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 |
|
P2 |
p. 630-636 7 p. |
artikel |
2 |
A comparison of Monte Carlo methods for neutron leakage at assembly level
|
Dorval, E. |
|
2016 |
|
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 |
|
P2 |
p. 621-629 9 p. |
artikel |
4 |
ADS-IRWST transient evaluation model for AP1000 SBLOCA analysis
|
Wang, Han |
|
2017 |
|
P2 |
p. 169-177 |
artikel |
5 |
A hybrid non-dominated sorting genetic algorithm and its application on multi-objective optimal design of nuclear power plant
|
Chen, Lei |
|
2017 |
|
P2 |
p. 150-159 |
artikel |
6 |
A multi-physics reduced order model for the analysis of Lead Fast Reactor single channel
|
Sartori, Alberto |
|
2016 |
|
P2 |
p. 198-208 11 p. |
artikel |
7 |
A new methodology for diagnosis system with ‘Don’t Know’ response for Nuclear Power Plant
|
dos Santos Nicolau, Andressa |
|
2017 |
|
P2 |
p. 91-97 |
artikel |
8 |
A new SP n theory formulation with self-consistent physical assumptions on angular flux
|
Chao, Yung-An |
|
2016 |
|
P2 |
p. 137-144 8 p. |
artikel |
9 |
An integrated approach to sensor FDI and signal reconstruction in HTGRs – Part II: Case studies
|
Uren, Kenneth R. |
|
2016 |
|
P2 |
p. 739-749 11 p. |
artikel |
10 |
An integrated approach to sensor FDI and signal reconstruction in HTGRs – Part I: Theoretical framework
|
Uren, Kenneth R. |
|
2016 |
|
P2 |
p. 750-760 11 p. |
artikel |
11 |
Application of Extreme Learning Machines to inverse neutron kinetics
|
Picca, Paolo |
|
2017 |
|
P2 |
p. 1-8 |
artikel |
12 |
Assembly-level analysis of heterogeneous Th–Pu PWR fuel
|
Zainuddin, Nurjuanis Zara |
|
2017 |
|
P2 |
p. 160-168 |
artikel |
13 |
Assessment of assembly homogenized two-steps core dynamic calculations using direct whole core transport solutions
|
Hursin, Mathieu |
|
2016 |
|
P2 |
p. 356-365 10 p. |
artikel |
14 |
A tightly coupled scheme for neutronics and thermal–hydraulics using open-source software
|
Wu, Hsingtzu |
|
2016 |
|
P2 |
p. 16-22 7 p. |
artikel |
15 |
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 |
|
P2 |
p. 659-670 12 p. |
artikel |
16 |
Burning of the Minor Actinides in fuel cycle of the MTR-reactors
|
Shaaban, Ismail |
|
2017 |
|
P2 |
p. 119-127 |
artikel |
17 |
CAD-based Monte Carlo automatic modeling method based on primitive solid
|
Wang, Dong |
|
2016 |
|
P2 |
p. 162-166 5 p. |
artikel |
18 |
Characterization of velocity and temperature fields in a 217 pin wire wrapped fuel bundle of sodium cooled fast reactor
|
Naveen Raj, M. |
|
2016 |
|
P2 |
p. 331-349 19 p. |
artikel |
19 |
Code improvement and model validation for Ascó-II Nuclear Power Plant model using a coupled 3D neutron kinetics/thermal–hydraulic code
|
Pericas, R. |
|
2016 |
|
P2 |
p. 366-374 9 p. |
artikel |
20 |
Comparison of critical flow models for SBLOCA tests of the ATLAS facility
|
Kim, Yeon-Sik |
|
2016 |
|
P2 |
p. 435-442 8 p. |
artikel |
21 |
Computational fluid dynamics study on cross flow pressure drop for triangular array rod assemblies with wire
|
Pramuditya, Syeilendra |
|
2016 |
|
P2 |
p. 803-816 14 p. |
artikel |
22 |
Computing eigenvalue sensitivity coefficients to nuclear data by adjoint superhistory method and adjoint Wielandt method implemented in RMC code
|
Qiu, Yishu |
|
2016 |
|
P2 |
p. 228-241 14 p. |
artikel |
23 |
Control parameter optimization for AP1000 reactor using Particle Swarm Optimization
|
Wang, Pengfei |
