| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Accident analysis of heat pipe cooled and AMTEC conversion space reactor system
|
Yuan, Yuan
|
|
2016
|
94 |
C |
p. 706-715
|
artikel
|
| 2 |
A comparison between oxide and metallic fueled ASTRID-like reactors
|
García-Cervantes, E.-Y.
|
|
2016
|
94 |
C |
p. 350-358
|
artikel
|
| 3 |
Advances in the Pennsylvania State University NEM code
|
Thompson, S.A.
|
|
2016
|
94 |
C |
p. 251-262
|
artikel
|
| 4 |
Analysis of ASTEC-Na capabilities for simulating a loss of flow CABRI experiment
|
Flores y Flores, A.
|
|
2016
|
94 |
C |
p. 175-188
|
artikel
|
| 5 |
Analysis of containment venting strategy under severe accident conditions
|
Lee, Na Rae
|
|
2016
|
94 |
C |
p. 633-642
|
artikel
|
| 6 |
Analysis of neutronics benchmarks for the utilization of mixed oxide fuel in light water reactor using DRAGON code
|
Nithyadevi, Rajan
|
|
2016
|
94 |
C |
p. 643-654
|
artikel
|
| 7 |
Analytical results for the skewness of the distribution of detector counts in a subcritical reactor
|
Difilippo, Felix C.
|
|
2016
|
94 |
C |
p. 208-212
|
artikel
|
| 8 |
An assessment of temperature history on concrete silo dry storage system for CANDU spent fuel
|
Lee, Dong-Gyu
|
|
2016
|
94 |
C |
p. 263-271
|
artikel
|
| 9 |
An efficient space-angle subgrid scale discretisation of the neutron transport equation
|
Buchan, A.G.
|
|
2016
|
94 |
C |
p. 440-450
|
artikel
|
| 10 |
An estimation to measure and to evaluate the work times following the trajectory of workers during decommissioning of nuclear facilities
|
Jeong, KwanSeong
|
|
2016
|
94 |
C |
p. 10-15
|
artikel
|
| 11 |
An evaluation and acceptance of COTS software for FPGA-based controllers in NPPS
|
Jung, Sejin
|
|
2016
|
94 |
C |
p. 338-349
|
artikel
|
| 12 |
An evaluation of thermowell’s integrity in RCP test facility
|
Kim, Yeon-Sik
|
|
2016
|
94 |
C |
p. 55-61
|
artikel
|
| 13 |
A nonlinear reactivity method with application to accident-tolerant fuels
|
Roberts, Jeremy A.
|
|
2016
|
94 |
C |
p. 581-588
|
artikel
|
| 14 |
An optimization study on the excess reactivity in a linear breed-and-burn fast reactor (B&BR)
|
Hartanto, Donny
|
|
2016
|
94 |
C |
p. 62-71
|
artikel
|
| 15 |
Application of h-adaptivity to the interface current collision probability method
|
Safarzadeh, O.
|
|
2016
|
94 |
C |
p. 826-831
|
artikel
|
| 16 |
Application of Serpent 2 and MCNP6 to study different criticality configurations of a VVER-1000 mock-up
|
Chersola, D.
|
|
2016
|
94 |
C |
p. 109-122
|
artikel
|
| 17 |
Assessment of the countermeasure improvement of ABWR using RETRAN-3D
|
Hamada, Yuhei
|
|
2016
|
94 |
C |
p. 223-229
|
artikel
|
| 18 |
A stability assessment of optimum Fuel Reload Patterns for a BWR
|
Castillo-Durán, Rogelio
|
|
2016
|
94 |
C |
p. 841-847
|
artikel
|
| 19 |
A subchannel based annular flow dryout model
|
Hammouda, Najmeddine
|
|
2016
|
94 |
C |
p. 313-324
|
artikel
|
| 20 |
Automatic construction of a simplified burn-up chain model by the singular value decomposition
|
Kajihara, Takanori
|
|
2016
|
94 |
C |
p. 742-749
|
artikel
|
| 21 |
Biasing secondary particle interaction physics and production in MCNP6
|
Fensin, M.L.
|
|
2016
|
94 |
C |
p. 618-625
|
artikel
|
| 22 |
CAD-based hierarchical geometry conversion method for modeling of fission reactor cores
|
Gan, Quan
|
|
2016
|
94 |
C |
p. 369-375
|
artikel
|
| 23 |
CFD simulation for the optimal design and utilization of experiment to research the flow process in PWR
|
Chen, Guangliang
|
|
2016
|
94 |
C |
p. 1-9
|
artikel
|
| 24 |
CFD simulations on the dynamics of liquid sloshing and its control in a storage tank for spent fuel applications
|
Sanapala, V.S.
