| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review
|
Abdellatif, Hossam H.
|
|
|
168 |
C |
p.
|
artikel
|
| 2 |
A hybrid Analytical Discrete Ordinates-Response Matrix Constant Nodal method for one-speed X, Y-geometry transport problems
|
Moraes, Leonardo R.C.
|
|
|
168 |
C |
p.
|
artikel
|
| 3 |
Analysis method for aerosol deposition behavior under sodium spray fire
|
Yu, Zhitong
|
|
|
168 |
C |
p.
|
artikel
|
| 4 |
Analysis of loss of flow without scram test in the FFTF reactor – Part I: Preparation of neutronics data
|
Nikitin, Evgeny
|
|
|
168 |
C |
p.
|
artikel
|
| 5 |
Analysis of nuclear microreactor efficacy with hydrogen production methods
|
Kalinichenko, Dimitri
|
|
|
168 |
C |
p.
|
artikel
|
| 6 |
An intelligent fault detection and diagnosis monitoring system for reactor operational resilience: Fault diagnosis
|
Mendoza, Mario
|
|
|
168 |
C |
p.
|
artikel
|
| 7 |
An inter-channel mixing model based on the void distribution in a rod bundle
|
He, Ming-yue
|
|
|
168 |
C |
p.
|
artikel
|
| 8 |
Cementation of degraded residues of spent radioactive organic solvents by fenton oxidation
|
Chen, Lei
|
|
|
168 |
C |
p.
|
artikel
|
| 9 |
CFD analysis of iodine mass transfer coupled with a chemical reaction in a filtered containment venting system
|
Humayun, Muhammad Shummas
|
|
|
168 |
C |
p.
|
artikel
|
| 10 |
Cohesive, elastic and anisotropic properties of s-, p- and d-block fission metals substituted Fe–Zr intermetallics
|
Ali, Kawsar
|
|
|
168 |
C |
p.
|
artikel
|
| 11 |
Control strategies and performance analysis for a novel nuclear heating system with heat storage
|
Liu, Weiqi
|
|
|
168 |
C |
p.
|
artikel
|
| 12 |
Corrosion products deposition and its effects on conjugate heat transfer for helical cruciform fuel assembly
|
Cong, Tenglong
|
|
|
168 |
C |
p.
|
artikel
|
| 13 |
Critical heat flux for downward flows in vertical round pipes
|
Hirose, Yoshiyasu
|
|
|
168 |
C |
p.
|
artikel
|
| 14 |
Development of a flow intrusion model for effectiveness evaluation in nuclear power plant security system
|
YAN, Zhenyu
|
|
|
168 |
C |
p.
|
artikel
|
| 15 |
Editorial Board
|
|
|
|
168 |
C |
p.
|
artikel
|
| 16 |
Effect of irradiation on thermal stability of nitric acid solutions of acetohydroxamic acid
|
Obedkov, A.S.
|
|
|
168 |
C |
p.
|
artikel
|
| 17 |
Effect of metallic redox ions on the corrosion behavior of GTAW weldment of type 304L stainless steel in simulated non-radioactive PUREX and HLLW medium
|
Shit, Gopinath
|
|
|
168 |
C |
p.
|
artikel
|
| 18 |
Encapsulation of radioactive stainless-steel corrosion products sludge in aluminum using hot isostatic pressing process and treatment suitability assessment
|
Kang, Ki Joon
|
|
|
168 |
C |
p.
|
artikel
|
| 19 |
Equivalence method and transient flow characteristics of the integrated valve
|
Yang, Linqing
|
|
|
168 |
C |
p.
|
artikel
|
| 20 |
Estimation of transuranic isotopes in irradiated fuel elements for pebble bed HTR on activity vector
|
Zhang, Hongjian
|
|
|
168 |
C |
p.
|
artikel
|
| 21 |
Experimental demonstration of a data-driven control system for subcritical nuclear facility
|
Yu, Jiankai
|
|
|
168 |
C |
p.
|
artikel
|
| 22 |
Experimental study of the depressurization phenomena of supercritical carbon dioxide system
|
Liu, Minyun
|
|
|
168 |
C |
p.
|
artikel
|
| 23 |
Flow blockage accident analysis in a multi purposes research reactor using Relap5 system code
|
Deghal Cheridi, Amina Lyria
|
|
|
168 |
C |
p.
|
artikel
|
| 24 |
Gamma-ray spectra of post-irradiated uranium salt for total mass accounting with sodium-22 tracer
|
Van Zile, Matthew
|
|
|
168 |
C |
p.
|
artikel
|
| 25 |
Neutron fission chain behavior for modern 235U multiplicity data
|
Durkee Jr., Joe W.
|
|
|
168 |
C |
p.
|
artikel
|
| 26 |
Nuclear safety operating margin using new power peaking factors for NUR nuclear research reactor
|
Sidi-Ali, K.
