| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Accuracy of a 2-level scheme based on a subgroup method for pressurized water reactor fuel assembly models
|
Canbakan, Axel
|
|
2015
|
81 |
C |
p. 164-173
10 p.
|
artikel
|
| 2 |
Advanced quadratures for three-dimensional discrete ordinate transport simulations: A comparative study
|
Manalo, Kevin
|
|
2015
|
81 |
C |
p. 196-206
11 p.
|
artikel
|
| 3 |
Analysis of the running-in phase of a Passively Safe Thorium Breeder Pebble Bed Reactor
|
Wols, F.J.
|
|
2015
|
81 |
C |
p. 227-239
13 p.
|
artikel
|
| 4 |
A neural network approach for burn-up calculation and its application to the dynamic fuel cycle code CLASS
|
Leniau, Baptiste
|
|
2015
|
81 |
C |
p. 125-133
9 p.
|
artikel
|
| 5 |
An integral experiment on thorium oxide/depleted uranium cylinders with D-T neutrons for 232Th(n, 2n) reaction
|
Feng, S.
|
|
2015
|
81 |
C |
p. 281-286
6 p.
|
artikel
|
| 6 |
A novel optimization method, Effective Discrete Firefly Algorithm, for fuel reload design of nuclear reactors
|
Poursalehi, N.
|
|
2015
|
81 |
C |
p. 263-275
13 p.
|
artikel
|
| 7 |
A pattern recognition approach based on DTW for automatic transient identification in nuclear power plants
|
Galbally, Javier
|
|
2015
|
81 |
C |
p. 287-300
14 p.
|
artikel
|
| 8 |
Characters of neutron noise in full-size molten salt reactor
|
Wang, Jiangmeng
|
|
2015
|
81 |
C |
p. 179-187
9 p.
|
artikel
|
| 9 |
Comparative analysis of compact heat exchangers for application as the intermediate heat exchanger for advanced nuclear reactors
|
Bartel, N.
|
|
2015
|
81 |
C |
p. 143-149
7 p.
|
artikel
|
| 10 |
Comparative assessment of PSI air oxidation model implementation in SCDAPSim3.5, MELCOR 1.8.6 and MELCOR 2.1
|
Fernandez-Moguel, Leticia
|
|
2015
|
81 |
C |
p. 134-142
9 p.
|
artikel
|
| 11 |
Control of Canadian once-through direct cycle supercritical water-cooled reactors
|
Sun, Peiwei
|
|
2015
|
81 |
C |
p. 6-17
12 p.
|
artikel
|
| 12 |
Development and application of a safety analysis code for small Lead cooled Fast Reactor SVBR 75/100
|
Guo, Chao
|
|
2015
|
81 |
C |
p. 62-72
11 p.
|
artikel
|
| 13 |
Development of simple method to incorporate out-of-core cooling effect on thorium conversion in multi-pass fueled reactor and investigation on characteristics of the effect
|
Fukaya, Yuji
|
|
2015
|
81 |
C |
p. 301-305
5 p.
|
artikel
|
| 14 |
3D simulation of eutectic interaction of Pb–Sn system using Moving Particle Semi-implicit (MPS) method
|
Andi Mustari, Asril Pramutadi
|
|
2015
|
81 |
C |
p. 26-33
8 p.
|
artikel
|
| 15 |
Editorial board
|
|
|
2015
|
81 |
C |
p. IFC-
1 p.
|
artikel
|
| 16 |
Effect of inserted fluoride salts on criticality in the LR-0 reactor
|
Losa, Evžen
|
|
2015
|
81 |
C |
p. 18-25
8 p.
|
artikel
|
| 17 |
Electrolysis of carbon dioxide for carbon monoxide production in a tubular solid oxide electrolysis cell
|
Dipu, Arnoldus Lambertus
|
|
2015
|
81 |
C |
p. 257-262
6 p.
|
artikel
|
| 18 |
End effect analysis with various axial burnup distributions in high density spent fuel storage racks
|
Park, Chang Je
|
|
2015
|
81 |
C |
p. 174-178
5 p.
|
artikel
|
| 19 |
EPRI depletion benchmark calculations using PARAGON
|
Kucukboyaci, Vefa N.
|
|
2015
|
81 |
C |
p. 1-5
5 p.
|
artikel
|
| 20 |
Experimental and numerical study of dynamic response of elevated water tank of AP1000 PCCWST considering FSI effect
|
Lu, Daogang
|
|
2015
|
81 |
C |
p. 73-83
11 p.
|
artikel
|
| 21 |
Extension and validation of SIMMER III code for gas cooled fast reactor
|
Chen, X.-N.
