| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
Activation of FLiBe coolant in the molten salt reactor
|
Ying, Dongchuan
|
|
2019
|
129 |
C |
p. 62-66
|
artikel
|
| 2 |
Advanced method for depletion calculation of control rods in sodium fast reactors
|
Guo, H.
|
|
2019
|
129 |
C |
p. 160-168
|
artikel
|
| 3 |
Advanced method for neutronic simulation of control rods in sodium fast reactors: Numerical and experimental validation
|
Guo, H.
|
|
2019
|
129 |
C |
p. 90-100
|
artikel
|
| 4 |
A leakage correction with SPH factors for two-group constants in GET-based pin-by-pin reactor analyses
|
Yu, Hwanyeal
|
|
2019
|
129 |
C |
p. 30-55
|
artikel
|
| 5 |
Analysis of different inert gas injection point's influence on hydrogen risk during post-inerting in nuclear power plant
|
Lyu, Xuefeng
|
|
2019
|
129 |
C |
p. 249-252
|
artikel
|
| 6 |
Analysis of IPWR neutronic-thermohydraulic operation characteristics under low power condition
|
Sun, Lin
|
|
2019
|
129 |
C |
p. 146-159
|
artikel
|
| 7 |
An application for streamlined and automated ENDF Cross Section Analysis and visualization (EXSAN)
|
Wooten, H. Omar
|
|
2019
|
129 |
C |
p. 482-486
|
artikel
|
| 8 |
A walk-away safe, Very-Small, Long-LIfe, Modular (VSLLIM) reactor for portable and stationary power
|
El-Genk, Mohamed S.
|
|
2019
|
129 |
C |
p. 181-198
|
artikel
|
| 9 |
Bubble detection in sodium flow using EVFM and correlation coefficient calculation
|
Xu, Wei
|
|
2019
|
129 |
C |
p. 472-481
|
artikel
|
| 10 |
Comparative dynamic analyses under HELB-induced jet impingement loads
|
Kim, Seung Hyun
|
|
2019
|
129 |
C |
p. 418-427
|
artikel
|
| 11 |
Control of a PWR nuclear reactor core power using scheduled PID controller with GA, based on two-point kinetics model and adaptive disturbance rejection system
|
Mousakazemi, Seyed Mohammad Hossein
|
|
2019
|
129 |
C |
p. 487-502
|
artikel
|
| 12 |
Development of a subchannel analysis code and its application to annular fuel assemblies
|
Xia, Hang
|
|
2019
|
129 |
C |
p. 428-436
|
artikel
|
| 13 |
Development of the RAINBOW code to evaluate assembly bowing reactivity coefficients in sodium-cooled fast reactors
|
Jing, Tian
|
|
2019
|
129 |
C |
p. 289-297
|
artikel
|
| 14 |
Editorial Board
|
|
|
2019
|
129 |
C |
p. ii
|
artikel
|
| 15 |
Effective subgroup method employing macro level grid optimization for LWR applications
|
Park, Hansol
|
|
2019
|
129 |
C |
p. 461-471
|
artikel
|
| 16 |
Enhancements along with application of the Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology by individual assimilations of fast reactor data
|
Pelloni, Sandro
|
|
2019
|
129 |
C |
p. 79-89
|
artikel
|
| 17 |
Evaluation of accident tolerant cladding materials in a severe accident of the BNPP
|
Ebrahimgol, H.
|
|
2019
|
129 |
C |
p. 214-223
|
artikel
|
| 18 |
Evaluation of the neutronic Superphenix start-up commissioning tests with TRIPOLI4
|
Garcia, E.
|
|
2019
|
129 |
C |
p. 366-374
|
artikel
|
| 19 |
Evaluation of the Th–U mixed oxide fuel neutronic characteristics in a CANDU 6® reactor
|
Visan, Iuliana
|
|
2019
|
129 |
C |
p. 240-248
|
artikel
|
| 20 |
Fuel cladding damage assessment based on reactivity insertion accidents for a 10 MWth LBE cooled fast reactor
|
Li, Ting
|
|
2019
|
129 |
C |
p. 412-417
|
artikel
|
| 21 |
GPU accelerated lattice Boltzmann method in neutron kinetics problems
|
Wang, Yahui
|
|
2019
|
129 |
C |
p. 350-365
|
artikel
|
| 22 |
Hugoniot analysis of energetic molten lead-water interaction
|
Iskhakov, A.S.
|
|
2019
|
129 |
C |
p. 437-449
|
artikel
|
| 23 |
Impact of system parameters on quenching heat transfer in the candidate materials for accident tolerant fuel-cladding in LWRs
|
Kang, Jun-young
|
|
2019
|
129 |
C |
p. 375-389
|
artikel
|
| 24 |
Implementation of the transient fixed-source problem in the neutron transport code PROTEUS-MOC
|
Nguyen, Tat Nghia
|
|
2019
|
129 |
C |
p. 199-206
|
artikel
|
| 25 |
Mechanism design of data management system for nuclear power
|
Shentu, Jun
|
|
2019
|
129 |
C |
p. 21-29
|
artikel
|
| 26 |
Microscopic calculation of delayed-photoneutron production in D2O using Geant4
|
Rand, E.T.