|
2016 |
|
P2 |
p. 687-695 9 p. |
artikel |
24 |
Control rod drop transient analysis with the coupled parallel code pCTF-PARCSv2.7
|
Ramos, Enrique |
|
2016 |
|
P2 |
p. 308-317 10 p. |
artikel |
25 |
COPRA experiments on natural convection heat transfer in a volumetrically heated slice pool with high Rayleigh numbers
|
Zhang, Luteng |
|
2016 |
|
P2 |
p. 81-88 8 p. |
artikel |
26 |
Coupled neutronics–fuel behavior calculations in steady state using the Serpent 2 Monte Carlo code
|
Valtavirta, Ville |
|
2017 |
|
P2 |
p. 50-64 |
artikel |
27 |
Criticality validation of SuperMC with ICSBEP
|
Zhang, Binhang |
|
2016 |
|
P2 |
p. 494-499 6 p. |
artikel |
28 |
CRUD, boron, and burnable absorber layer 2-D modeling requirements using MOC neutron transport
|
Walter, Daniel J. |
|
2016 |
|
P2 |
p. 388-399 12 p. |
artikel |
29 |
3D/2D rotational plane slicing method for 3D whole-core transport calculation
|
Yoo, Han Jong |
|
2016 |
|
P2 |
p. 30-38 9 p. |
artikel |
30 |
Depletion benchmarks calculation of random media using explicit modeling approach of RMC
|
Liu, Shichang |
|
2016 |
|
P2 |
p. 167-175 9 p. |
artikel |
31 |
Design and neutronic investigation of the Nano fluids application to VVER-1000 nuclear reactor with dual cooled annular fuel
|
Ansarifar, G.R. |
|
2016 |
|
P2 |
p. 39-47 9 p. |
artikel |
32 |
Design concept for a small pebble bed reactor with ROX fuel
|
Ho, Hai Quan |
|
2016 |
|
P2 |
p. 471-478 8 p. |
artikel |
33 |
Determination of the maximum speed of WWER-1000 nuclear reactor control rods
|
Khoshahval, Farrokh |
|
2016 |
|
P2 |
p. 58-68 11 p. |
artikel |
34 |
Development of a portable heavy-water leak sensor based on laser absorption spectroscopy
|
Lee, Lim |
|
2016 |
|
P2 |
p. 350-355 6 p. |
artikel |
35 |
Development of a PWR-W GOTHIC 3D model for containment accident analysis
|
Bocanegra, Rafael |
|
2016 |
|
P2 |
p. 547-560 14 p. |
artikel |
36 |
Development strategy and conceptual design of China Lead-based Research Reactor
|
Wu, Yican |
|
2016 |
|
P2 |
p. 511-516 6 p. |
artikel |
37 |
Directional diffusion coefficients and leakage-corrected discontinuity factors: Implementation in Serpent and tests
|
Dorval, E. |
|
2016 |
|
P2 |
p. 101-112 12 p. |
artikel |
38 |
Editorial board
|
|
|
2016 |
|
P2 |
p. IFC- 1 p. |
artikel |
39 |
Editorial board
|
|
|
2017 |
|
P2 |
p. IFC |
artikel |
40 |
Effect of transverse power distribution on the ONB location in the subcooled boiling flow
|
Al-Yahia, Omar S. |
|
2017 |
|
P2 |
p. 98-106 |
artikel |
41 |
Establishment of the hazard reduction methodology to be taken into account for safety assessment during decommissioning of nuclear facilities
|
Jeong, KwanSeong |
|
2016 |
|
P2 |
p. 7-15 9 p. |
artikel |
42 |
Evaluating the effect of cross-over length and mutation rate variations on the performance of DERMAGA
|
Kastanya, Doddy |
|
2017 |
|
P2 |
p. 32-41 |
artikel |
43 |
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 |
|
P2 |
p. 324-330 7 p. |
artikel |
44 |
Evaluation of burnable absorber rods effect on neutronic performance in fuel assembly of WWER-1000 reactor
|
Khoshahval, Farrokh |
|
2016 |
|
P2 |
p. 648-658 11 p. |
artikel |
45 |
Experimental investigation of the thermal hydraulics of supercritical water under natural circulation in a closed loop
|
Kiss, Attila |
|
2017 |
|
P2 |
p. 178-203 |
artikel |
46 |
Experimental study on fundamental phenomena in HTGR small break air-ingress accident
