| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A ∞ and A N formulations of the linear transport equation in heterogeneous media
|
Coppa, G.
|
|
2016
|
87 |
P2 |
p. 630-636
7 p.
|
artikel
|
| 2 |
A comparison of Monte Carlo methods for neutron leakage at assembly level
|
Dorval, E.
|
|
2016
|
87 |
P2 |
p. 591-600
10 p.
|
artikel
|
| 3 |
Adoption of nitrogen power conversion system for small scale ultra-long cycle fast reactor eliminating intermediate sodium loop
|
Seo, Seok Bin
|
|
2016
|
87 |
P2 |
p. 621-629
9 p.
|
artikel
|
| 4 |
A multi-physics reduced order model for the analysis of Lead Fast Reactor single channel
|
Sartori, Alberto
|
|
2016
|
87 |
P2 |
p. 198-208
11 p.
|
artikel
|
| 5 |
A new SP n theory formulation with self-consistent physical assumptions on angular flux
|
Chao, Yung-An
|
|
2016
|
87 |
P2 |
p. 137-144
8 p.
|
artikel
|
| 6 |
An integrated approach to sensor FDI and signal reconstruction in HTGRs – Part II: Case studies
|
Uren, Kenneth R.
|
|
2016
|
87 |
P2 |
p. 739-749
11 p.
|
artikel
|
| 7 |
An integrated approach to sensor FDI and signal reconstruction in HTGRs – Part I: Theoretical framework
|
Uren, Kenneth R.
|
|
2016
|
87 |
P2 |
p. 750-760
11 p.
|
artikel
|
| 8 |
Assessment of assembly homogenized two-steps core dynamic calculations using direct whole core transport solutions
|
Hursin, Mathieu
|
|
2016
|
87 |
P2 |
p. 356-365
10 p.
|
artikel
|
| 9 |
A tightly coupled scheme for neutronics and thermal–hydraulics using open-source software
|
Wu, Hsingtzu
|
|
2016
|
87 |
P2 |
p. 16-22
7 p.
|
artikel
|
| 10 |
A unified methodology for single- and multiobjective in-core fuel management optimisation based on augmented Chebyshev scalarisation and a harmony search algorithm
|
Schlünz, E.B.
|
|
2016
|
87 |
P2 |
p. 659-670
12 p.
|
artikel
|
| 11 |
CAD-based Monte Carlo automatic modeling method based on primitive solid
|
Wang, Dong
|
|
2016
|
87 |
P2 |
p. 162-166
5 p.
|
artikel
|
| 12 |
Characterization of velocity and temperature fields in a 217 pin wire wrapped fuel bundle of sodium cooled fast reactor
|
Naveen Raj, M.
|
|
2016
|
87 |
P2 |
p. 331-349
19 p.
|
artikel
|
| 13 |
Code improvement and model validation for Ascó-II Nuclear Power Plant model using a coupled 3D neutron kinetics/thermal–hydraulic code
|
Pericas, R.
|
|
2016
|
87 |
P2 |
p. 366-374
9 p.
|
artikel
|
| 14 |
Comparison of critical flow models for SBLOCA tests of the ATLAS facility
|
Kim, Yeon-Sik
|
|
2016
|
87 |
P2 |
p. 435-442
8 p.
|
artikel
|
| 15 |
Computational fluid dynamics study on cross flow pressure drop for triangular array rod assemblies with wire
|
Pramuditya, Syeilendra
|
|
2016
|
87 |
P2 |
p. 803-816
14 p.
|
artikel
|
| 16 |
Computing eigenvalue sensitivity coefficients to nuclear data by adjoint superhistory method and adjoint Wielandt method implemented in RMC code
|
Qiu, Yishu
|
|
2016
|
87 |
P2 |
p. 228-241
14 p.
|
artikel
|
| 17 |
Control parameter optimization for AP1000 reactor using Particle Swarm Optimization
|
Wang, Pengfei
|
|
2016
|
87 |
P2 |
p. 687-695
9 p.
