| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Activation cross section for the 125Te(p,xn) reactions in 5.5–100.5MeV energy range
|
Karpuz, Nurdan
|
|
2013
|
60 |
C |
p. 341-343
3 p.
|
artikel
|
| 2 |
Advanced progressive real coded genetic algorithm for nuclear system availability optimization through preventive maintenance scheduling
|
Aghaie, M.
|
|
2013
|
60 |
C |
p. 64-72
9 p.
|
artikel
|
| 3 |
Analyses of liquid entrainment through ADS-4 in AP1000 during a typical small break LOCA transient
|
Wang, W.W.
|
|
2013
|
60 |
C |
p. 195-201
7 p.
|
artikel
|
| 4 |
Analyses of the MYRRHA spallation loop using the system code ATHLET
|
Palazzo, Simone
|
|
2013
|
60 |
C |
p. 274-286
13 p.
|
artikel
|
| 5 |
Analysis of flow stability in nuclear reactor subchannels with water at supercritical pressures
|
Ampomah-Amoako, Emmanuel
|
|
2013
|
60 |
C |
p. 396-405
10 p.
|
artikel
|
| 6 |
Analysis of hydrogen control in severe accidents of CANDU6
|
Huang, Gaofeng
|
|
2013
|
60 |
C |
p. 301-307
7 p.
|
artikel
|
| 7 |
Analysis of kinetic parameters of 3MW TRIGA Mark-II research reactor using the SRAC2006 code system
|
Khan, M.J.H.
|
|
2013
|
60 |
C |
p. 181-186
6 p.
|
artikel
|
| 8 |
Analysis of the experimental neutron noise from the PHENIX reactor
|
Zylbersztejn, F.
|
|
2013
|
60 |
C |
p. 106-114
9 p.
|
artikel
|
| 9 |
A preliminary simulation study of dynamic rod worth for the SMART (System-integrated Modular Advanced ReacTor) reactor
|
Hong, Ser Gi
|
|
2013
|
60 |
C |
p. 350-356
7 p.
|
artikel
|
| 10 |
A random walk based methodology for the realistic estimation of radioactivity migration in a porous medium
|
Sen, Soubhadra
|
|
2013
|
60 |
C |
p. 202-205
4 p.
|
artikel
|
| 11 |
Assessment of the neutronic performance of some alternative fluids in a fusion–fission hybrid reactor by using Monte Carlo method
|
Günay, Mehtap
|
|
2013
|
60 |
C |
p. 93-97
5 p.
|
artikel
|
| 12 |
Assessment of the RELAP5/MOD3.3 code for condensation in the presence of air using experimental data and theoretical model
|
Ağlar, Fahri
|
|
2013
|
60 |
C |
p. 329-340
12 p.
|
artikel
|
| 13 |
A study using RELAP5 on capability and instability of two-phase natural circulation flow under passive external reactor vessel cooling
|
Guozhi, Zhao
|
|
2013
|
60 |
C |
p. 115-126
12 p.
|
artikel
|
| 14 |
Calculation of reactivity in subcritical reactors using the method of partial derivatives
|
Antolin, M.Q.
|
|
2013
|
60 |
C |
p. 34-38
5 p.
|
artikel
|
| 15 |
Capability of RELAP5 MOD3.3 code to simulate density wave instability in parallel narrow rectangular channels
|
Zhou, Yuan
|
|
2013
|
60 |
C |
p. 256-266
11 p.
|
artikel
|
| 16 |
Comparison of different neutronics analysis technique for Accelerator-Driven System
|
Aizawa, Naoto
|
|
2013
|
60 |
C |
p. 368-373
6 p.
|
artikel
|
| 17 |
Comparison of the once-through and closed nuclear fuel cycles with regard to waste disposal area required in a geological repository
|
Bulut Acar, Banu
|
|
2013
|
60 |
C |
p. 172-180
9 p.
|
artikel
|
| 18 |
Containment behaviour in Phébus FP
|
Laurie, M.
|
|
2013
|
60 |
C |
p. 15-27
13 p.
|
artikel
|
| 19 |
Coolant distribution and mixing at the core inlet of PWR in a real geometry
|
Zhang, G.