|
|
2016
|
94 |
C |
p. 494-509
|
artikel
|
| 25 |
Comparison analysis of temperature fluctuations for double jet of liquid metal cooled fast reactor
|
Wang, Lizhi
|
|
2016
|
94 |
C |
p. 802-807
|
artikel
|
| 26 |
Computer code ENDSAM for random sampling and validation of the resonance parameters covariance matrices of some major nuclear data libraries
|
Plevnik, Lucijan
|
|
2016
|
94 |
C |
p. 510-517
|
artikel
|
| 27 |
Core design optimization and analysis of the Purdue Novel Modular Reactor (NMR-50)
|
Odeh, Faisal Y.
|
|
2016
|
94 |
C |
p. 288-299
|
artikel
|
| 28 |
Correlation of errors in the Monte Carlo fission source and the fission matrix fundamental-mode eigenvector
|
Dufek, Jan
|
|
2016
|
94 |
C |
p. 415-421
|
artikel
|
| 29 |
Coupled probabilistic and point kinetics modelling of fast pulses in nuclear systems
|
Cooling, C.M.
|
|
2016
|
94 |
C |
p. 655-671
|
artikel
|
| 30 |
Design and performance evaluation of Core Flow Monitoring Mechanisms for PFBR
|
Sabih, Muhammad
|
|
2016
|
94 |
C |
p. 732-741
|
artikel
|
| 31 |
Design study and cost assessment of straight, zigzag, S-shape, and OSF PCHEs for a FLiNaK–SCO2 Secondary Heat Exchanger in FHRs
|
Kim, In Hun
|
|
2016
|
94 |
C |
p. 129-137
|
artikel
|
| 32 |
Development of on-the-fly temperature-dependent cross-sections treatment in RMC code
|
Liu, Shichang
|
|
2016
|
94 |
C |
p. 144-149
|
artikel
|
| 33 |
Editorial board
|
|
|
2016
|
94 |
C |
p. IFC
|
artikel
|
| 34 |
Effect of diameter and axial location on upward gas–liquid two-phase flow patterns in intermediate-scale vertical tubes
|
Ansari, M.R.
|
|
2016
|
94 |
C |
p. 530-540
|
artikel
|
| 35 |
Effect of friction on pebble flow pattern in pebble bed reactor
|
Li, Yu
|
|
2016
|
94 |
C |
p. 32-43
|
artikel
|
| 36 |
Effects of Pu and MA uniform and nonuniform distributions on subcritical multiplication of TRIGA Mark II ADS reactor
|
Shahbunder, Hesham
|
|
2016
|
94 |
C |
p. 332-337
|
artikel
|
| 37 |
Electrochemical corrosion of Zircaloy-2 under PWR water chemistry but at room temperature
|
Waheed, Abdel-Aziz Fahmy
|
|
2016
|
94 |
C |
p. 168-174
|
artikel
|
| 38 |
Estimation of the radionuclides emission region using trajectory and atmospheric dispersion models
|
Suh, Kyung-Suk
|
|
2016
|
94 |
C |
p. 626-632
|
artikel
|
| 39 |
Evaluation of in-vessel corium retention margin for small modular reactor ACP100
|
Zhu, Dahuan
|
|
2016
|
94 |
C |
p. 684-690
|
artikel
|
| 40 |
Experimental and analytical studies on heat transfer in a scaled intermediate heat exchanger with water
|
Takano, Masahito
|
|
2016
|
94 |
C |
p. 691-705
|
artikel
|
| 41 |
Experimental study of composition and influence factors on fouling of stainless steel and copper in seawater
|
Yang, Dazhang
|
|
2016
|
94 |
C |
p. 767-772
|
artikel
|
| 42 |
Fire risk analysis based on one-dimensional model in nuclear power plant
|
Yu, Yu
|
|
2016
|
94 |
C |
p. 409-414
|
artikel
|
| 43 |
HAZOP application for the nuclear power plants decommissioning projects
|
Rimkevičius, Sigitas
|
|
2016
|
94 |
C |
p. 461-471
|
artikel
|
| 44 |
Hydrogen risk for advanced PWR under typical severe accidents induced by DVI line break
|
Tong, L.L.