|
artikel
|
| 18 |
Control rod drop transient analysis with the coupled parallel code pCTF-PARCSv2.7
|
Ramos, Enrique
|
|
2016
|
87 |
P2 |
p. 308-317
10 p.
|
artikel
|
| 19 |
COPRA experiments on natural convection heat transfer in a volumetrically heated slice pool with high Rayleigh numbers
|
Zhang, Luteng
|
|
2016
|
87 |
P2 |
p. 81-88
8 p.
|
artikel
|
| 20 |
Criticality validation of SuperMC with ICSBEP
|
Zhang, Binhang
|
|
2016
|
87 |
P2 |
p. 494-499
6 p.
|
artikel
|
| 21 |
CRUD, boron, and burnable absorber layer 2-D modeling requirements using MOC neutron transport
|
Walter, Daniel J.
|
|
2016
|
87 |
P2 |
p. 388-399
12 p.
|
artikel
|
| 22 |
3D/2D rotational plane slicing method for 3D whole-core transport calculation
|
Yoo, Han Jong
|
|
2016
|
87 |
P2 |
p. 30-38
9 p.
|
artikel
|
| 23 |
Depletion benchmarks calculation of random media using explicit modeling approach of RMC
|
Liu, Shichang
|
|
2016
|
87 |
P2 |
p. 167-175
9 p.
|
artikel
|
| 24 |
Design and neutronic investigation of the Nano fluids application to VVER-1000 nuclear reactor with dual cooled annular fuel
|
Ansarifar, G.R.
|
|
2016
|
87 |
P2 |
p. 39-47
9 p.
|
artikel
|
| 25 |
Design concept for a small pebble bed reactor with ROX fuel
|
Ho, Hai Quan
|
|
2016
|
87 |
P2 |
p. 471-478
8 p.
|
artikel
|
| 26 |
Determination of the maximum speed of WWER-1000 nuclear reactor control rods
|
Khoshahval, Farrokh
|
|
2016
|
87 |
P2 |
p. 58-68
11 p.
|
artikel
|
| 27 |
Development of a portable heavy-water leak sensor based on laser absorption spectroscopy
|
Lee, Lim
|
|
2016
|
87 |
P2 |
p. 350-355
6 p.
|
artikel
|
| 28 |
Development of a PWR-W GOTHIC 3D model for containment accident analysis
|
Bocanegra, Rafael
|
|
2016
|
87 |
P2 |
p. 547-560
14 p.
|
artikel
|
| 29 |
Development strategy and conceptual design of China Lead-based Research Reactor
|
Wu, Yican
|
|
2016
|
87 |
P2 |
p. 511-516
6 p.
|
artikel
|
| 30 |
Directional diffusion coefficients and leakage-corrected discontinuity factors: Implementation in Serpent and tests
|
Dorval, E.
|
|
2016
|
87 |
P2 |
p. 101-112
12 p.
|
artikel
|
| 31 |
Editorial board
|
|
|
2016
|
87 |
P2 |
p. IFC-
1 p.
|
artikel
|
| 32 |
Establishment of the hazard reduction methodology to be taken into account for safety assessment during decommissioning of nuclear facilities
|
Jeong, KwanSeong
|
|
2016
|
87 |
P2 |
p. 7-15
9 p.
|
artikel
|
| 33 |
Evaluation method of iodine re-evolution from an in-containment water pool after a loss of coolant accident, Part I: pH estimation of a solution with various chemicals
|
Kim, Tae Hyeon
|
|
2016
|
87 |
P2 |
p. 324-330
7 p.
|
artikel
|
| 34 |
Evaluation of burnable absorber rods effect on neutronic performance in fuel assembly of WWER-1000 reactor
|
Khoshahval, Farrokh
|
|
2016
|
87 |
P2 |
p. 648-658
11 p.
|
artikel
|
| 35 |
Experimental study on fundamental phenomena in HTGR small break air-ingress accident
|
Kim, Jae Soon
|
|
2016
|
87 |
P2 |
p. 145-156
12 p.
|
artikel
|
| 36 |
Features of MCNP6
|
Goorley, T.
