| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Analysis of operator support method based on intelligent dynamic interlock in lead-cooled fast reactor simulator
|
Xu, Peng
|
|
2017
|
99 |
C |
p. 279-282
4 p.
|
artikel
|
| 2 |
Analysis on vibration response of U-tube bundles caused by two-phase cross-flow turbulence
|
Jiang, Nai-bin
|
|
2017
|
99 |
C |
p. 328-334
7 p.
|
artikel
|
| 3 |
Analytical solution of the fractional point kinetics equations with multi-group of delayed neutrons during start-up of a nuclear reactor
|
Nahla, Abdallah A.
|
|
2017
|
99 |
C |
p. 247-252
6 p.
|
artikel
|
| 4 |
Application of the BEPU methodology to assess fuel performance in dry storage
|
Feria, F.
|
|
2017
|
99 |
C |
p. 240-246
7 p.
|
artikel
|
| 5 |
Assessment of two-phase interchannel mixing models for BWR and PWR conditions
|
Pang, Bo
|
|
2017
|
99 |
C |
p. 283-291
9 p.
|
artikel
|
| 6 |
A study for an appropriate risk management of new technology deployment in Nuclear Power Plants
|
Jung, Kil-Young
|
|
2017
|
99 |
C |
p. 157-164
8 p.
|
artikel
|
| 7 |
A study of the performance of a sparse grid cross section representation methodology as applied to MOX fuel
|
Botes, Danniëll
|
|
2017
|
99 |
C |
p. 444-454
11 p.
|
artikel
|
| 8 |
CFD analysis of flow field in a 5×5 rod bundle with multi-grid
|
Cheng, Songbai
|
|
2017
|
99 |
C |
p. 464-470
7 p.
|
artikel
|
| 9 |
Comparative economic analysis of the Integral Molten Salt Reactor and an advanced PWR using the G4-ECONS methodology
|
Samalova, Ludmila
|
|
2017
|
99 |
C |
p. 258-265
8 p.
|
artikel
|
| 10 |
Comparative study on aerosol removal by natural processes in containment in severe accident for AP1000 reactor
|
Sun, Xiaohui
|
|
2017
|
99 |
C |
p. 216-226
11 p.
|
artikel
|
| 11 |
Cyber security in nuclear industry – Analytic study from the terror incident in nuclear power plants (NPPs)
|
Cho, Hyo Sung
|
|
2017
|
99 |
C |
p. 47-53
7 p.
|
artikel
|
| 12 |
Development and characterization of a fiber-optic monitoring system for the key environment variables of the spent nuclear fuel pool at a nuclear power plant
|
Kim, Rinah
|
|
2017
|
99 |
C |
p. 183-192
10 p.
|
artikel
|
| 13 |
Development and verification of LOOP: A Linkage of ORIGEN2.2 and OpenMC
|
Gul, Anas
|
|
2017
|
99 |
C |
p. 321-327
7 p.
|
artikel
|
| 14 |
Development and verification of MOC code based on Krylov subspace and efficient preconditioning techniques
|
Zheng, Yong
|
|
2017
|
99 |
C |
p. 427-433
7 p.
|
artikel
|
| 15 |
Development of a set of benchmark problems to verify numerical methods for solving burnup equations
|
Lago, Daniel
|
|
2017
|
99 |
C |
p. 266-271
6 p.
|
artikel
|
| 16 |
Editorial board
|
|
|
2017
|
99 |
C |
p. IFC-
1 p.
|
artikel
|
| 17 |
Effect of 3-D moderator flow configurations on the reactivity of CANDU nuclear reactors
|
Zadeh, Foad Mehdi
|
|
2017
|
99 |
C |
p. 136-150
15 p.
|
artikel
|
| 18 |
Effects of heavy weight waste glass recycled as fine aggregate on the mechanical properties of mortar specimens
|
Choi, So Yeong
|
|
2017
|
99 |
C |
p. 372-382
11 p.
|
artikel
|
| 19 |
Extension of double heterogeneity treatment method for coated TRISO fuel particles
|
Kim, Hanjoo
|
|
2017
|
99 |
C |
p. 124-135
12 p.
