Digital Library
Close Browse articles from a journal
     Journal description
       All volumes of the corresponding journal
         All issues of the corresponding volume
                                       All articles of the corresponding issues
 
                             53 results found
no title author magazine year volume issue page(s) type
1 A fuel depletion analysis of the MSRE and three conceptual small molten-salt reactors for Mo-99 production Sheu, R.J.
2014
71 C p. 111-117
7 p.
article
2 Alternative off-site power supply improves nuclear power plant safety Gjorgiev, Blaže
2014
71 C p. 304-312
9 p.
article
3 An assessment of prompt neutron reproduction time in a reflector dominated fast critical system: ELECTRA Suvdantsetseg, E.
2014
71 C p. 159-165
7 p.
article
4 An evaluation on the cutting technologies for decommissioning of the large cylinder parts in the major components of NPPs Jeong, KwanSeong
2014
71 C p. 340-342
3 p.
article
5 A new concept of Monte Carlo kinetics parameter calculation using complex-valued perturbation Yamamoto, Toshihiro
2014
71 C p. 480-488
9 p.
article
6 A novel extension of chord length sampling method for TRISO-type fueled reactor applications Liang, Chao
2014
71 C p. 440-450
11 p.
article
7 A simplified approach to evaluating severe accident source term for PWR Huang, Gaofeng
2014
71 C p. 352-360
9 p.
article
8 Biogeochemical changes at early stage after the closure of radioactive waste geological repository in South Korea Choung, Sungwook
2014
71 C p. 6-10
5 p.
article
9 Boiling heat transfer and dryout in helically coiled tubes under different pressure conditions Chung, Young-Jong
2014
71 C p. 298-303
6 p.
article
10 Burnup estimation for plate type fuel assembly of research reactors through the least square fitting method Alawneh, Luay M.
2014
71 C p. 37-45
9 p.
article
11 Calculation of radiation heat transfer view factors among fuel rod bundles based on CFD method Yang, Lei
2014
71 C p. 462-466
5 p.
article
12 Comparison of a Modal Method and a Proper Orthogonal Decomposition approach for multi-group time-dependent reactor spatial kinetics Sartori, Alberto
2014
71 C p. 217-229
13 p.
article
13 Comparisons of prediction methods for peak cladding temperature and effective thermal conductivity in spent fuel assemblies of transportation/storage casks Kim, Hyungjin
2014
71 C p. 427-435
9 p.
article
14 Coupling of COBAYA3/SUBCHANFLOW inside the NURESIM platform and validation using selected benchmarks Calleja, M.
2014
71 C p. 145-158
14 p.
article
15 Design and analysis of operation performance of parameters of the integrated valve under the high temperature condition Liu, Qian-feng
2014
71 C p. 237-244
8 p.
article
16 Design of a model predictive load-following controller by discrete optimization of control rod speed for PWRs Kim, Jae Hwan
2014
71 C p. 343-351
9 p.
article
17 Development of a 1D transient electrorefiner model for pyroprocess simulation Cumberland, Riley M.
2014
71 C p. 52-59
8 p.
article
18 Development of Monte Carlo-based pebble bed reactor fuel management code Setiadipura, Topan
2014
71 C p. 313-321
9 p.
article
19 Development of the HELIOS/CAPP code system for the analysis of pebble type VHTR cores Lee, Hyun Chul
2014
71 C p. 130-144
15 p.
article
20 Dynamic sequence analysis for feed-and-bleed operation in an OPR1000 Kim, Bo Gyung
2014
71 C p. 361-375
15 p.
article
21 Economic analysis of two nuclear fuel cycle options Zhou, Chaoran
2014
71 C p. 230-236
7 p.
article
22 Editorial board 2014
71 C p. IFC-
1 p.
article
23 Effectiveness of source term optimization for higher disposal density of spent fuels in a deep geological repository Cho, Dong-Keun
2014
71 C p. 125-129
5 p.
article
24 Evaluation of the performance of peridotite aggregates for radiation shielding concrete Wang, Jinjun
2014
71 C p. 436-439
4 p.
article
25 Experimental and numerical testing of an innovative steam generator tube plugging procedure Nicolici, S.
2014
71 C p. 190-197
8 p.
article
26 Experimental verification on the integrity and performance of the passive residual heat removal system for a SMART design with VISTA-ITL Min, Byung-Yeon
2014
71 C p. 118-124
7 p.
article
27 Gamma and neutron attenuation behaviours of boron carbide–silicon carbide composites Buyuk, Bulent
2014
71 C p. 46-51
6 p.
article
28 Goal-based angular adaptivity applied to the spherical harmonics discretisation of the neutral particle transport equation Goffin, Mark A.
