| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Accident mitigation for spent fuel storage in the upper pool of a Mark III containment
|
Chen, Yen-Shu
|
|
2016
|
91 |
C |
p. 156-164
9 p.
|
artikel
|
| 2 |
A method for the identification of a set of critical safety functions for a uranium hexafluoride conversion plant
|
Santos, F.C.
|
|
2016
|
91 |
C |
p. 165-175
11 p.
|
artikel
|
| 3 |
An automatic adaptive mesh generation method for weight window in Monte Carlo particle transport
|
Zhao, Jinbo
|
|
2016
|
91 |
C |
p. 105-110
6 p.
|
artikel
|
| 4 |
An evaluation on the scenarios of work trajectory during installation of dismantling equipment for decommissioning of nuclear facilities
|
Jeong, KwanSeong
|
|
2016
|
91 |
C |
p. 25-35
11 p.
|
artikel
|
| 5 |
A note on “Comment on the paper: Espinosa-Paredes, et al., 2011. Fractional neutron point kinetics equations for nuclear reactor dynamics. Ann. Nucl. Energ. 38, 307–330.” by A. E. Aboanber, A. A. Nahla
|
Espinosa-Paredes, Gilberto
|
|
2016
|
91 |
C |
p. 215-216
2 p.
|
artikel
|
| 6 |
Burnup performance of small-sized long-life CANDLE high temperature gas-cooled reactors with U–Th–Pa fuel
|
Liem, Peng Hong
|
|
2016
|
91 |
C |
p. 36-47
12 p.
|
artikel
|
| 7 |
Design study of neutron beam facility around TRIGA research reactor core
|
Yasmeen, Rashida
|
|
2016
|
91 |
C |
p. 203-205
3 p.
|
artikel
|
| 8 |
Development and verification of a 281-group WIMS-D library based on ENDF/B-VII.1
|
Dong, Zhengyun
|
|
2016
|
91 |
C |
p. 189-194
6 p.
|
artikel
|
| 9 |
Editorial board
|
|
|
2016
|
91 |
C |
p. IFC-
1 p.
|
artikel
|
| 10 |
Evaluation methodology of a manipulator actuator for the dismantling process during nuclear decommissioning
|
Park, Jongwon
|
|
2016
|
91 |
C |
p. 22-24
3 p.
|
artikel
|
| 11 |
Experimentally investigating boiling characteristics in the transition boiling for the downward facing heating
|
Chuang, T.J.
|
|
2016
|
91 |
C |
p. 148-155
8 p.
|
artikel
|
| 12 |
Formulation of a point reactor kinetics model based on the neutron telegraph equation
|
Altahhan, Muhammad Ramzy
|
|
2016
|
91 |
C |
p. 176-188
13 p.
|
artikel
|
| 13 |
Fuel cycle scheme design and evaluation for thorium–uranium breeding recycle in CANDU reactors
|
Yang, Bo
|
|
2016
|
91 |
C |
p. 195-202
8 p.
|
artikel
|
| 14 |
Hydrodynamics of two-phase flow in a rod bundle under cross-flow condition
|
Tian, W.X.
|
|
2016
|
91 |
C |
p. 206-214
9 p.
|
artikel
|
| 15 |
Implementation and testing of the on-the-fly thermal scattering Monte Carlo sampling method for graphite and light water in MCNP6
|
Pavlou, Andrew T.
|
|
2016
|
91 |
C |
p. 111-126
16 p.
|
artikel
|
| 16 |
Matlab enhanced multi-threaded tomography optimization sequence (MEMTOS)
|
Lum, Edward S.
|
|
2016
|
91 |
C |
p. 127-134
8 p.
|
artikel
|
| 17 |
Parallel GPU implementation of PWR reactor burnup
|
Heimlich, A.
|
|
2016
|
91 |
C |
p. 135-141
7 p.
|
artikel
|
| 18 |
Primary loop analysis for a PWR contains Passive Core Cooling System; LOCA and clad rising temperature
|
Porhemmat, M.H.
|
|
2016
|
91 |
C |
p. 8-21
14 p.
|
artikel
|
| 19 |
Risk monitor riskangel for risk-informed applications in nuclear power plants
|
Wang, Fang
|
|
2016
|
91 |
C |
p. 142-147
6 p.
|
artikel
|
| 20 |
Risk reduction due to modification of normal residual heat removal system of AP1000® reactor to meet European Utility Requirements
|
Queral, C.
|
|
2016
|
91 |
C |
p. 65-78
14 p.
|
artikel
|
| 21 |
Study on a new framework of Human Reliability Analysis to evaluate soft control execution error in advanced MCRs of NPPs
|
Jang, Inseok
|
|
2016
|
91 |
C |
p. 92-104
13 p.
|
artikel
|
| 22 |
Supercritical kinetic analysis in simplified system of fuel debris using integral kinetic model
|
Tuya, Delgersaikhan
|
|
2016
|
91 |
C |
p. 59-64
6 p.
|
artikel
|
| 23 |
The effect of smaller turbulent motions on heat transfer in the annular gap flow of flywheel
|
Wang, Y.J.
|
|
2016
|
91 |
C |
p. 1-7
7 p.
|
artikel
|
| 24 |
Uncertainty quantification and representativity analysis of LWR-PROTEUS Phase III experiments using SHARKX
|
Hursin, Mathieu
|
|
2016
|
91 |
C |
p. 48-58
11 p.
|
artikel
|
| 25 |
Validation of the Serpent 2-DYNSUB code sequence using the Special Power Excursion Reactor Test III (SPERT III)
|
Knebel, Miriam
|
|
2016
|
91 |
C |
p. 79-91
13 p.
|
artikel
|
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