|
Kim, Jae Soon |
|
2016 |
|
P2 |
p. 145-156 12 p. |
artikel |
47 |
Features of MCNP6
|
Goorley, T. |
|
2016 |
|
P2 |
p. 772-783 12 p. |
artikel |
48 |
Flow and heat transfer in laminar–turbulent transitional flow regime under rolling motion
|
Yuan, Hongsheng |
|
2016 |
|
P2 |
p. 527-536 10 p. |
artikel |
49 |
Heat transfer of water flowing upward in vertical annuli with spacers at high pressure conditions
|
Zhao, M. |
|
2016 |
|
P2 |
p. 209-216 8 p. |
artikel |
50 |
High Conversion Th–U233 fuel for current generation of PWRs: Part III – Fuel availability and utilization considerations
|
Baldova, D. |
|
2016 |
|
P2 |
p. 517-526 10 p. |
artikel |
51 |
Human error and the associated recovery probabilities for soft control being used in the advanced MCRs of NPPs
|
Jang, Inseok |
|
2016 |
|
P2 |
p. 290-298 9 p. |
artikel |
52 |
Identification and categorisation of safety issues for ESNII reactor concepts. Part I: Common phenomena related to materials
|
Tuček, K. |
|
2016 |
|
P2 |
p. 411-425 15 p. |
artikel |
53 |
Impact of Ag and NOx compounds on the transport of ruthenium in the primary circuit of nuclear power plant in a severe accident
|
Kajan, Ivan |
|
2017 |
|
P2 |
p. 9-19 |
artikel |
54 |
Impact of power density profile on passive decay heat removal in prismatic HTGR
|
Sambuu, Odmaa |
|
2016 |
|
P2 |
p. 23-29 7 p. |
artikel |
55 |
Impact of proof test interval and coverage on probability of failure of safety instrumented function
|
Jin, Jianghong |
|
2016 |
|
P2 |
p. 537-540 4 p. |
artikel |
56 |
Implementation of condition-dependent probabilistic risk assessment using surveillance data on passive components
|
Lewandowski, Radoslaw |
|
2016 |
|
P2 |
p. 696-706 11 p. |
artikel |
57 |
Improvement and evaluation of debris coolability analysis module in severe accident analysis code SAMPSON using LIVE experiment
|
Wei, Hongyang |
|
2017 |
|
P2 |
p. 65-72 |
artikel |
58 |
Improvements to the Transmutation Trajectory Analysis of depletion evaluation
|
Huang, Kai |
|
2016 |
|
P2 |
p. 637-647 11 p. |
artikel |
59 |
In-phase instabilities in BWR with sub-cooled boiling, direct heating, and spacers effects
|
Muñoz-Cobo, José L. |
|
2016 |
|
P2 |
p. 671-686 16 p. |
artikel |
60 |
Introducing time in derivation of the scaling factor for MCNP criticality calculations
|
Yang, Yang |
|
2016 |
|
P2 |
p. 385-387 3 p. |
artikel |
61 |
Investigations of single-phase flow mixing characteristics in a wire-wrapped 37-pin bundle for a sodium-cooled fast reactor
|
Kim, Hyungmo |
|
2016 |
|
P2 |
p. 541-546 6 p. |
artikel |
62 |
Measurement of 75As(n,2n) cross section in well-defined spectrum of LR-0 special core
|
Košťál, Michal |
|
2017 |
|
P2 |
p. 42-49 |
artikel |
63 |
Measurement of sub-critical reactivity in a heavy water reactor by neutron noise methods using a time stamping data acquisition system
|
Kumar, Rajeev |
|
2016 |
|
P2 |
p. 720-727 8 p. |
artikel |
64 |
Micro-Pocket Fission Detectors (MPFDs) for in-core neutron detection
|
Reichenberger, Michael A. |
|
2016 |
|
P2 |
p. 318-323 6 p. |
artikel |
65 |
Modeling the thermal stress of heat transfer tubes with tube support plate gaps in a steam generator
|
Sun, Baozhi |
|
2016 |
|
P2 |
p. 400-410 11 p. |
artikel |
66 |
Monte Carlo modeling of the Pakistan Research Reactor-1 (PARR-1)
|
Ali, M. Rizwan |
|
2016 |
|
P2 |
p. 584-590 7 p. |
artikel |
67 |