|
|
|
168 |
C |
p.
|
artikel
|
| 27 |
Numerical simulation of thermal hydraulics of supercritical pressure water with 2×2 rod assembly wrapped differently with a wire
|
Kumar, Gaurav
|
|
|
168 |
C |
p.
|
artikel
|
| 28 |
Numerical study on a 7-pin bundle fuel assembly with different wire arrangements
|
Li, Yaodi
|
|
|
168 |
C |
p.
|
artikel
|
| 29 |
Numerical study on flow structure and heat transfer of supercritical CO2 in tubes with different inclination angles
|
Hou, Junren
|
|
|
168 |
C |
p.
|
artikel
|
| 30 |
Numerical study on thermal hydraulics characteristics during steam submerged jet condensation from rectangular CD nozzle
|
Quddus, Abdul
|
|
|
168 |
C |
p.
|
artikel
|
| 31 |
Physical optimization and safety analysis of space thermionic reactor
|
Xie, Lin
|
|
|
168 |
C |
p.
|
artikel
|
| 32 |
Possibility of YH1.85 and MgO–BeO as a moderator in high temperature reactors
|
Tiftikci, Ali
|
|
|
168 |
C |
p.
|
artikel
|
| 33 |
Prediction of sodium leakage droplet size distribution in sodium-cooled fast reactor loop
|
Xu, Zhen
|
|
|
168 |
C |
p.
|
artikel
|
| 34 |
Preliminary analysis of startup transient for an ultra-small lithium-cooled space reactor power system
|
Ge, Li
|
|
|
168 |
C |
p.
|
artikel
|
| 35 |
Preliminary analysis of the irradiation deformation of a typical molten salt reactor graphite component
|
Wang, Yong
|
|
|
168 |
C |
p.
|
artikel
|
| 36 |
Preliminary safety analysis of the TRANSMUTEX sub-critical reactor using the GeN-Foam multi-physics solver
|
Guilbaud, Thomas
|
|
|
168 |
C |
p.
|
artikel
|
| 37 |
Radiation safety assessments for radioactive concrete recycling workers and residents
|
Kim, Min Ji
|
|
|
168 |
C |
p.
|
artikel
|
| 38 |
Radiological characterization plan for decommissioning IFIN-HH's Cyclotron
|
Ionescu, E.
|
|
|
168 |
C |
p.
|
artikel
|
| 39 |
Reactor lightweight shielding optimization method based on parallel embedded genetic particle-swarm hybrid algorithm
|
Zheng, Songchuan
|
|
|
168 |
C |
p.
|
artikel
|
| 40 |
Reactor reliability modeling and reliable life analysis method for multi-state space reactor systems based on DBN and interval estimation
|
Chen, Ziwei
|
|
|
168 |
C |
p.
|
artikel
|
| 41 |
Release of windowed multipole library for ENDF/B-VIII.0 in support of OpenMC criticality and depletion analysis
|
Yu, Jiankai
|
|
|
168 |
C |
p.
|
artikel
|
| 42 |
SBLOCA analysis of a floating nuclear reactor under ocean conditions using MARS-KS moving reactor model
|
Ko, Yujoeng
|
|
|
168 |
C |
p.
|
artikel
|
| 43 |
Shifting to a 36-month fuel cycle with advanced moderating burnable absorbers enabling high assay low enriched uranium (HALEU)
|
Bolukbasi, M.J.
|
|
|
168 |
C |
p.
|
artikel
|
| 44 |
The application of trajectory analysis method and Fast Fourier Transform analysis method in the division of flow instability influence regions under ocean conditions
|
Wang, Sipeng
|
|
|
168 |
C |
p.
|
artikel
|
| 45 |
The effect of the radial heat loss, upper reservoir temperature, and corrugated wall channel on the flooding critical heat flux
|
Nahon, Lior
|
|
|
168 |
C |
p.
|
artikel
|
| 46 |
Thermal and radiation shielding characteristics of erbium ions doped zinc tellurite glasses
|
Nazrin, S.N
|
|
|
168 |
C |
p.
|
artikel
|
| 47 |
Time-dependent simplified D P 1 approximation for neutron transport equation
|
Nazari, M.
|
|
|
168 |
C |
p.
|
artikel
|
| 48 |
TRU utilization and MA transmutation in thorium-based fluorinated molten salt fast reactor
|
Li, Dongguo
|
|
|
168 |
C |
p.
|
artikel
|
| 49 |
Using life cycle assessment to quantify the environmental benefits of circular economy strategies in the nuclear industry
|
Pucciarelli, Martina
|
|
|
168 |
C |
p.
|
artikel
|
| 50 |
Xenon behavior modeling for molten salt reactors by using multiple transport mechanisms
|
Wu, Chen
|
|
|
168 |
C |
p.
|
artikel
|
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