
article |
89 |
Numerical simulation and theoretical analysis of heat transfer in a moving packed bed with the local internal heat source
|
Wang, Yongwei |
|
2015 |
85 |
C |
p. 418-425 8 p. |
article |
90 |
Numerical simulation of heat transfer and friction in non-uniform wall roughness lattice with different roughness element shapes
|
Xiao, Hongguang |
|
2015 |
85 |
C |
p. 732-739 8 p. |
article |
91 |
On the spatiotemporal correlations in a linear stochastic field generated by non-interacting particles: Theory
|
Ayyoubzadeh, Seyed Mohsen |
|
2015 |
85 |
C |
p. 1226-1238 13 p. |
article |
92 |
On the use of the SPH method in nodal diffusion analyses of SFR cores
|
Nikitin, E. |
|
2015 |
85 |
C |
p. 544-551 8 p. |
article |
93 |
On the way to enabling FRAPCON-3 to model spent fuel under dry storage conditions: The thermal evolution
|
Feria, F. |
|
2015 |
85 |
C |
p. 995-1002 8 p. |
article |
94 |
Optimization of U–Th fuel in heavy water moderated thermal breeder reactors using multivariate regression analysis and genetic algorithms
|
Kumar, Akansha |
|
2015 |
85 |
C |
p. 885-892 8 p. |
article |
95 |
Optimized CANDU-6 cell and reactivity device supercell models for advanced fuels reactor database generation
|
St-Aubin, Emmanuel |
|
2015 |
85 |
C |
p. 331-336 6 p. |
article |
96 |
Parametric evaluation of an SMR design domain
|
Al Rashdan, Ahmad |
|
2015 |
85 |
C |
p. 958-978 21 p. |
article |
97 |
Prediction of the strength of concrete radiation shielding based on LS-SVM
|
Juncai, Xu |
|
2015 |
85 |
C |
p. 296-300 5 p. |
article |
98 |
Prediction of time series of NPP operating parameters using dynamic model based on BP neural network
|
Liu, Yong-kuo |
|
2015 |
85 |
C |
p. 566-575 10 p. |
article |
99 |
Preliminary study on functional performance of compound type multistage safety injection tank
|
Bae, Youngmin |
|
2015 |
85 |
C |
p. 1045-1051 7 p. |
article |
100 |
Preliminary test results and CFD analysis for Moderator Circulation Test (MCT)
|
Kim, Hyoung Tae |
|
2015 |
85 |
C |
p. 386-393 8 p. |
article |
101 |
Preparation of U3O8 by calcination from ammonium uranyl carbonate in microwave fields: Process optimization
|
Liu, Bing-Guo |
|
2015 |
85 |
C |
p. 879-884 6 p. |
article |
102 |
Pressure drops of single/two-phase flows through porous beds with multi-sizes spheres and sands particles
|
Li, Liangxing |
|
2015 |
85 |
C |
p. 290-295 6 p. |
article |
103 |
Pressure oscillation and steam cavity during the condensation of a submerged steam jet
|
Zhao, Quanbin |
|
2015 |
85 |
C |
p. 512-522 11 p. |
article |
104 |
Proliferation issues related to fast SMRs
|
Frieß, Friederike |
|
2015 |
85 |
C |
p. 725-731 7 p. |
article |
105 |
Proof-of-principle of high-fidelity coupled CRUD deposition and cycle depletion simulation
|
Walter, Daniel J. |
|
2015 |
85 |
C |
p. 1152-1166 15 p. |
article |
106 |
Reactivity estimation during a reactivity-initiated accident using the extended Kalman filter
|
Busquim e Silva, R. |
|
2015 |
85 |
C |
p. 753-762 10 p. |
article |
107 |
Results of nuclear security culture survey on personnel at nuclear power plants
|
Yoo, Hosik |
|
2015 |
85 |
C |
p. 398-402 5 p. |
article |
108 |
Screening key parameters related to passive system performance based on Analytic Hierarchy Process
|
Ma, Guohang |
|
2015 |
85 |
C |
p. 1141-1151 11 p. |
article |
109 |
Semi-analytic benchmark for multi-group free-gas Legendre moments and the application of Gauss quadrature in generating thermal scattering Legendre moments
|
Zheng, Weixiong |
|
2015 |
85 |
C |
p. 1131-1140 10 p. |
article |
110 |
Simulation of the PHEBUS FPT-1 experiment using MELCOR and exploration of the primary core degradation mechanism
|
Wang, Jun |
|
2015 |
85 |
C |
p. 193-204 12 p. |
article |
111 |
Simultaneous multiple reactivity insertions in a typical MTR-type research reactor having U3Si2–Al fuel
|
Nasir, Rubina |
|
2015 |
85 |
C |
p. 869-878 10 p. |
article |
112 |
Space–time effects in the initiating phase of sodium fast reactors and their evaluation using a three-dimensional neutron kinetics model
|
Guyot, M. |
|
2015 |
85 |
C |
p. 115-126 12 p. |
article |
113 |
Spatially adaptive hp refinement approach for PN neutron transport equation using spectral element method
|
Nahavandi, N. |
|
2015 |
85 |
C |
p. 1066-1076 11 p. |
article |
114 |
Stability monitor for Boiling Water Reactors based on the Multivariate Empirical Mode Decomposition
|
Prieto-Guerrero, Alfonso |
|
2015 |
85 |
C |
p. 453-460 8 p. |
article |
115 |
Study the effects of different reflector types on the neutronic parameters of the 10MW MTR reactor using the MCNP4C code
|
Dawahra, S. |
|
2015 |
85 |
C |
p. 1115-1118 4 p. |
article |
116 |
Techno-economic assessment of thorium power in Canada
|
Graves, Brian |
|
2015 |
85 |
C |
p. 481-487 7 p. |
article |
117 |
The characteristics of break flows of SBLOCA tests in ATLAS facility
|
Kim, Yeon-Sik |
|
2015 |
85 |
C |
p. 1200-1209 10 p. |
article |
118 |
The investigation of Passive Accident Mitigation Scheme for advanced PWR NPP
|
Shi, Er-bing |
|
2015 |
85 |
C |
p. 590-596 7 p. |
article |
119 |
The new STRESA tool for preservation of thermalhydraulic experimental data produced in the European Commission
|
Pla, Patricia |
|
2015 |
85 |
C |
p. 893-902 10 p. |
article |
120 |
Theoretical calculation of the characteristics of annular flow in a rectangular narrow channel
|
Chen, Chong |
|
2015 |
85 |
C |
p. 259-270 12 p. |
article |
121 |
Thermal–mechanical analysis of the first wall for CFETR helium cooled solid breeder blanket
|
Liu, Qianwen |
|
2015 |
85 |
C |
p. 12-16 5 p. |
article |
122 |
Towards modeling and validation enhancements of the PSI MCNPX fast neutron fluence computational scheme based on recent PWR experimental data
|
Dupré, A. |
|
2015 |
85 |
C |
p. 820-829 10 p. |
article |
123 |
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