Nanoscopic designs of radiological protection in environmental scale for the Fukushima nuclear accident: Strategy by dispersion, dissolution, and filtration
|
Woo, Tae Ho |
|
2016 |
|
P2 |
p. 569-574 6 p. |
artikel |
68 |
New derivation of Blackshow–Murrays formula for the Doppler-broadened scattering kernel and calculation of the angular moments via Lagrange interpolation
|
Sanchez, Richard |
|
2016 |
|
P2 |
p. 113-125 13 p. |
artikel |
69 |
Nodal collocation method for the multidimensional P L equations applied to neutron transport source problems
|
Capilla, M.T. |
|
2016 |
|
P2 |
p. 89-100 12 p. |
artikel |
70 |
Nuclear-data uncertainty propagations in burnup calculation for the PWR assembly
|
Wan, Chenghui |
|
2017 |
|
P2 |
p. 20-31 |
artikel |
71 |
Numerical analysis of the dust distribution during LOVA
|
Tong, L.L. |
|
2016 |
|
P2 |
p. 454-461 8 p. |
artikel |
72 |
Numerical implementation, verification and validation of two-phase flow four-equation drift flux model with Jacobian-free Newton–Krylov method
|
Zou, Ling |
|
2016 |
|
P2 |
p. 707-719 13 p. |
artikel |
73 |
Numerical simulation and experimental verification of microstructure evolution in large forged pipe used for AP1000 nuclear power plants
|
Wang, Shenglong |
|
2016 |
|
P2 |
p. 176-185 10 p. |
artikel |
74 |
On the calculation of angular neutron flux in MCNP
|
Beričič, Jure |
|
2017 |
|
P2 |
p. 128-149 |
artikel |
75 |
Passive Non-Destructive Assay based on gamma-ray spectrometry to verify UO2 samples in the form of powder and pellet
|
Tohamy, M. |
|
2016 |
|
P2 |
p. 186-191 6 p. |
artikel |
76 |
Performance-based ECCS cladding acceptance criteria: A new simulation approach
|
Zoino, A. |
|
2017 |
|
P2 |
p. 204-216 |
artikel |
77 |
Performance of iodide vapour absorption in the venturi scrubber working in self-priming mode
|
Zhou, Yanmin |
|
2016 |
|
P2 |
p. 426-434 9 p. |
artikel |
78 |
Pressure wave propagation phenomena in the pipe system of a nuclear power plant
|
Yi, Sung-Jae |
|
2016 |
|
P2 |
p. 157-161 5 p. |
artikel |
79 |
PSA model with consideration of the effect of fault-tolerant techniques in digital I&C systems
|
Lee, Seung Jun |
|
2016 |
|
P2 |
p. 375-384 10 p. |
artikel |
80 |
Quantifying the effects of depletion parameters on the PWR spent fuel reactivity based on nuclide sensitivity coefficients
|
Sheu, Rong-Jiun |
|
2016 |
|
P2 |
p. 126-136 11 p. |
artikel |
81 |
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 |
|
P2 |
p. 267-281 15 p. |
artikel |
82 |
Review calculations for the OECD/NEA Burn-up Credit Criticality Safety Benchmark
|
Herrero, José J. |
|
2016 |
|
P2 |
p. 48-57 10 p. |
artikel |
83 |
Review study of virtual reality techniques used at nuclear issues with emphasis on Brazilian research
|
da Silva, Márcio Henrique |
|
2016 |
|
P2 |
p. 192-197 6 p. |
artikel |
84 |
Risk assessment on abnormal accidents from human errors during decommissioning of nuclear facilities
|
Jeong, KwanSeong |
|
2016 |
|
P2 |
p. 1-6 6 p. |
artikel |
85 |
Safety analysis of MTR type research reactor during postulated beam tube break inducing positive reactivity
|
Khakim, Azizul |
|
2016 |
|
P2 |
p. 793-798 6 p. |
artikel |
86 |
Simulation of the airborne radioactive substance distribution and monitoring of coolant leakage in a typical Nuclear Reactor Containment
|
Zheng, Ya |
|
2016 |
|
P2 |
p. 462-470 9 p. |
artikel |
87 |
Small break LOCA analysis without emergency core cooling systems using the RELAP5/SCDAP code in VVER-1000 reactor