|
|
2016
|
87 |
P2 |
p. 772-783
12 p.
|
artikel
|
| 37 |
Flow and heat transfer in laminar–turbulent transitional flow regime under rolling motion
|
Yuan, Hongsheng
|
|
2016
|
87 |
P2 |
p. 527-536
10 p.
|
artikel
|
| 38 |
Heat transfer of water flowing upward in vertical annuli with spacers at high pressure conditions
|
Zhao, M.
|
|
2016
|
87 |
P2 |
p. 209-216
8 p.
|
artikel
|
| 39 |
High Conversion Th–U233 fuel for current generation of PWRs: Part III – Fuel availability and utilization considerations
|
Baldova, D.
|
|
2016
|
87 |
P2 |
p. 517-526
10 p.
|
artikel
|
| 40 |
Human error and the associated recovery probabilities for soft control being used in the advanced MCRs of NPPs
|
Jang, Inseok
|
|
2016
|
87 |
P2 |
p. 290-298
9 p.
|
artikel
|
| 41 |
Identification and categorisation of safety issues for ESNII reactor concepts. Part I: Common phenomena related to materials
|
Tuček, K.
|
|
2016
|
87 |
P2 |
p. 411-425
15 p.
|
artikel
|
| 42 |
Impact of power density profile on passive decay heat removal in prismatic HTGR
|
Sambuu, Odmaa
|
|
2016
|
87 |
P2 |
p. 23-29
7 p.
|
artikel
|
| 43 |
Impact of proof test interval and coverage on probability of failure of safety instrumented function
|
Jin, Jianghong
|
|
2016
|
87 |
P2 |
p. 537-540
4 p.
|
artikel
|
| 44 |
Implementation of condition-dependent probabilistic risk assessment using surveillance data on passive components
|
Lewandowski, Radoslaw
|
|
2016
|
87 |
P2 |
p. 696-706
11 p.
|
artikel
|
| 45 |
Improvements to the Transmutation Trajectory Analysis of depletion evaluation
|
Huang, Kai
|
|
2016
|
87 |
P2 |
p. 637-647
11 p.
|
artikel
|
| 46 |
In-phase instabilities in BWR with sub-cooled boiling, direct heating, and spacers effects
|
Muñoz-Cobo, José L.
|
|
2016
|
87 |
P2 |
p. 671-686
16 p.
|
artikel
|
| 47 |
Introducing time in derivation of the scaling factor for MCNP criticality calculations
|
Yang, Yang
|
|
2016
|
87 |
P2 |
p. 385-387
3 p.
|
artikel
|
| 48 |
Investigations of single-phase flow mixing characteristics in a wire-wrapped 37-pin bundle for a sodium-cooled fast reactor
|
Kim, Hyungmo
|
|
2016
|
87 |
P2 |
p. 541-546
6 p.
|
artikel
|
| 49 |
Measurement of sub-critical reactivity in a heavy water reactor by neutron noise methods using a time stamping data acquisition system
|
Kumar, Rajeev
|
|
2016
|
87 |
P2 |
p. 720-727
8 p.
|
artikel
|
| 50 |
Micro-Pocket Fission Detectors (MPFDs) for in-core neutron detection
|
Reichenberger, Michael A.
|
|
2016
|
87 |
P2 |
p. 318-323
6 p.
|
artikel
|
| 51 |
Modeling the thermal stress of heat transfer tubes with tube support plate gaps in a steam generator
|
Sun, Baozhi
|
|
2016
|
87 |
P2 |
p. 400-410
11 p.
|
artikel
|
| 52 |
Monte Carlo modeling of the Pakistan Research Reactor-1 (PARR-1)
|
Ali, M. Rizwan
|
|
2016
|
87 |
P2 |
p. 584-590
7 p.
|
artikel
|
| 53 |
Nanoscopic designs of radiological protection in environmental scale for the Fukushima nuclear accident: Strategy by dispersion, dissolution, and filtration
|
Woo, Tae Ho
|
|
2016
|
87 |
P2 |
p. 569-574
6 p.