|
|
2013
|
60 |
C |
p. 187-194
8 p.
|
artikel
|
| 20 |
Decay heat removal without forced cooling on a small simplified PBR with an accumulative fuel loading scheme
|
Irwanto, Dwi
|
|
2013
|
60 |
C |
p. 383-395
13 p.
|
artikel
|
| 21 |
Depletion analysis of control absorber in a small research reactor
|
Park, Chang Je
|
|
2013
|
60 |
C |
p. 377-382
6 p.
|
artikel
|
| 22 |
Design and analysis of an innovative pressure tube light water reactor with variable moderator control
|
Rachamin, R.
|
|
2013
|
60 |
C |
p. 248-255
8 p.
|
artikel
|
| 23 |
Design for integrated pyroprocessing plant level simulator
|
Lee, Hyo Jik
|
|
2013
|
60 |
C |
p. 316-328
13 p.
|
artikel
|
| 24 |
Design, modeling and reconstruction method research of a 14.1MeV neutron imaging system suitable for low yield Z-Pinch diagnosis
|
Jia, Qinggang
|
|
2013
|
60 |
C |
p. 412-419
8 p.
|
artikel
|
| 25 |
Design of annular fuels for a typical VVER-1000 core: Neutronic investigation, pitch optimization and MDNBR calculation
|
Amin Mozafari, M.
|
|
2013
|
60 |
C |
p. 226-234
9 p.
|
artikel
|
| 26 |
Editorial board
|
|
|
2013
|
60 |
C |
p. IFC-
1 p.
|
artikel
|
| 27 |
Estimation of sub-criticality using extended Kalman filtering technique
|
Bhatt, T.U.
|
|
2013
|
60 |
C |
p. 98-105
8 p.
|
artikel
|
| 28 |
Increasing transcurium production efficiency through directed resonance shielding
|
Hogle, Susan
|
|
2013
|
60 |
C |
p. 267-273
7 p.
|
artikel
|
| 29 |
Large-eddy simulations of structure effects of an upstream elbow main pipe on hot and cold fluids mixing in a vertical tee junction
|
Lu, T.
|
|
2013
|
60 |
C |
p. 420-431
12 p.
|
artikel
|
| 30 |
MCNPX–BUCAL1 code to code verification through burnup analysis
|
El Bakkari, B.
|
|
2013
|
60 |
C |
p. 242-247
6 p.
|
artikel
|
| 31 |
Neutron and gamma-ray deep penetration calculation through biological concrete shield of VVER-1000 reactor by a new technique based on variance reduction
|
Alizadeh, Alia
|
|
2013
|
60 |
C |
p. 86-92
7 p.
|
artikel
|
| 32 |
Neutron characteristics of single-crystal magnesium fluoride
|
Adib, M.
|
|
2013
|
60 |
C |
p. 163-171
9 p.
|
artikel
|
| 33 |
Nuclear reactor core optimization with Parallel Integer Coded Genetic Algorithm
|
Norouzi, A.
|
|
2013
|
60 |
C |
p. 308-315
8 p.
|
artikel
|
| 34 |
Nuclear safety and nuclear security synergy
|
Gandhi, Sonal
|
|
2013
|
60 |
C |
p. 357-361
5 p.
|
artikel
|
| 35 |
Numerical simulation of thermal stratification in an elbow branch pipe of a tee junction with and without leakage
|
Lu, T.
|
|
2013
|
60 |
C |
p. 432-438
7 p.
|
artikel
|
| 36 |
Numerical study of single and two-phase models of water/Al2O3 nanofluid turbulent forced convection flow in VVER-1000 nuclear reactor
|
Hadad, Kamal
|
|
2013
|
60 |
C |
p. 287-294
8 p.
|
artikel
|
| 37 |
On the Sjöstrand method of reactivity measurement
|
Janczyszyn, Jerzy
|
|
2013
|
60 |
C |
p. 374-376
3 p.
|
artikel
|
| 38 |
Photon interaction, energy absorption and neutron removal cross section of concrete including marble
|
El-Khayatt, A.M.
|
|
2013
|
60 |
C |
p. 8-14
7 p.