|
Salehi, Mohsen |
|
2016 |
|
P2 |
p. 299-307 9 p. |
artikel |
88 |
Sodium flow measurement in large pipelines of sodium cooled fast breeder reactors with bypass type flow meters
|
Rajan, K.K. |
|
2016 |
|
P2 |
p. 74-80 7 p. |
artikel |
89 |
Solving the multigroup integro-differential equation of the neutron diffusion kinetics in 3D-Cartesian geometry
|
Quintero-Leyva, Barbaro |
|
2016 |
|
P2 |
p. 282-289 8 p. |
artikel |
90 |
Stability analysis of the Backward Euler time discretization for the pin-resolved transport transient reactor calculation
|
Zhu, Ang |
|
2016 |
|
P2 |
p. 252-266 15 p. |
artikel |
91 |
Static and transient analysis of a medium-sized sodium cooled fast reactor loaded with oxide, nitride, carbide and metallic fuels
|
Zhang, Youpeng |
|
2016 |
|
P2 |
p. 761-771 11 p. |
artikel |
92 |
Study of graphite reactivity worth on well-defined cores assembled on LR-0 reactor
|
Košťál, Michal |
|
2016 |
|
P2 |
p. 601-611 11 p. |
artikel |
93 |
System scaling analysis for modeling small break LOCA using the FULL SPECTRUM LOCA evaluation model
|
Liao, Jun |
|
2016 |
|
P2 |
p. 443-453 11 p. |
artikel |
94 |
The application of transient analysis code to estimation of total released energy in a two-fuel-solution-tank system
|
Kikuchi, Haruka |
|
2016 |
|
P2 |
p. 486-493 8 p. |
artikel |
95 |
The neutron point kinetics equation: Suppression of fractional derivative effects by temperature feedback
|
Schramm, M. |
|
2016 |
|
P2 |
p. 479-485 7 p. |
artikel |
96 |
Theoretical basis of quantification for layer of protection analysis (LOPA)
|
Jin, Jianghong |
|
2016 |
|
P2 |
p. 69-73 5 p. |
artikel |
97 |
Thermal conductivity of perspective fuel based on uranium nitride
|
Solntceva, E.S. |
|
2016 |
|
P2 |
p. 799-802 4 p. |
artikel |
98 |
Thermal–hydraulic modeling and transient analysis of helium-cooled tungsten target coupled with ADS core
|
Peng, Tianji |
|
2016 |
|
P2 |
p. 612-620 9 p. |
artikel |
99 |
Thermal neutron scattering cross sections of beryllium and magnesium oxides
|
Al-Qasir, Iyad |
|
2016 |
|
P2 |
p. 242-251 10 p. |
artikel |
100 |
Thermal stability investigation technique for uranium nitride
|
Baranov, V.G. |
|
2016 |
|
P2 |
p. 784-792 9 p. |
artikel |
101 |
Three higher order analytical nodal methods for multigroup neutron diffusion equations
|
Guessous, Najib |
|
2016 |
|
P2 |
p. 561-568 8 p. |
artikel |
102 |
Transient analyses of the Jordanian 5MW research reactor under LOEP accident
|
Al-Yahia, Omar S. |
|
2016 |
|
P2 |
p. 575-583 9 p. |
artikel |
103 |
Transient identification by clustering based on Integrated Deterministic and Probabilistic Safety Analysis outcomes
|
Di Maio, Francesco |
|
2016 |
|
P2 |
p. 217-227 11 p. |
artikel |
104 |
Ultimate analysis of PWR prestressed concrete containment under long-term prestressing loss
|
Hu, Hsuan-Teh |
|
2016 |
|
P2 |
p. 500-510 11 p. |
artikel |
105 |
Use of discontinuity factors in high-order finite element methods
|
Vidal-Ferràndiz, A. |
|
2016 |
|
P2 |
p. 728-738 11 p. |
artikel |
106 |
Using Evidence Credibility Decay Model for dependence assessment in human reliability analysis
|
Guo, Xingfeng |
|
2017 |
|
P2 |
p. 107-118 |
artikel |
107 |
Verification of the accuracy of the higher order of neutron anisotropic scattering in the AGENT neutronics code system
|
Kim, Donghoon |
|
2017 |
|
P2 |
p. 73-90 |
artikel |