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                             47 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Aerial work robot for a nuclear power plant with a pressurized heavy water reactor Shin, Hocheol
 2016
 92 C p. 284-288
5 p.
 artikel
2 Analysis of accumulators configuration in LB-LOCA for Bushehr NPP Shoushtari, M.M.
 2016
 92 C p. 96-106
11 p.
 artikel
3 Analysis of correlations and their impact on convergence rates in Monte Carlo eigenvalue simulations Miao, J.
 2016
 92 C p. 81-95
15 p.
 artikel
4 Analysis of flow distribution in plate-type core affected by uneven inlet temperature distribution Xia, G.L.
 2016
 92 C p. 333-344
12 p.
 artikel
5 Analysis of natural circulation operational characteristics for integrated pressurized water reactor Xia, G.L.
 2016
 92 C p. 304-311
8 p.
 artikel
6 Analysis of the fractional neutron point kinetics (FNPK) equation Espinosa-Paredes, Gilberto
 2016
 92 C p. 363-368
6 p.
 artikel
7 An experimental study of the coolability of debris beds with geometry variations Takasuo, Eveliina
 2016
 92 C p. 251-261
11 p.
 artikel
8 An experimental study on the thermal-hydraulic phenomena in the Hybrid Safety Injection Tank using a separate effect test facility Ryu, Sung Uk
 2016
 92 C p. 211-227
17 p.
 artikel
9 Applicability of adiabatic approximation on neutron noise analysis in molten salt reactor Wang, Jiangmeng
 2016
 92 C p. 295-303
9 p.
 artikel
10 Assessment of homogeneous and heterogeneous resonance integral tables and their applications to the embedded self-shielding method Liu, Yuxuan
 2016
 92 C p. 186-197
12 p.
 artikel
11 Assessment of TASS/SMR code for a loss of coolant flow transient using results of integral type test facility Chung, Young-Jong
 2016
 92 C p. 1-7
7 p.
 artikel
12 CAPP/GAMMA+ code system for coupled neutronics and thermo-fluid simulation of a prismatic VHTR core Tak, Nam-il
 2016
 92 C p. 228-242
15 p.
 artikel
13 CFD aided approach to design printed circuit heat exchangers for supercritical CO2 Brayton cycle application Kim, Seong Gu
 2016
 92 C p. 175-185
11 p.
 artikel
14 Cold neutron source conceptual designing for Tehran Research Reactor Khajvand, N.
 2016
 92 C p. 407-412
6 p.
 artikel
15 Delayed Neutron Detection with graphite moderator for clad failure detection in Sodium-Cooled Fast Reactors Rohée, E.
 2016
 92 C p. 440-446
7 p.
 artikel
16 Editorial board 2016
 92 C p. IFC-
1 p.
 artikel
17 Ensuring safety in design of safety critical computer based systems Singh, Lalit Kumar
 2016
 92 C p. 289-294
6 p.
 artikel
18 Equivalence treatment in homogenization via Monte Carlo method Li, Mancang
 2016
 92 C p. 72-80
9 p.
 artikel
19 Estimation of evaporation rate of cesium from hot sodium pool to inert cover gas of typical SFR Pradeep, Arjun
 2016
 92 C p. 431-439
9 p.
 artikel
20 Evaluation of thermal hydraulic safety of a nuclear fuel assembly in a mast assembly of nuclear power plant Kim, YoungSoo
 2016
 92 C p. 136-149
14 p.
 artikel
21 Finite difference applied to the reconstruction method of the nuclear power density distribution Pessoa, Paulo O.
 2016
 92 C p. 378-390
13 p.
 artikel
22 Fluid-to-fluid scaling of heat transfer phenomena with supercritical pressure fluids: Results from RANS analyses Pucciarelli, A.
 2016
 92 C p. 21-35
15 p.
 artikel
23 Full 3-D core calculations with refueling for the OPAL Research Reactor using Monte Carlo Code Serpent 2 Ferraro, Diego
 2016
 92 C p. 369-377
9 p.
 artikel
24 Generation of thermal scattering libraries for liquids beyond the Gaussian approximation using molecular dynamics and NJOY/LEAPR Márquez Damián, J.I.