|
artikel
|
| 20 |
Feasibility of ANFIS towards multiclass event classification in PFBR considering dimensionality reduction using PCA
|
Prusty, Manas Ranjan
|
|
2017
|
99 |
C |
p. 311-320
10 p.
|
artikel
|
| 21 |
Fluctuations of the fission energy generated in a multiplying system
|
Pál, L.
|
|
2017
|
99 |
C |
p. 116-123
8 p.
|
artikel
|
| 22 |
HPC implementation in the time-dependent neutron diffusion code AZKIND
|
Rodríguez Hernández, Andrés
|
|
2017
|
99 |
C |
p. 174-182
9 p.
|
artikel
|
| 23 |
Improvement of TASS/SMR code using a simple correlation for subcooled boiling flow prediction
|
Chung, Young Jong
|
|
2017
|
99 |
C |
p. 421-426
6 p.
|
artikel
|
| 24 |
Improvements in the prediction of heat transfer to supercritical pressure fluids by the use of algebraic heat flux models
|
Pucciarelli, A.
|
|
2017
|
99 |
C |
p. 58-67
10 p.
|
artikel
|
| 25 |
Incorporating delayed neutrons into the point-model equations routinely used for neutron coincidence counting in nuclear safeguards
|
Croft, S.
|
|
2017
|
99 |
C |
p. 36-39
4 p.
|
artikel
|
| 26 |
Investigation of the recriticality potential during reflooding phase of Fukushima Daiichi Unit-3 accident
|
Darnowski, Piotr
|
|
2017
|
99 |
C |
p. 495-509
15 p.
|
artikel
|
| 27 |
Lattice Boltzmann method for solving non-equilibrium radiative transport problems
|
Gairola, Abhinav
|
|
2017
|
99 |
C |
p. 151-156
6 p.
|
artikel
|
| 28 |
Minor actinide incineration and Th-U breeding in a small FLiNaK Molten Salt Fast Reactor
|
Yu, Chenggang
|
|
2017
|
99 |
C |
p. 335-344
10 p.
|
artikel
|
| 29 |
New techniques for designing the initial and reload cores with constant long cycle lengths
|
Shi, Jun
|
|
2017
|
99 |
C |
p. 165-173
9 p.
|
artikel
|
| 30 |
Numerical analysis for multi-group neutron-diffusion equation using Radial Point Interpolation Method (RPIM)
|
Kim, Kyung-O
|
|
2017
|
99 |
C |
p. 193-198
6 p.
|
artikel
|
| 31 |
Numerical simulation of the telescope sipping of a leaking VVER fuel assembly
|
Szabó, Péter
|
|
2017
|
99 |
C |
p. 345-352
8 p.
|
artikel
|
| 32 |
Numerical study on flow pattern of sonic steam jet condensed into subcooled water
|
Zhou, Lun
|
|
2017
|
99 |
C |
p. 206-215
10 p.
|
artikel
|
| 33 |
On an analytical formulation for the mono-energetic neutron space-kinetic equation in full cylinder symmetry
|
Oliveira, F.R.
|
|
2017
|
99 |
C |
p. 253-257
5 p.
|
artikel
|
| 34 |
One-group analytical solution to two-region reactor kinetic model
|
Holschuh, Thomas V.
|
|
2017
|
99 |
C |
p. 199-205
7 p.
|
artikel
|
| 35 |
On the equivalence of neutron source and flux spectra
|
Žerovnik, Gašper
|
|
2017
|
99 |
C |
p. 54-57
4 p.
|
artikel
|
| 36 |
Physical model of the nuclear fuel cycle simulation code SITON
|
Brolly, Á.
|
|
2017
|
99 |
C |
p. 471-483
13 p.
|
artikel
|
| 37 |
Pneumatic transportation pattern of fuel pebbles in a pebble-bed reactor
|
Liu, Hongbing
|
|
2017
|
99 |
C |
p. 434-443
10 p.
|
artikel
|
| 38 |
Proposed re-evaluation of the 154Eu thermal n , γ capture cross-section based on spent fuel benchmarking studies
|
Skutnik, Steven E.
