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                             46 results found
no title author magazine year volume issue page(s) type
1 Age-dating uranium metal using microstructural damage Loveless, Amanda M.
 2015
 83 C p. 298-301
4 p.
 article
2 Analysis of parallel channel instabilities in the CANDU supercritical water reactor Dutta, Goutam
 2015
 83 C p. 264-273
10 p.
 article
3 Analysis of 149 Sm time evolution and the reactivity contribution in nuclear reactors Moreira, O.
 2015
 83 C p. 87-93
7 p.
 article
4 Analysis of the accident in the Fukushima Daiichi nuclear power station Unit 3 with MELCOR_2.1 Fernandez-Moguel, L.
 2015
 83 C p. 193-215
23 p.
 article
5 An analytical investigation of direct vessel injection line break accidents of the ATLAS facility Kim, Yeon-Sik
 2015
 83 C p. 398-407
10 p.
 article
6 An evaluation on the cutting technologies for decommissioning of the tube bundles in the RPV of NPPs Jeong, KwanSeong
 2015
 83 C p. 342-345
4 p.
 article
7 Applications of high-resolution spatial discretization scheme and Jacobian-free Newton–Krylov method in two-phase flow problems Zou, Ling
 2015
 83 C p. 101-107
7 p.
 article
8 Burnup performance of OTTO cycle pebble bed reactors with ROX fuel Ho, Hai Quan
 2015
 83 C p. 1-7
7 p.
 article
9 CATHARE 2 simulations of steady state air/water tests performed in a 1:1 scale SFR sub-assembly mock-up Perez, J.
 2015
 83 C p. 283-297
15 p.
 article
10 Comparative study of the hydrogen generation during short term station blackout (STSBO) in a BWR Polo-Labarrios, M.A.
 2015
 83 C p. 274-282
9 p.
 article
11 Comparison of fast neutron spectra in graphite and FLINA salt inserted in well-defined core assembled in LR-0 reactor Košťál, Michal
 2015
 83 C p. 216-225
10 p.
 article
12 Coupling a CFD code with neutron kinetics and pin thermal models for nuclear reactor safety analyses Chen, Zhao
 2015
 83 C p. 41-49
9 p.
 article
13 Criticality Safety Evaluation of a Swiss wet storage pool using a global uncertainty analysis methodology Pecchia, Marco
 2015
 83 C p. 226-235
10 p.
 article
14 Development of high-immersive simulation system for designing maintenance strategy and its application to CLEAR-I Yang, Zihui
 2015
 83 C p. 309-315
7 p.
 article
15 Development of magnetic flux leakage technique for examination of steam generator tubes of prototype fast breeder reactor Singh, W. Sharatchandra
 2015
 83 C p. 57-64
8 p.
 article
16 Development of reliability and probabilistic safety assessment program RiskA Wu, Yican
 2015
 83 C p. 316-321
6 p.
 article
17 Dimensional measurements on 112GWd/t irradiated MOX fuel pins using X-ray radiography Saravanan, T.
 2015
 83 C p. 8-13
6 p.
 article
18 1/3D modeling of the core coolant circuit of a PHWR nuclear power plant Corzo, Santiago
 2015
 83 C p. 386-397
12 p.
 article
19 Editorial board 2015
 83 C p. IFC-
1 p.
 article
20 Effect of rolling motion on two-phase frictional pressure drop of boiling flows in a rectangular narrow channel Chen, Chong
 2015
 83 C p. 125-136
12 p.
 article
21 Estimate of the reactivity of the VENUS-F subcritical configuration using a Monte Carlo MSM method Lecouey, J.L.
 2015
 83 C p. 65-75
11 p.
 article
22 Experimental and numerical void fraction measurement for modeled two-phase flow inside a vertical pipe Adineh, Mahtab
 2015
 83 C p. 188-192
5 p.
 article
23 Experimental assessment of the kinetic parameters of the JSI TRIGA reactor Filliatre, P.
 2015
 83 C p. 236-245
10 p.
