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                             50 gevonden resultaten
nr titel auteur tijdschrift jaar jaarg. afl. pagina('s) type
1 Analysis of Buoyancy-Driven Flow in the Rocom Test Facility Feng, Qingqing
 2017
 127 C p. 44-53
10 p.
 artikel
2 An Method to Quantify Control Rod Worth Uncertainty Propagated from Nuclear Data Hao, Chen
 2017
 127 C p. 178-186
9 p.
 artikel
3 Applying method of electrophysical diagnostics testing of uranium nitride under irradiation Ryabikovskaya, E.
 2017
 127 C p. 3-10
8 p.
 artikel
4 A study on low-pressure subcooled flow boiling using RELAP5/MOD3.4 Xu, Caihong
 2017
 127 C p. 387-397
11 p.
 artikel
5 Bottom Reflooding Experiments in a Thin Rectangular Channel Xu, Wei
 2017
 127 C p. 335-342
8 p.
 artikel
6 Core Damage Quick Assessment for NPP in China Liu, Yuanyuan
 2017
 127 C p. 96-102
7 p.
 artikel
7 Criticality search of soluble boron iteration in MC code JMCT Rui, Li
 2017
 127 C p. 329-334
6 p.
 artikel
8 Dependence on Base Width and Doping Concentration of Current Degradation in Gate-controlled Lateral PNP Bipolar Transistors Exposed to Reactor Neutrons and Gamma Rays Wang, Chenhui
 2017
 127 C p. 110-119
10 p.
 artikel
9 Design Process for Dual-Purpose Nuclear Spent Fuel Casks Palacio, Alejandro
 2017
 127 C p. 398-406
9 p.
 artikel
10 Development and Preliminary Verification of Reactor Shielding Design Code cosSHIELD of COSINE Code Package Hu, Ye
 2017
 127 C p. 87-95
9 p.
 artikel
11 Development of Radiation Grafted Super Absorbent Polymers for Agricultural Applications Fernando, T.N.
 2017
 127 C p. 163-177
15 p.
 artikel
12 Development of Subchannel Code SUBSC for high-fidelity multi-physics coupling application Chen, Jun
 2017
 127 C p. 264-274
11 p.
 artikel
13 Dimension of the forced vessel water level based on subcooling margin of core outlet coolant in CPR1000 nuclear power plants Zhenying, Wang
 2017
 127 C p. 103-109
7 p.
 artikel
14 Diversified Reactor Level Measurement System in the Boiling Water Reactor of Olkiluoto Janne, Pitkänen
 2017
 127 C p. 139-147
9 p.
 artikel
15 Dynamic response of AP1000 water tank with internal ring baffles under earthquake loads Zhao, Chunfeng
 2017
 127 C p. 407-415
9 p.
 artikel
16 Dynamic response of the HTR-10 under the control rod withdrawal test without scram GOU, Feng
 2017
 127 C p. 247-254
8 p.
 artikel
17 Edge plasma study using a fast visible light camera in the COMPASS tokamak Jirman, Tomáš
 2017
 127 C p. 360-368
9 p.
 artikel
18 Editorial Capriotti, Luca
 2017
 127 C p. 1-2
2 p.
 artikel
19 Establishment of an Electronic Radioactive Source Register at the NNR Maree, Vanessa
 2017
 127 C p. 120-126
7 p.
 artikel
20 Experimental study on transient characteristic of passive containment cooling system Cheng, Cheng
 2017
 127 C p. 193-200
8 p.
 artikel
21 Finite volume method based neutronics solvers for steady and transient-state analysis of nuclear reactors Hu, Tianliang
 2017
 127 C p. 275-283
9 p.
 artikel
22 Fluid-Structure Interaction Analysis Using Finite Element Methods for IRWST of Reactor Building Xiaoying, Sun
 2017
 127 C p. 225-233
9 p.
 artikel
23 From the risk integral to seismic PSA models. Practice and limitation of seismic risk assessment Raganelli, Lavinia
 2017
 127 C p. 154-162
9 p.
 artikel
24 Gamma irradiation technology to preservation of foodstuffs as an effort to maintain quality and acquaint the significant role of nuclear on food production to Indonesia society: A Review Handayani, Muhammad
 2017
 127 C p. 302-309
8 p.
 artikel
25 Generic PWR Simulation Suite for Nuclear Training Improvement after Fukushima Liu, Tao
 2017
 127 C p. 148-153
6 p.