|
artikel
|
| 39 |
Physics design of 2MW upgraded Apsara research reactor
|
Singh, Tej
|
|
2013
|
60 |
C |
p. 141-156
16 p.
|
artikel
|
| 40 |
Pre-conceptual thermal–hydraulics and neutronics studies on sodium-cooled oxide and carbide cores
|
Ammirabile, Luca
|
|
2013
|
60 |
C |
p. 127-140
14 p.
|
artikel
|
| 41 |
Preventing xenon oscillations in Monte Carlo burnup calculations by enforcing equilibrium xenon distribution
|
Isotalo, A.E.
|
|
2013
|
60 |
C |
p. 78-85
8 p.
|
artikel
|
| 42 |
Reactivities of neutronic and aneutronic fusion fuels
|
Nayak, Bishnupriya
|
|
2013
|
60 |
C |
p. 73-77
5 p.
|
artikel
|
| 43 |
Review of the natC(n,γ) cross section and criticality calculations of the graphite moderated reactor BR1
|
Díez, C.J.
|
|
2013
|
60 |
C |
p. 210-217
8 p.
|
artikel
|
| 44 |
Stability of single-phase natural-circulation flows in steam generator U tubes
|
Watanabe, Tadashi
|
|
2013
|
60 |
C |
p. 344-349
6 p.
|
artikel
|
| 45 |
Statistical testing of temperature fluctuations for estimating thermal power in central subassembly of fast reactor
|
Sharma, Paawan
|
|
2013
|
60 |
C |
p. 406-411
6 p.
|
artikel
|
| 46 |
Subgroup decomposition method in diffusion theory
|
Yasseri, Saam
|
|
2013
|
60 |
C |
p. 235-241
7 p.
|
artikel
|
| 47 |
Temperature fluctuations inside the CANDU reactor Moderator Test Facility (MTF)
|
Sarchami, Araz
|
|
2013
|
60 |
C |
p. 157-162
6 p.
|
artikel
|
| 48 |
The criticality of VVER-1000 mock-up with different H3BO3 concentration
|
Košťál, Michal
|
|
2013
|
60 |
C |
p. 1-7
7 p.
|
artikel
|
| 49 |
The line source problem in anisotropic neutron transport with internal reflection
|
Liemert, André
|
|
2013
|
60 |
C |
p. 206-209
4 p.
|
artikel
|
| 50 |
Thermal–hydraulic performance analysis of IPWR during full pressure start-up mode
|
Zhao, L.
|
|
2013
|
60 |
C |
p. 28-33
6 p.
|
artikel
|
| 51 |
The stochastic implicit Euler method – A stable coupling scheme for Monte Carlo burnup calculations
|
Dufek, Jan
|
|
2013
|
60 |
C |
p. 295-300
6 p.
|
artikel
|
| 52 |
Usability of epoxy/ilmenite composite material as an attenuator for radiation and a restoration mortar for cracks
|
El-Sarraf, M.A.
|
|
2013
|
60 |
C |
p. 362-367
6 p.
|
artikel
|
| 53 |
Use of sensitivity and uncertainty analysis in reactor design verification Part II: Flux measurement analysis
|
Kastanya, Doddy
|
|
2013
|
60 |
C |
p. 448-458
11 p.
|
artikel
|
| 54 |
Use of sensitivity and uncertainty analysis in reactor design verification. Part I: TSUNAMI analysis
|
Dahmani, Mohamed
|
|
2013
|
60 |
C |
p. 439-447
9 p.
|
artikel
|
| 55 |
Validation of neutronic models and calculation systems by means of experimental results in the IPEN/MB-01 reactor
|
dos Santos, Adimir
|
|
2013
|
60 |
C |
p. 51-63
13 p.
|
artikel
|
| 56 |
Validation of simplified methods for fuel depletion calculations in gas-cooled fast reactors
|
Martín-del-Campo, Cecilia
|
|
2013
|
60 |
C |
p. 218-225
8 p.
|
artikel
|
| 57 |
Variational assimilation for xenon dynamical forecasts in neutronic using advanced background error covariance matrix modelling
|
Ponçot, Angélique
|
|
2013
|
60 |
C |
p. 39-50
12 p.
|
artikel
|
Tijdschrift beschrijving