|
|
2015
|
81 |
C |
p. 320-331
12 p.
|
artikel
|
| 22 |
Fabrication methods and thermal hydraulics analysis of enhanced thermal conductivity UO2–BeO fuel in light water reactors
|
Zhou, Wenzhong
|
|
2015
|
81 |
C |
p. 240-248
9 p.
|
artikel
|
| 23 |
Heat transfer effectiveness for cooling of Canadian SCWR fuel assembly under the LOCA/LOECC scenario
|
Wu, Pan
|
|
2015
|
81 |
C |
p. 306-319
14 p.
|
artikel
|
| 24 |
Investigation of subcritical multiplication parameters in TRIGA Mark II accelerator driven system
|
Shahbunder, Hesham
|
|
2015
|
81 |
C |
p. 336-341
6 p.
|
artikel
|
| 25 |
Methodology for analyzing risk at nuclear facilities
|
Yoo, Hosik
|
|
2015
|
81 |
C |
p. 213-218
6 p.
|
artikel
|
| 26 |
Minimum critical mass in coupled core systems
|
van Dam, Hugo
|
|
2015
|
81 |
C |
p. 276-280
5 p.
|
artikel
|
| 27 |
Minor actinide transmutation in a board type sodium cooled breed and burn reactor core
|
Zheng, Meiyin
|
|
2015
|
81 |
C |
p. 41-49
9 p.
|
artikel
|
| 28 |
New strategies of sensitivity analysis capabilities in continuous-energy Monte Carlo code RMC
|
Qiu, Yishu
|
|
2015
|
81 |
C |
p. 50-61
12 p.
|
artikel
|
| 29 |
Nondeterministic method to analysis of the aging effects in PWR power plants components
|
Borges, Diogo da Silva
|
|
2015
|
81 |
C |
p. 249-256
8 p.
|
artikel
|
| 30 |
Physical mechanism analysis of burnup actinide composition in light water reactor MOX fuel and its application to uncertainty evaluation
|
Oizumi, Akito
|
|
2015
|
81 |
C |
p. 117-124
8 p.
|
artikel
|
| 31 |
Plant application of ICARE/ASTECv2.0r3 computer code for investigation of in-vessel melt retention in VVER-1000 reactor design
|
Gencheva, R.
|
|
2015
|
81 |
C |
p. 207-212
6 p.
|
artikel
|
| 32 |
Preliminary investigation on the primary heat exchanger lower head rupture accident of forced circulation LBE-cooled fast reactor
|
Gu, Zhixing
|
|
2015
|
81 |
C |
p. 84-90
7 p.
|
artikel
|
| 33 |
PWR control rods position monitoring
|
Eissa, M.
|
|
2015
|
81 |
C |
p. 106-116
11 p.
|
artikel
|
| 34 |
Relationship of the SPN_AN method to the even-parity transport equation
|
Williams, M.M.R.
|
|
2015
|
81 |
C |
p. 342-353
12 p.
|
artikel
|
| 35 |
Removal of uranium from soil using full-sized washing electrokinetic separation equipment
|
Kim, Gye-Nam
|
|
2015
|
81 |
C |
p. 188-195
8 p.
|
artikel
|
| 36 |
Research on the deposition model of particle-like corrosion product in SG tubes of PWR
|
Lu, Daogang
|
|
2015
|
81 |
C |
p. 98-105
8 p.
|
artikel
|
| 37 |
Safety assessment of U–Mo fuel mini plates irradiated in HANARO reactor
|
Jo, Daeseong
|
|
2015
|
81 |
C |
p. 219-226
8 p.
|
artikel
|
| 38 |
SMITHERS: An object-oriented modular mapping methodology for MCNP-based neutronic–thermal hydraulic multiphysics
|
Richard, Joshua
|
|
2015
|
81 |
C |
p. 150-163
14 p.
|
artikel
|
| 39 |
Social networking-based simulations for nuclear security: Strategy assessment following nuclear cyber terror on South Korean nuclear power plants (NPPs)
|
Woo, Tae Ho
|
|
2015
|
81 |
C |
p. 91-97
7 p.
|
artikel
|
| 40 |
Spectral history model in DYN3D: Verification against coupled Monte-Carlo thermal-hydraulic code BGCore
|
Bilodid, Y.
|
|
2015
|
81 |
C |
p. 34-40
7 p.
|
artikel
|
| 41 |
The ‘Fuel Rod Analysis ToolBox’: A general program for preparing the input of a fuel rod performance code
|
Lassmann, K.
|
|
2015
|
81 |
C |
p. 332-335
4 p.
|
artikel
|
Tijdschrift beschrijving