 artikel
26 Grain Boundary Segregation of Substitutional Solutes/Impurities and Grain Boundary Decohesion in BCC Fe He, Xinfu
 2017
 127 C p. 377-386
10 p.
 artikel
27 High-temperature tests of silicon carbide composite cladding under GFR conditions Angelici Avincola, Valentina
 2017
 127 C p. 320-328
9 p.
 artikel
28 Japan Nuclear Human Resource Development Network Fujiwara, Kentaro
 2017
 127 C p. 35-43
9 p.
 artikel
29 Large Scale Simulation of Nuclear Waste Materials Ji, Yaqi
 2017
 127 C p. 416-424
9 p.
 artikel
30 Natural Language Process: A New Kind of Nuclear Quality Assurance Management Tool Guan, Yongqing
 2017
 127 C p. 201-219
19 p.
 artikel
31 Neutronics/Thermal-hydraulics Coupling Analysis for the Liquid-Fuel MOSART Concept Zhang, Dalin
 2017
 127 C p. 343-351
9 p.
 artikel
32 Numerical Investigation on Thermal Hydraulic and Transit time Characteristics of Density Wave Oscillations Wang, Sipeng
 2017
 127 C p. 291-301
11 p.
 artikel
33 Prediction of chemical effects of Mo and B on the Cs chemisorption onto stainless steel Di Lemma, Fidelma Giulia
 2017
 127 C p. 29-34
6 p.
 artikel
34 Prediction of components degradation using support vector regression with optimized parameters Yang, Chunzhen
 2017
 127 C p. 284-290
7 p.
 artikel
35 Qualification of Electric Penetration Assemblies for CAP Series Nuclear Power Plant Kaiyun, Zheng
 2017
 127 C p. 68-75
8 p.
 artikel
36 Rapid Nuclear Forensics Analysis via Laser Based Microphotonic Techniques Coupled with Chemometrics Bhatt, Bobby
 2017
 127 C p. 76-86
11 p.
 artikel
37 Research and application of piping inside grinding robots in nuclear power plant Yu, Pei
 2017
 127 C p. 54-59
6 p.
 artikel
38 Researches and investigation on manufacturers’ reliability test data of electronic parts Ruidong, Dai
 2017
 127 C p. 242-246
5 p.
 artikel
39 Research of the disturbances to reactor vessel water level measurement due to physical phenomena in CPR1000 nuclear power plants Zhenying, Wang
 2017
 127 C p. 60-67
8 p.
 artikel
40 Research on the control of containment pressure of Gen II+ NPP under severe accident condition Ningbo, Lei
 2017
 127 C p. 220-224
5 p.
 artikel
41 Risk Analysis and Control Strategies for the Assembly of Major Structure Module in AP1000 Nuclear Power Project Hu, Tiezhu
 2017
 127 C p. 187-192
6 p.
 artikel
42 Safety analyses of reactor VVER 1000 Vojackova, Jitka
 2017
 127 C p. 352-359
8 p.
 artikel
43 Sensitivity and uncertainty analysis for eigenvalue and few-group constants of reactor-physics calculations Wan, Chenghui
 2017
 127 C p. 11-19
9 p.
 artikel
44 Sources of uncertainty in the seismic design of submerged free-standing racks González Merino, Alberto
 2017
 127 C p. 310-319
10 p.
 artikel
45 Swimming pool-type low-temperature heating reactor: recent progress in research and application Zhang, Yi-Xuan
 2017
 127 C p. 425-431
7 p.
 artikel
46 Systematic and quantitative uncertainty analysis for rod ejection accident of pressurized water reactor Pan, Xinyi
 2017
 127 C p. 369-376
8 p.
 artikel
47 Three-dimensional simulation of a LBLOCA in an AP1000® containment building Fernández-Cosials, Kevin
 2017
 127 C p. 234-241
8 p.
 artikel
48 Tornado Hazard Assessment for a Nuclear Power Plant in China Zhu, Hao
 2017
 127 C p. 20-28
9 p.
 artikel
49 Validation and Application of MCNP and TORT Source Generation Codes Zheng, Zheng
 2017
 127 C p. 255-263
9 p.
 artikel
50 What do the CEOs expect from us? (If they expect something) Fernández-Cosials, Kevin
 2017
 127 C p. 127-138
12 p.
 artikel
                             50 gevonden resultaten
 
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