| nr |
titel |
auteur |
tijdschrift |
jaar |
jaarg. |
afl. |
pagina('s) |
type |
| 1 |
A liquid injection based Second Shutdown System for a typical material testing research reactor
|
Boustani, Ehsan
|
|
|
115 |
C |
p. 487-493
|
artikel
|
| 2 |
Analysis and modeling of post-dryout heat transfer in upward vertical flow
|
Yu, Dali
|
|
|
115 |
C |
p. 186-194
|
artikel
|
| 3 |
Analysis of the IAEA benchmark on heat transfer in a 4 × 4 rod bundle with mixing grid
|
Bieder, Ulrich
|
|
|
115 |
C |
p. 352-366
|
artikel
|
| 4 |
An application of the nodal expansion method to the determination of the radial temperature distribution in a nuclear fuel rod
|
Dall’Osso, Aldo
|
|
|
115 |
C |
p. 9-15
|
artikel
|
| 5 |
A new local variance reduction method based on anti-forward Monte Carlo calculation
|
Shi, Tao
|
|
|
115 |
C |
p. 595-600
|
artikel
|
| 6 |
A new method for simulating aerosols Brownian coagulation based on finite active samples assumption
|
Li, Yu
|
|
|
115 |
C |
p. 534-541
|
artikel
|
| 7 |
Application of sub-channel modeling to BWR core analysis
|
Gosdin, C.
|
|
|
115 |
C |
p. 294-302
|
artikel
|
| 8 |
A review for identification and selection of initiating events important for Level 1 probabilistic safety assessment study for a 10 MW water water research reactor (VVR)
|
Ameyaw, F.
|
|
|
115 |
C |
p. 303-314
|
artikel
|
| 9 |
A steam or gas pressurizer effect on the system pressure characteristics for an integral pressurized water reactor
|
Chung, Young-Jong
|
|
|
115 |
C |
p. 249-255
|
artikel
|
| 10 |
Best estimate calculation and uncertainty quantification of sodium-cooled fast reactor using MARS-LMR code
|
Kang, Seok-Ju
|
|
|
115 |
C |
p. 138-153
|
artikel
|
| 11 |
Boundary identification between LBLOCA and SBLOCA based on stratification and temperature gradient in two-phase PTS
|
Ghafari, M.
|
|
|
115 |
C |
p. 430-441
|
artikel
|
| 12 |
CFD analysis of steam jet injection in a hybrid SIT
|
Jeon, Byong Guk
|
|
|
115 |
C |
p. 126-137
|
artikel
|
| 13 |
Code-to-code comparisons on spatial solution capabilities and performances between nTRACER and the standalone IDT solver of APOLLO3®
|
Ban, Young Suk
|
|
|
115 |
C |
p. 573-594
|
artikel
|
| 14 |
Comment on “Vanadium, rhodium, silver and cobalt self-powered neutron detector calculations by RAST-K v2.0”
|
Wiesenack, Wolfgang
|
|
|
115 |
C |
p. 633-634
|
artikel
|
| 15 |
Continuous energy coarse mesh transport (COMET) method
|
Rahnema, Farzad
|
|
|
115 |
C |
p. 601-610
|
artikel
|
| 16 |
Correlation between pressure tube thickness and expected discharged burnup in CANDU: Lattice calculations
|
Kastanya, Doddy
|
|
|
115 |
C |
p. 243-248
|
artikel
|
| 17 |
Coupled unstructured fine-mesh neutronics and thermal-hydraulics methodology using open software: A proof-of-concept
|
Vasconcelos, Vitor
|
|
|
115 |
C |
p. 173-185
|
artikel
|
| 18 |
Criticality concerns of a group actinide co-crystallization separations approach to used nuclear fuel recycling
|
Kitcher, Evans D.
|
|
|
115 |
C |
p. 387-392
|
artikel
|
| 19 |
Cross-section adjustment in the fast energy range on the basis of an Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology
|
Pelloni, Sandro
|
|
|
115 |
C |
p. 323-342
|
artikel
|
| 20 |
Determination of the optimal few-energy group structure for the Canadian Super Critical Water-cooled Reactor
|
Moghrabi, A.
|
|
|
115 |
C |
p. 27-38
|
artikel
|
| 21 |
Development of a new general nuclide inventory analysis code GNIAC
|
Ma, Jimin
|
|
|
115 |
C |
p. 415-422
|
artikel
|
| 22 |
Dynamic event tree analysis with the SAS4A/SASSYS-1 safety analysis code
|
Jankovsky, Zachary K.