|
|
2016
|
94 |
C |
p. 325-331
|
artikel
|
| 45 |
Improvement of CANDU safety parameters by using the CANFLEX fuel
|
Kim, Woosong
|
|
2016
|
94 |
C |
p. 793-801
|
artikel
|
| 46 |
Improvement of core design of small pebble bed reactor with accumulative fuel loading scheme
|
Simanullang, Irwan Liapto
|
|
2016
|
94 |
C |
p. 87-92
|
artikel
|
| 47 |
Improving collaborative work and project management in a nuclear power plant design team: A human-centered design approach
|
Boy, Guy André
|
|
2016
|
94 |
C |
p. 555-565
|
artikel
|
| 48 |
Investigation of different burnable absorbers effects on the neutronic characteristics of PWR assembly
|
Galahom, A. Abdelghafar
|
|
2016
|
94 |
C |
p. 22-31
|
artikel
|
| 49 |
Local bifurcation analysis in nuclear reactor dynamics by Sotomayor’s theorem
|
Pirayesh, Behnam
|
|
2016
|
94 |
C |
p. 716-731
|
artikel
|
| 50 |
Mechanical analysis of flying robot for nuclear safety and security control by radiological monitoring
|
Cho, Hyo Sung
|
|
2016
|
94 |
C |
p. 138-143
|
artikel
|
| 51 |
Mechanism study and theoretical simulation on heat split phenomenon in dual-cooled annular fuel element
|
Deng, Yangbin
|
|
2016
|
94 |
C |
p. 44-54
|
artikel
|
| 52 |
Monte Carlo criticality calculations accelerated by a growing neutron population
|
Dufek, Jan
|
|
2016
|
94 |
C |
p. 16-21
|
artikel
|
| 53 |
Monte Carlo power iteration: Entropy and spatial correlations
|
Nowak, Michel
|
|
2016
|
94 |
C |
p. 856-868
|
artikel
|
| 54 |
Natural circulation heat transfer model development over vertical tube bundle in the condensate heat exchanger
|
Chung, Young Jong
|
|
2016
|
94 |
C |
p. 759-766
|
artikel
|
| 55 |
Neutron deep penetration through reactor pressure vessel and biological concrete shield of VVER-1000 Mock-Up in LR-0 reactor
|
Košťál, Michal
|
|
2016
|
94 |
C |
p. 672-683
|
artikel
|
| 56 |
Neutron flux monitoring with in-vessel fission chambers to detect an inadvertent control rod withdrawal in a sodium-cooled fast reactor
|
Verma, V.
|
|
2016
|
94 |
C |
p. 487-493
|
artikel
|
| 57 |
Neutronic calculations of the MTR-22MW research reactor loaded with MOX (PuO2&UO2) Caramel fuel using the MCNP5 Code
|
Shaaban, Ismail
|
|
2016
|
94 |
C |
p. 478-486
|
artikel
|
| 58 |
Nuclear data uncertainty propagation analysis for depletion calculation in PWR and FR pin-cells
|
Zu, Tiejun
|
|
2016
|
94 |
C |
p. 399-408
|
artikel
|
| 59 |
Nuclear data uncertainty propagation on spent fuel nuclide compositions
|
Leray, O.
|
|
2016
|
94 |
C |
p. 603-611
|
artikel
|
| 60 |
Nuclear emulsion measuring the prompt fission neutron spectrum of 238U induced by 2.8MeV neutrons
|
Wen, Weiping
|
|
2016
|
94 |
C |
p. 576-580
|
artikel
|
| 61 |
Numerical analysis on hydrogen stratification and post-inerting of hydrogen risk
|
Peng, Cheng
|
|
2016
|
94 |
C |
p. 451-460
|
artikel
|
| 62 |
Numerical analysis on the effect of flow rates and jet diameter in rewetting vertical nuclear fuel bundle with jet impingements
|
Debbarma, Ajoy
|
|
2016
|
94 |
C |
p. 518-529
|
artikel
|
| 63 |
Numerical and experimental investigation on the baffle design in secondary side of the PRHR HX in AP1000
|
Lu, Daogang
|
|
2016
|
94 |
C |
p. 359-368
|
artikel
|
| 64 |
On the relation between Rossi alpha and Feynman alpha methods
|
Degweker, S.B.
|
|
2016
|
94 |
C |
p. 433-439
|
artikel
|
| 65 |
Optimal design method for a digital human–computer interface based on human reliability in a nuclear power plant. Part 3: Optimization method for interface task layout
|
Jiang, Jianjun
|
|
2016
|
94 |
C |
p. 750-758
|
artikel
|
| 66 |
Optimization of PWR design parameters for implementation in SMRs
|
Ashiq, Muhammad
|
|
2016
|
94 |
C |
p. 123-128
|
artikel
|
| 67 |
Origin and validity of graphite dosimetry units and related conversion factors
|
Black, G.
|
|
2016
|
94 |
C |
p. 241-250
|
artikel
|
| 68 |
Parameterized representation of macroscopic cross section in burn-up cycles
|
Fiel, João Claudio B.