|
|
2019
|
129 |
C |
p. 390-398
|
artikel
|
| 27 |
Modeling isotopic evolution with surrogates based on dynamic mode decomposition
|
Abdo, Mohammad
|
|
2019
|
129 |
C |
p. 280-288
|
artikel
|
| 28 |
Modelling of a planar impinging jet at unity, moderate and low Prandtl number: Assessment of advanced RANS closures
|
De Santis, Andrea
|
|
2019
|
129 |
C |
p. 125-145
|
artikel
|
| 29 |
Neutronic analysis of thorium MOX fuel blocks with different driver fuels in advanced block-type HTRs
|
Attom, Areej Mutwakkil
|
|
2019
|
129 |
C |
p. 101-109
|
artikel
|
| 30 |
New energy deposition treatment in the Serpent 2 Monte Carlo transport code
|
Tuominen, Riku
|
|
2019
|
129 |
C |
p. 224-232
|
artikel
|
| 31 |
Numerical analysis of isotope production in molten salt reactors: A case study for Molybdenum-99 production
|
Stoddard, M.N.
|
|
2019
|
129 |
C |
p. 56-61
|
artikel
|
| 32 |
On SP N theory
|
Sanchez, Richard
|
|
2019
|
129 |
C |
p. 331-349
|
artikel
|
| 33 |
Optimization of hydrogen mitigation systems in CPR1000 during a refueling outage
|
Huang, Zhi'ao
|
|
2019
|
129 |
C |
p. 253-263
|
artikel
|
| 34 |
Parametric neutronics analyses of lattice geometry and coolant candidates for a soluble-boron-free civil marine SMR core using micro-heterogeneous duplex fuel
|
Alam, Syed Bahauddin
|
|
2019
|
129 |
C |
p. 1-12
|
artikel
|
| 35 |
Performance analysis of UO2 fuel rod for low-power research reactor application
|
Jeong, Gwan Yoon
|
|
2019
|
129 |
C |
p. 233-239
|
artikel
|
| 36 |
Plutonium multi recycling in pressurised water reactors of the EPR type using laser isotope separation of Pu242
|
Camarcat, Noel
|
|
2019
|
129 |
C |
p. 399-411
|
artikel
|
| 37 |
Re-assessment of station blackout accident in VVER-1000 NPP with additional measures following Fukushima accident using Relap/Mod3.2
|
Jabbari, M.
|
|
2019
|
129 |
C |
p. 316-330
|
artikel
|
| 38 |
Scaling and integral effect test on transition from depressurization to long-term gravity injection
|
Li, Yuquan
|
|
2019
|
129 |
C |
p. 110-124
|
artikel
|
| 39 |
Sensitivity and uncertainty analysis on keff due to nuclear data in the KRITZ-2:19 – Comparison between JENDL-4.0 and ENDF/B-VII.1
|
Ahmed, Abdulaziz
|
|
2019
|
129 |
C |
p. 308-315
|
artikel
|
| 40 |
Shapley effect application for variance-based sensitivity analysis of the few-group cross-sections
|
Radaideh, Majdi I.
|
|
2019
|
129 |
C |
p. 264-279
|
artikel
|
| 41 |
Simulation and optimization of control rod sequence exchange operations for a pressurized water reactor under Mechanical Shim control strategy
|
He, Zhengxi
|
|
2019
|
129 |
C |
p. 450-460
|
artikel
|
| 42 |
Stability analysis of the CMFD scheme with linear prolongation
|
Shen, Qicang
|
|
2019
|
129 |
C |
p. 298-307
|
artikel
|
| 43 |
Studies of intra-pin power distributions in operated BWR fuel assemblies using MCNP with a cycle check-up methodology
|
Pecchia, M.
|
|
2019
|
129 |
C |
p. 67-78
|
artikel
|
| 44 |
Study of gas-liquid upward annular flow through a contraction
|
Anupriya, S.
|
|
2019
|
129 |
C |
p. 169-180
|
artikel
|
| 45 |
Three dimensional void distribution measurement of salt-water pool-boiling in 5 × 5 bundle geometry with X-ray CT system
|
Furuya, Masahiro
|
|
2019
|
129 |
C |
p. 207-213
|
artikel
|
| 46 |
Verification and validation of the modular ray tracing MOC using the coupled forward-adjoint approach and application to C5G7 benchmark
|
Porhemmat, M.H.
|
|
2019
|
129 |
C |
p. 13-20
|
artikel
|
Tijdschrift beschrijving