|
artikel
|
| 54 |
New derivation of Blackshow–Murrays formula for the Doppler-broadened scattering kernel and calculation of the angular moments via Lagrange interpolation
|
Sanchez, Richard
|
|
2016
|
87 |
P2 |
p. 113-125
13 p.
|
artikel
|
| 55 |
Nodal collocation method for the multidimensional P L equations applied to neutron transport source problems
|
Capilla, M.T.
|
|
2016
|
87 |
P2 |
p. 89-100
12 p.
|
artikel
|
| 56 |
Numerical analysis of the dust distribution during LOVA
|
Tong, L.L.
|
|
2016
|
87 |
P2 |
p. 454-461
8 p.
|
artikel
|
| 57 |
Numerical implementation, verification and validation of two-phase flow four-equation drift flux model with Jacobian-free Newton–Krylov method
|
Zou, Ling
|
|
2016
|
87 |
P2 |
p. 707-719
13 p.
|
artikel
|
| 58 |
Numerical simulation and experimental verification of microstructure evolution in large forged pipe used for AP1000 nuclear power plants
|
Wang, Shenglong
|
|
2016
|
87 |
P2 |
p. 176-185
10 p.
|
artikel
|
| 59 |
Passive Non-Destructive Assay based on gamma-ray spectrometry to verify UO2 samples in the form of powder and pellet
|
Tohamy, M.
|
|
2016
|
87 |
P2 |
p. 186-191
6 p.
|
artikel
|
| 60 |
Performance of iodide vapour absorption in the venturi scrubber working in self-priming mode
|
Zhou, Yanmin
|
|
2016
|
87 |
P2 |
p. 426-434
9 p.
|
artikel
|
| 61 |
Pressure wave propagation phenomena in the pipe system of a nuclear power plant
|
Yi, Sung-Jae
|
|
2016
|
87 |
P2 |
p. 157-161
5 p.
|
artikel
|
| 62 |
PSA model with consideration of the effect of fault-tolerant techniques in digital I&C systems
|
Lee, Seung Jun
|
|
2016
|
87 |
P2 |
p. 375-384
10 p.
|
artikel
|
| 63 |
Quantifying the effects of depletion parameters on the PWR spent fuel reactivity based on nuclide sensitivity coefficients
|
Sheu, Rong-Jiun
|
|
2016
|
87 |
P2 |
p. 126-136
11 p.
|
artikel
|
| 64 |
Re-evaluation of spent nuclear fuel assay data for the Three Mile Island unit 1 reactor and application to code validation
|
Gauld, I.C.
|
|
2016
|
87 |
P2 |
p. 267-281
15 p.
|
artikel
|
| 65 |
Review calculations for the OECD/NEA Burn-up Credit Criticality Safety Benchmark
|
Herrero, José J.
|
|
2016
|
87 |
P2 |
p. 48-57
10 p.
|
artikel
|
| 66 |
Review study of virtual reality techniques used at nuclear issues with emphasis on Brazilian research
|
da Silva, Márcio Henrique
|
|
2016
|
87 |
P2 |
p. 192-197
6 p.
|
artikel
|
| 67 |
Risk assessment on abnormal accidents from human errors during decommissioning of nuclear facilities
|
Jeong, KwanSeong
|
|
2016
|
87 |
P2 |
p. 1-6
6 p.
|
artikel
|
| 68 |
Safety analysis of MTR type research reactor during postulated beam tube break inducing positive reactivity
|
Khakim, Azizul
|
|
2016
|
87 |
P2 |
p. 793-798
6 p.
|
artikel
|
| 69 |
Simulation of the airborne radioactive substance distribution and monitoring of coolant leakage in a typical Nuclear Reactor Containment
|
Zheng, Ya
|
|
2016
|
87 |
P2 |
p. 462-470
9 p.
|
artikel
|
| 70 |
Small break LOCA analysis without emergency core cooling systems using the RELAP5/SCDAP code in VVER-1000 reactor
|
Salehi, Mohsen
|
|
2016
|
87 |
P2 |
p. 299-307
9 p.