|
|
2016
|
94 |
C |
p. 472-477
|
artikel
|
| 69 |
Parametric studies of the PWR fuel assembly modeling with Monte-Carlo method
|
Kępisty, Grzegorz
|
|
2016
|
94 |
C |
p. 189-207
|
artikel
|
| 70 |
Performance comparison and optimization of two configurations of (Very) high temperature gas-cooled reactors combined cycles
|
Wang, Jie
|
|
2016
|
94 |
C |
p. 279-287
|
artikel
|
| 71 |
Performance test of MARS-LMR code with benchmark analysis of EBR-II SHRT-17
|
Choi, Chiwoong
|
|
2016
|
94 |
C |
p. 376-391
|
artikel
|
| 72 |
Phenomena identification and ranking table for passive residual heat removal system in IRWST
|
Li, Xiangbin
|
|
2016
|
94 |
C |
p. 80-86
|
artikel
|
| 73 |
Power transient analysis of fuel-loaded reflector experimental devices in Jules Horowitz Material Testing Reactor
|
Console Camprini, P.
|
|
2016
|
94 |
C |
p. 541-554
|
artikel
|
| 74 |
Prediction of golden time using SVR for recovering SIS under severe accidents
|
Yoo, Kwae Hwan
|
|
2016
|
94 |
C |
p. 102-108
|
artikel
|
| 75 |
Pressure drop and average void fraction measurements for two-phase flow through highly permeable porous media
|
Chikhi, N.
|
|
2016
|
94 |
C |
p. 422-432
|
artikel
|
| 76 |
Proposed methodology for Passive Autocatalytic Recombiner sizing and location for a BWR Mark-III reactor containment building
|
Serrano, César
|
|
2016
|
94 |
C |
p. 589-602
|
artikel
|
| 77 |
Quantum evolutionary algorithm and tabu search in pressurized water reactor loading pattern design
|
Wu, Shun-Chi
|
|
2016
|
94 |
C |
p. 773-782
|
artikel
|
| 78 |
Re-evaluation of the thermal neutron capture cross section of 147Nd
|
Rochman, D.
|
|
2016
|
94 |
C |
p. 612-617
|
artikel
|
| 79 |
Shielding technology for upper structure of HTTR
|
Ueta, Shohei
|
|
2016
|
94 |
C |
p. 72-79
|
artikel
|
| 80 |
Simplification of transition state diagrams via Generalized Perturbation Theory in the Markovian reliability analysis of aging safety systems
|
Vicente, R.C.
|
|
2016
|
94 |
C |
p. 155-167
|
artikel
|
| 81 |
Standardized verification of fuel cycle modeling
|
Feng, B.
|
|
2016
|
94 |
C |
p. 300-312
|
artikel
|
| 82 |
The impact of heavy reflectors on power distribution perturbations in large PWR reactor cores
|
Sargeni, A.
|
|
2016
|
94 |
C |
p. 566-575
|
artikel
|
| 83 |
The influence of void-reactivity feedback on the bifurcation phenomena and nonlinear characteristics of a single nuclear-coupled boiling channel
|
Lee, Jin-Der
|
|
2016
|
94 |
C |
p. 814-825
|
artikel
|
| 84 |
The least-squares method based on coupling coefficients for reactor power distribution reconstruction
|
Peng, Xingjie
|
|
2016
|
94 |
C |
p. 272-278
|
artikel
|
| 85 |
The numerical solution of space-dependent neutron kinetics equations in hexagonal-z geometry using Diagonally Implicit Runge Kutta method
|
Cai, Yun
|
|
2016
|
94 |
C |
p. 150-154
|
artikel
|
| 86 |
Theoretical study of hydraulic jump during circular horizontal hot leg injection in pressurized water reactor
|
El Hawary, Shehab
|
|
2016
|
94 |
C |
p. 783-792
|
artikel
|
| 87 |
Thermal conductivity of compacted bentonite as a buffer material for a high-level radioactive waste repository
|
Lee, Jae Owan
|
|
2016
|
94 |
C |
p. 848-855
|
artikel
|
| 88 |
Uncertainty in RELAP5/MOD3.2 calculations for interfacial drag in downward two-phase flow
|
Clark, Collin
|
|
2016
|
94 |
C |
p. 230-240
|
artikel
|
| 89 |
Updating of the public dose assessment approach for decommissioning related releases from the Ignalina NPP
|
Ragaišis, Valdas
|
|
2016
|
94 |
C |
p. 93-101
|
artikel
|
| 90 |
Use of Effective Diffusion Homogenization method with the Monte Carlo code for light water reactor
|
Ćalić, Dušan
|
|
2016
|
94 |
C |
p. 392-398
|
artikel
|
| 91 |
Validation of the finned sodium–air heat exchanger model in MARS-LMR
|
Choi, C.W.
|
|
2016
|
94 |
C |
p. 213-222
|
artikel
|
| 92 |
Void penetration length from air injection through a downward large diameter submerged pipe in water pool
|
Rassame, Somboon
|
|
2016
|
94 |
C |
p. 832-840
|
artikel
|
| 93 |
Walking path-planning method for multiple radiation areas
|
Liu, Yong-kuo
|
|
2016
|
94 |
C |
p. 808-813
|
artikel
|
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