 article
24 Experimental investigation and CFD analysis on cross flow in the core of PMR200 Lee, Jeong-Hun
 2015
 83 C p. 422-435
14 p.
 article
25 Experimental study on heat pipe heat removal capacity for passive cooling of spent fuel pool Xiong, Zhenqin
 2015
 83 C p. 258-263
6 p.
 article
26 Few-group condensation via two-material coexisting ring model for fast reactor core analysis Won, Jong Hyuck
 2015
 83 C p. 172-180
9 p.
 article
27 Fuel cladding integrity analysis during beam trip transients for China lead-based demonstration reactor Xue, Sha
 2015
 83 C p. 94-100
7 p.
 article
28 Heat transfer to supercritical water in a 2×2 rod bundle Gu, H.Y.
 2015
 83 C p. 114-124
11 p.
 article
29 High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW Daeubler, Miriam
 2015
 83 C p. 352-375
24 p.
 article
30 Inventory calculation and nuclear data uncertainty propagation on light water reactor fuel using ALEPH-2 and SCALE 6.2 Fiorito, L.
 2015
 83 C p. 137-146
10 p.
 article
31 Investigation of the pulse energy noise dynamics of IBR-2M using cluster analysis Pepelyshev, Yu.N.
 2015
 83 C p. 50-56
7 p.
 article
32 Locally manufactured films for neutron flux measurement in the MNSR type reactor Nassan, L.
 2015
 83 C p. 108-113
6 p.
 article
33 Methods for reconstruction of the density distribution of nuclear power Pessoa, Paulo O.
 2015
 83 C p. 76-86
11 p.
 article
34 Minimizing MTR reactor uranium load with the use of MOX fuel by employing ORIGEN-S and MCNP4C codes Shaaban, Ismail
 2015
 83 C p. 34-40
7 p.
 article
35 Minimum dose method for walking-path planning of nuclear facilities Liu, Yong-kuo
 2015
 83 C p. 161-171
11 p.
 article
36 Modeling and simulation of bubbling hot well deaerator in condensers of ships Xue, Ruo-Jun
 2015
 83 C p. 346-351
6 p.
 article
37 Molecular dynamics analysis of incoherent neutron scattering from light water via the Van Hove space–time self-correlation function with a new quantum correction Abe, Y.
 2015
 83 C p. 302-308
7 p.
 article
38 Monte Carlo simulation for calculation of kinetic parameters in an Accelerator Driven Subcritical TRIGA reactor Hassanzadeh, M.
 2015
 83 C p. 322-327
6 p.
 article
39 Numerical and experimental investigation on the transient heat transfer characteristics of C-shape rod bundles used in Passive Residual Heat Removal Heat Exchangers Zhang, Yuhao
 2015
 83 C p. 147-160
14 p.
 article
40 ROP margin improvement options for CANDU reactors Kastanya, D.
 2015
 83 C p. 181-187
7 p.
 article
41 SCALE and SERPENT solutions of the OECD VVER-1000 LEU and MOX burnup computational benchmark Mercatali, L.
 2015
 83 C p. 328-341
14 p.
 article
42 Shortening transmutation time by using the molten salt reactor Biss, Klaus Hendrik
 2015
 83 C p. 25-33
9 p.
 article
43 Simulation of unprotected LOFA in MTR reactors using a mix CFD and one-d computation tool Khater, Hany
 2015
 83 C p. 376-385
10 p.
 article
44 Survey of prediction capabilities of three nuclear data libraries for a PWR application Vanhanen, R.
 2015
 83 C p. 408-421
14 p.
 article
45 Sustainability of the Chinese nuclear expansion: Natural uranium resources availability, Pu cycle, fuel utilization efficiency and spent fuel management Fiori, F.
 2015
 83 C p. 246-257
12 p.
 article
46 Theoretical approach to study the light particles induced production routes of 22Na Eslami, M.
 2015
 83 C p. 14-24
11 p.
 article
                             46 results found
 
 Koninklijke Bibliotheek - National Library of the Netherlands