|
artikel
|
| 71 |
Sodium flow measurement in large pipelines of sodium cooled fast breeder reactors with bypass type flow meters
|
Rajan, K.K.
|
|
2016
|
87 |
P2 |
p. 74-80
7 p.
|
artikel
|
| 72 |
Solving the multigroup integro-differential equation of the neutron diffusion kinetics in 3D-Cartesian geometry
|
Quintero-Leyva, Barbaro
|
|
2016
|
87 |
P2 |
p. 282-289
8 p.
|
artikel
|
| 73 |
Stability analysis of the Backward Euler time discretization for the pin-resolved transport transient reactor calculation
|
Zhu, Ang
|
|
2016
|
87 |
P2 |
p. 252-266
15 p.
|
artikel
|
| 74 |
Static and transient analysis of a medium-sized sodium cooled fast reactor loaded with oxide, nitride, carbide and metallic fuels
|
Zhang, Youpeng
|
|
2016
|
87 |
P2 |
p. 761-771
11 p.
|
artikel
|
| 75 |
Study of graphite reactivity worth on well-defined cores assembled on LR-0 reactor
|
Košťál, Michal
|
|
2016
|
87 |
P2 |
p. 601-611
11 p.
|
artikel
|
| 76 |
System scaling analysis for modeling small break LOCA using the FULL SPECTRUM LOCA evaluation model
|
Liao, Jun
|
|
2016
|
87 |
P2 |
p. 443-453
11 p.
|
artikel
|
| 77 |
The application of transient analysis code to estimation of total released energy in a two-fuel-solution-tank system
|
Kikuchi, Haruka
|
|
2016
|
87 |
P2 |
p. 486-493
8 p.
|
artikel
|
| 78 |
The neutron point kinetics equation: Suppression of fractional derivative effects by temperature feedback
|
Schramm, M.
|
|
2016
|
87 |
P2 |
p. 479-485
7 p.
|
artikel
|
| 79 |
Theoretical basis of quantification for layer of protection analysis (LOPA)
|
Jin, Jianghong
|
|
2016
|
87 |
P2 |
p. 69-73
5 p.
|
artikel
|
| 80 |
Thermal conductivity of perspective fuel based on uranium nitride
|
Solntceva, E.S.
|
|
2016
|
87 |
P2 |
p. 799-802
4 p.
|
artikel
|
| 81 |
Thermal–hydraulic modeling and transient analysis of helium-cooled tungsten target coupled with ADS core
|
Peng, Tianji
|
|
2016
|
87 |
P2 |
p. 612-620
9 p.
|
artikel
|
| 82 |
Thermal neutron scattering cross sections of beryllium and magnesium oxides
|
Al-Qasir, Iyad
|
|
2016
|
87 |
P2 |
p. 242-251
10 p.
|
artikel
|
| 83 |
Thermal stability investigation technique for uranium nitride
|
Baranov, V.G.
|
|
2016
|
87 |
P2 |
p. 784-792
9 p.
|
artikel
|
| 84 |
Three higher order analytical nodal methods for multigroup neutron diffusion equations
|
Guessous, Najib
|
|
2016
|
87 |
P2 |
p. 561-568
8 p.
|
artikel
|
| 85 |
Transient analyses of the Jordanian 5MW research reactor under LOEP accident
|
Al-Yahia, Omar S.
|
|
2016
|
87 |
P2 |
p. 575-583
9 p.
|
artikel
|
| 86 |
Transient identification by clustering based on Integrated Deterministic and Probabilistic Safety Analysis outcomes
|
Di Maio, Francesco
|
|
2016
|
87 |
P2 |
p. 217-227
11 p.
|
artikel
|
| 87 |
Ultimate analysis of PWR prestressed concrete containment under long-term prestressing loss
|
Hu, Hsuan-Teh
|
|
2016
|
87 |
P2 |
p. 500-510
11 p.
|
artikel
|
| 88 |
Use of discontinuity factors in high-order finite element methods
|
Vidal-Ferràndiz, A.
|
|
2016
|
87 |
P2 |
p. 728-738
11 p.
|
artikel
|
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