2014
71 C p. 60-80
21 p.
article
29 G4-STORK: A Geant4-based Monte Carlo reactor kinetics simulation code Russell, Liam
2014
71 C p. 451-461
11 p.
article
30 Improvement on the calculation of D2O moderated critical systems with new thermal neutron scattering libraries Márquez Damián, J.I.
2014
71 C p. 206-210
5 p.
article
31 Large scale applicability of a Fully Adaptive Non-Intrusive Spectral Projection technique: Sensitivity and uncertainty analysis of a transient Perkó, Zoltán
2014
71 C p. 272-292
21 p.
article
32 Measurement of isothermal temperature reactivity coefficient at research reactor with IRT-4M fuel Bily, Tomas
2014
71 C p. 91-96
6 p.
article
33 Monitoring and preventing numerical oscillations in 3D simulations with coupled Monte Carlo codes Kotlyar, D.
2014
71 C p. 198-205
8 p.
article
34 Neutronic and thermal hydraulic analyses of LEU targets irradiated in a research reactor for Molybdenum-99 production Jo, Daeseong
2014
71 C p. 467-474
8 p.
article
35 Numerical analysis of freezing controlled penetration behavior of the molten core debris in an instrument tube with MPS Chen, Ronghua
2014
71 C p. 322-332
11 p.
article
36 Numerical modelling of low-Reynolds number direct contact condensation in a suppression pool test facility Patel, G.
2014
71 C p. 376-387
12 p.
article
37 Numerical simulations of air–water cap-bubbly flows using two-group interfacial area transport equation Wang, Xia
2014
71 C p. 399-410
12 p.
article
38 On an analytical representation for the solution of the neutron point kinetics equation free of stiffness Wollmann da Silva, M.
2014
71 C p. 97-102
6 p.
article
39 On-line method to identify control rod drops in Pressurized Water Reactors Souza, T.J.
2014
71 C p. 293-297
5 p.
article
40 On-the-fly sampling of temperature-dependent thermal neutron scattering data for Monte Carlo simulations Pavlou, Andrew T.
2014
71 C p. 411-426
16 p.
article
41 Recommended dispersing conditions for broths used in the preparation of uranium microspheres with carbon Hunt, R.D.
2014
71 C p. 1-5
5 p.
article
42 SAC-CFR computer code verification with Experimental Breeder Reactor II loss-of-primary-flow-without-scram tests data Guo, Chao
2014
71 C p. 166-173
8 p.
article
43 Sensitivity analysis of CHF parameters under flow instability by using a neural network method Li, Jingjing
2014
71 C p. 211-216
6 p.
article
44 Stability improvement of noise analysis method in the case of random noise contamination for subcriticality measurements Kong, Chidong
2014
71 C p. 245-253
9 p.
article
45 Technical design and engineering prototype experiment of active magnetic bearing for helium blower of HTR-PM Yang, Guojun
2014
71 C p. 103-110
8 p.
article
46 The ADOPT code for automated fast reactor core design Qvist, Staffan
2014
71 C p. 23-36
14 p.
article
47 The complex nonlinear dynamics in the multiple boiling channels coupling with multi-point reactors with constant total flow rate Lee, Jin Der
2014
71 C p. 174-189
16 p.
article
48 The max–min ant system and tabu search for pressurized water reactor loading pattern design Lin, Chaung
2014
71 C p. 388-398
11 p.
article
49 Thermal analysis of prismatic gas-cooled reactor core under coolant channel blockage accidents Lee, Sung Nam
2014
71 C p. 11-22
12 p.
article
50 The scenario-based system of workers training to prevent accidents during decommissioning of nuclear facilities Jeong, KwanSeong
2014
71 C p. 475-479
5 p.
article
51 Three-dimensional single-channel thermal analysis of fully ceramic microencapsulated fuel via two-temperature homogenized model Lee, Yoonhee
2014
71 C p. 254-271
18 p.
article
52 UWB1 – Fast nuclear fuel depletion code Lovecký, M.
2014
71 C p. 333-339
7 p.
article
53 Verification of the BISON fuel performance code Hales, J.D.
2014
71 C p. 81-90
10 p.
article
                             53 results found
 
 Koninklijke Bibliotheek - National Library of the Netherlands