 2016
 92 C p. 107-112
6 p.
 artikel
25 Hybrid microscopic depletion model in nodal code DYN3D Bilodid, Y.
 2016
 92 C p. 397-406
10 p.
 artikel
26 Incorporation of interface current method based on 2D CP approach in VISWAM code system for hexagonal geometry Khan, Suhail Ahmad
 2016
 92 C p. 161-174
14 p.
 artikel
27 Investigation on fluctuations in full-size Molten Salt Reactor with coupled neutronic/thermal-hydraulic model Wang, Jiangmeng
 2016
 92 C p. 262-276
15 p.
 artikel
28 Localized neutron flux assessment and verification studies using MCNPX PWR full core model Vasiliev, A.
 2016
 92 C p. 317-332
16 p.
 artikel
29 Measurement and calculation of U and Th reaction rates in uranium mock assemblies Liu, R.
 2016
 92 C p. 391-396
6 p.
 artikel
30 MHD design analysis of an annular linear induction electromagnetic pump for SFR thermal hydraulic experimental loop Kim, Hee Reyoung
 2016
 92 C p. 127-135
9 p.
 artikel
31 Modeling of critical experiments and its impact on integral covariance matrices and correlation coefficients Peters, Elisabeth
 2016
 92 C p. 355-362
8 p.
 artikel
32 Monte Carlo burnup in HTR system with various TRISO packing Kępisty, G.
 2016
 92 C p. 419-430
12 p.
 artikel
33 Neutronic analysis of a U–Mo–Al fuel and europium as burnable poison Muniz, Rafael Oliveira Rondon
 2016
 92 C p. 46-51
6 p.
 artikel
34 Neutronic and fuel cycle comparison of uranium and thorium as matrix for minor actinides bearing-blankets Kooyman, T.
 2016
 92 C p. 61-71
11 p.
 artikel
35 Non-equilibrium mass transfer absorption model for the design of boron isotopes chemical exchange column Bai, Peng
 2016
 92 C p. 16-20
5 p.
 artikel
36 Nonlinear analysis of containment structure based on modified tendon model Kwak, Hyo-Gyoung
 2016
 92 C p. 113-126
14 p.
 artikel
37 Nuclear data uncertainty for criticality-safety: Monte Carlo vs. linear perturbation Rochman, D.
 2016
 92 C p. 150-160
11 p.
 artikel
38 Post-test simulation of the HTR-10 reactivity insertion without scram Chen, Fubing
 2016
 92 C p. 36-45
10 p.
 artikel
39 Preliminary thermal-hydraulic sub-channel analysis of 61 wire-wrapped bundle cooled by lead bismuth eutectic Lyu, Kefeng
 2016
 92 C p. 243-250
8 p.
 artikel
40 Reaction rate tally and depletion calculation with on-the-fly temperature treatment Liu, Shichang
 2016
 92 C p. 277-283
7 p.
 artikel
41 Selection of important initiating events for Level 1 probabilistic safety assessment study at Puspati TRIGA Reactor Maskin, M.
 2016
 92 C p. 198-210
13 p.
 artikel
42 Sensitivity study of APR-1400 steam generator primary head stay cylinder and tube sheet thickness Abdallah, Khaled Atya Ahmed
 2016
 92 C p. 8-15
8 p.
 artikel
43 Stochastic semi-implicit substep method for coupled depletion Monte-Carlo codes Kotlyar, D.
 2016
 92 C p. 52-60
9 p.
 artikel
44 Study on the identification of main drivers affecting the performance of human operators during low power and shutdown operation Kim, Ar Ryum
 2016
 92 C p. 447-455
9 p.
 artikel
45 Study on working mechanism of AP1000 moisture separator by numerical modeling Zhang, Huang
 2016
 92 C p. 345-354
10 p.
 artikel
46 The energy dependent Pál–Bell equation and the influence of the neutron energy on the survival probability in a supercritical medium Saxby, J.E.M.
 2016
 92 C p. 413-418
6 p.
 artikel
47 Uncertainty analysis for the weighted least square fitted buildup factors in the point kernel module Park, Chang Je
 2016
 92 C p. 312-316
5 p.
 artikel
                             47 gevonden resultaten
 
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