|
|
2017
|
99 |
C |
p. 80-107
28 p.
|
artikel
|
| 39 |
Radiation source reconstruction based on a covariance matrix adaptation evolution strategy and the adjoint flux and forward source inner product evaluation method
|
Dion, M.
|
|
2017
|
99 |
C |
p. 292-300
9 p.
|
artikel
|
| 40 |
Radiological dose assessment for the hypothetical severe accident of the Tehran Research Reactor and corresponding emergency response
|
Ahangari, Rohollah
|
|
2017
|
99 |
C |
p. 272-278
7 p.
|
artikel
|
| 41 |
Radiotoxicity implications and reduction strategies of minor actinide in a boiling water reactor
|
Alonso, Gustavo
|
|
2017
|
99 |
C |
p. 410-420
11 p.
|
artikel
|
| 42 |
Reactivity costs in MARIA reactor
|
Marcinkowska, Zuzanna E.
|
|
2017
|
99 |
C |
p. 366-371
6 p.
|
artikel
|
| 43 |
Reflux condensation behavior in SBLOCA tests of ATLAS facility
|
Kim, Yeon-Sik
|
|
2017
|
99 |
C |
p. 227-239
13 p.
|
artikel
|
| 44 |
Simulation of a sodium fast core: Effect of B 1 leakage models on group constant generation
|
Faure, B.
|
|
2017
|
99 |
C |
p. 484-494
11 p.
|
artikel
|
| 45 |
Simulation of the in-vessel retention device heat-removal capability of AP-1000 during a core meltdown accident
|
Tsai, Fei-Jan
|
|
2017
|
99 |
C |
p. 455-463
9 p.
|
artikel
|
| 46 |
Spectral properties of dynamic processes in a nuclear reactor
|
Avvakumov, Alexander V.
|
|
2017
|
99 |
C |
p. 68-79
12 p.
|
artikel
|
| 47 |
Study on the extension of A N and SP N methods to the analysis of heterogeneous media
|
Coppa, Gianni
|
|
2017
|
99 |
C |
p. 108-115
8 p.
|
artikel
|
| 48 |
Sustainable and safe energy supply with seawater uranium fueled HTGR and its economy
|
Fukaya, Y.
|
|
2017
|
99 |
C |
p. 19-27
9 p.
|
artikel
|
| 49 |
Tailoring the response of Autonomous Reactivity Control (ARC) systems
|
Qvist, Staffan A.
|
|
2017
|
99 |
C |
p. 383-398
16 p.
|
artikel
|
| 50 |
The code development and thermo-hydrodynamic analysis of the reflood during severe accident in PWR
|
Niu, S.P.
|
|
2017
|
99 |
C |
p. 9-18
10 p.
|
artikel
|
| 51 |
The effect of nodalization and temperature of reactor upper region: Sensitivity analysis for APR-1400 LBLOCA
|
Kang, Dong Gu
|
|
2017
|
99 |
C |
p. 28-35
8 p.
|
artikel
|
| 52 |
The experimental determination of the 238U(n,γ) and total fission reaction rates along the pellet radius of the IPEN/MB-01 reactor
|
Mura, Luís Felipe Liambos
|
|
2017
|
99 |
C |
p. 399-409
11 p.
|
artikel
|
| 53 |
The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors
|
Brown, Nicholas R.
|
|
2017
|
99 |
C |
p. 353-365
13 p.
|
artikel
|
| 54 |
The research on AP1000 nuclear main pumps’ complete characteristics and the normalization method
|
Zhu, Rongsheng
|
|
2017
|
99 |
C |
p. 1-8
8 p.
|
artikel
|
| 55 |
Thermal analysis of CASTOR RBMK-1500 casks during long-term storage of spent nuclear fuel
|
Poškas, R.
|
|
2017
|
99 |
C |
p. 40-46
7 p.
|
artikel
|
| 56 |
Total sensitivity and uncertainty analysis for LWR pin-cells with improved UNICORN code
|
Wan, Chenghui
|
|
2017
|
99 |
C |
p. 301-310
10 p.
|
artikel
|
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