| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A differentiator based second-order sliding-mode control of a pressurized water nuclear research reactor considering Xenon concentration feedback
|
Abdulraheem, Kamal Kayode
|
|
|
156 |
C |
p.
|
artikel
|
| 2 |
A flexible optimization algorithm for GO-FLOW methodology to deal with shared signals
|
Zheng, Licheng
|
|
|
156 |
C |
p.
|
artikel
|
| 3 |
A graph representation model for radiation exposure prediction and path-planning in nuclear power plants
|
Li, Mengkun
|
|
|
156 |
C |
p.
|
artikel
|
| 4 |
A Lie symmetries interpretation of the neutron diffusion equation
|
Ramsey, Scott D.
|
|
|
156 |
C |
p.
|
artikel
|
| 5 |
An applicability study of scoping libraries on BWR fuel assembly designs
|
Tung, Wu-Hsiung
|
|
|
156 |
C |
p.
|
artikel
|
| 6 |
A new equation for Bondarenko self-shielded cross section sensitivities to nuclide densities
|
Favorite, Jeffrey A.
|
|
|
156 |
C |
p.
|
artikel
|
| 7 |
A preliminary study on visibility improvement of turbid underwater images for dismantling of nuclear facilities
|
Park, Seung-Kyu
|
|
|
156 |
C |
p.
|
artikel
|
| 8 |
A rapid coupling method for calculating the radiation field in decommissioning nuclear power plants
|
Zhang, Zehuan
|
|
|
156 |
C |
p.
|
artikel
|
| 9 |
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR
|
Maccari, Pietro
|
|
|
156 |
C |
p.
|
artikel
|
| 10 |
Design of non-instrumented irradiation capsule for material irradiation in FBTR at different higher temperatures
|
Saurav, Suman
|
|
|
156 |
C |
p.
|
artikel
|
| 11 |
Development of a multi-physics coupling system based on ICoCo interface and its validation on NEA-OECD core transient benchmark
|
Feng, Wenpei
|
|
|
156 |
C |
p.
|
artikel
|
| 12 |
Development of a web-based radiological emergency preparedness system for nuclear accidents
|
Suh, Kyung-Suk
|
|
|
156 |
C |
p.
|
artikel
|
| 13 |
Editorial Board
|
|
|
|
156 |
C |
p.
|
artikel
|
| 14 |
Effects of ion irradiation on Cr, CrN, and TiAlCrN coated Zircaloy-4 for accident tolerant fuel claddings
|
Song, Ligang
|
|
|
156 |
C |
p.
|
artikel
|
| 15 |
Evaluation of the reactor building environmental conditions under a LOCA for the decommissioning Chinshan plant
|
Chen, Yen-Shu
|
|
|
156 |
C |
p.
|
artikel
|
| 16 |
Experimental investigation of vacuum drying for removal of residual water in canister
|
Bang, Kyoung-Sik
|
|
|
156 |
C |
p.
|
artikel
|
| 17 |
Fuel cycle considerations for uranium, plutonium and minor actinide partitioning and transmutation
|
Taiwo, Temitope
|
|
|
156 |
C |
p.
|
artikel
|
| 18 |
Gaussian processes for surrogate modeling of discharged fuel nuclide compositions
|
Figueroa, Antonio
|
|
|
156 |
C |
p.
|
artikel
|
| 19 |
Identification of the appropriate architecture of multilayer feed-forward neural network for estimation of NPPs parameters using the GA in combination with the LM and the BR learning algorithms
|
Moshkbar-Bakhshayesh, Khalil
|
|
|
156 |
C |
p.
|
artikel
|
| 20 |
Improvement of plutonium sample property measurement based on fast neutron multiplicity counting
|
Hou, Suxia
|
|
|
156 |
C |
p.
|
artikel
|
| 21 |
Long-term reactivity control of accident tolerant fuel loaded marine small modular reactor using particle-type burnable poisons
|
Tiang, Zi Hua
|
|
|
156 |
C |
p.
|
artikel
|
| 22 |
Mathematical foundations of the three-dimensional neutron hydrodynamics coupled transport equations
|
Xu, Longfei
|
|
|
156 |
C |
p.
|
artikel
|
| 23 |
Multicollision source method for discrete ordinates neutron transport calculation
|
Wang, Xinyu
|
|
|
156 |
C |
p.
|
artikel
|
| 24 |
Neutron noise calculation: A comparative study between SP3 theory and diffusion theory
|
Gong, Helin
|
|
|
156 |
C |
p.
|
artikel
|
| 25 |
Nuclear-data uncertainty analysis for the start-up physics test of CPR1000 reactor
|
Zhang, Liming
|
|
|
156 |
C |
p.
|
artikel
|
| 26 |
Prediction of the internal states of a nuclear power plant containment in LOCAs using rule-dropout deep fuzzy neural networks
|
Koo, Young Do
|
|
|
156 |
C |
p.
|
artikel
|
| 27 |
Quantitative resilience evaluation on recovery from emergency situations in nuclear power plants
|
Kim, Ji Tae
|
|
|
156 |
C |
p.
|
artikel
|
| 28 |
Risk-informed approach for safety improvement of domestic research reactor
|
Lee, Yoon-Hwan
|
|
|
156 |
C |
p.
|
artikel
|
| 29 |
Study on heat transfer characteristics of liquid droplet radiator: With VS without inter-droplets coupling
|
Huang, Di
|
|
|
156 |
C |
p.
|
artikel
|
| 30 |
The windowed multipole formalism and applications to uncertainty quantification
|
Alhajri, Abdulla
|
|
|
156 |
C |
p.
|
artikel
|
| 31 |
Uncertainty analysis in coupled neutronic/thermal-hydraulic calculations based on computational fluid dynamics
|
Zhao, Pengcheng
|
|
|
156 |
C |
p.
|
artikel
|
| 32 |
VVER-1000/V446 spent fuel pool risk assessment and support through portable mitigating equipment
|
Afshar, N.
|
|
|
156 |
C |
p.
|
artikel
|
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