|
|
|
115 |
C |
p. 55-72
|
artikel
|
| 23 |
Dynamic response analysis of corrosion products activity under steady state operation and Mechanical Shim based power-maneuvering transients in AP-1000
|
Mahmood, Fiaz
|
|
|
115 |
C |
p. 16-26
|
artikel
|
| 24 |
Editorial Board
|
|
|
|
115 |
C |
p. ii
|
artikel
|
| 25 |
Estimation of pressure-equalizing time for a hybrid safety injection tank used in a passive safety injection system
|
Kim, Jaemin
|
|
|
115 |
C |
p. 154-160
|
artikel
|
| 26 |
Exergy and exergoeconomic analyses of a novel integration of a 1000 MW pressurized water reactor power plant and a gas turbine cycle through a superheater
|
Seyyedi, S.M.
|
|
|
115 |
C |
p. 161-172
|
artikel
|
| 27 |
Experimental investigation on heat transfer behavior in a tight 19 rod bundle cooled with supercritical R134a
|
Chen, Jiayue
|
|
|
115 |
C |
p. 393-402
|
artikel
|
| 28 |
Gemma: Development of a two-dimensional neutron transport code with the method of characteristics
|
Reyes, Guillermo Ibarra
|
|
|
115 |
C |
p. 367-376
|
artikel
|
| 29 |
Grid-based RRT∗ for minimum dose walking path-planning in complex radioactive environments
|
Chao, Nan
|
|
|
115 |
C |
p. 73-82
|
artikel
|
| 30 |
Impact of new nuclear data on neutronic calculations of the OPAL Reactor using Serpent
|
Maul, Lance
|
|
|
115 |
C |
p. 523-533
|
artikel
|
| 31 |
Implementation and assessment of wall friction models for LWR core analysis
|
Toptan, Aysenur
|
|
|
115 |
C |
p. 565-572
|
artikel
|
| 32 |
Implementation of a frequency-domain neutron noise analysis method in a production-level continuous energy Monte Carlo code: Verification and application in a BWR
|
Yamamoto, Toshihiro
|
|
|
115 |
C |
p. 494-501
|
artikel
|
| 33 |
Influence of particle morphology on pressure gradients of single-phase air flow in the mono-size non-spherical particle beds
|
Park, Jin Ho
|
|
|
115 |
C |
p. 1-8
|
artikel
|
| 34 |
Investigation on the lubrication regimes and dynamic characteristics of hydro-hybrid bearing of two-circuit main loop liquid sodium pump system
|
Xie, Zhongliang
|
|
|
115 |
C |
p. 220-232
|
artikel
|
| 35 |
Letter to the editor
|
Khoshahval, Farrokh
|
|
|
115 |
C |
p. 635-636
|
artikel
|
| 36 |
Magnetic-field analysis of an MHD channel in a liquid-metal circulation system of a prototype GenIV sodium fast reactor
|
Lee, Geun Hyeong
|
|
|
115 |
C |
p. 343-351
|
artikel
|
| 37 |
Method of WWER active core power parameters evaluation by readings of ex-core neutron flux monitoring system using additional information
|
Druzhaev, A.A.
|
|
|
115 |
C |
p. 542-553
|
artikel
|
| 38 |
Minor actinide transmutation characteristics in AP1000
|
Liu, Bin
|
|
|
115 |
C |
p. 116-125
|
artikel
|
| 39 |
Modeling Safety-II based on unexpected reactor trips
|
Park, Jooyoung
|
|
|
115 |
C |
p. 280-293
|
artikel
|
| 40 |
Neutronic calculation of an axially heterogeneous ASTRID fuel assembly with APOLLO3®: Analysis of biases and foreseen improvements
|
Faure, Bastien
|
|
|
115 |
C |
p. 88-104
|
artikel
|
| 41 |
Neutronic calculations of a thermal reactor using the Albedo Method in two energy groups
|
Fiel, João Cláudio Batista
|
|
|
115 |
C |
p. 83-87
|
artikel
|
| 42 |
Numerical analysis of frequency optimization and effect of liquid sodium for ultrasonic high frequency guided wave inspection of core support structure of fast breeder reactor
|
Dhayalan, R.
|
|
|
115 |
C |
p. 233-242
|
artikel
|
| 43 |
Numerical predictions of the drag coefficients of irregular particles in an HTGR
|
Sun, Qi
|
|
|
115 |
C |
p. 195-208
|
artikel
|
| 44 |
Numerical study on flow inversion in UTSG under natural circulation
|
Bian, Bo-shen
|
|
|
115 |
C |
p. 315-322
|
artikel
|
| 45 |
Online gamma-ray spectroscopy acquisition
|
Yang, Xue
|
|
|
115 |
C |
p. 105-115
|
artikel
|
| 46 |
Optimization of the cross section area on the meridian surface of the 1400-MW canned nuclear coolant pump based on a new medial axial transform design method
|
Wang, Xiaofang
|
|
|
115 |
C |
p. 466-479
|
artikel
|
| 47 |
Post-operation radiological source term and dose rate estimates for the Scalable LIquid Metal-cooled small Modular Reactor
|
El-Genk, Mohamed S.
|
|
|
115 |
C |
p. 442-458
|
artikel
|
| 48 |
Reactor physics phenomena in additively manufactured control elements for the High Flux Isotope Reactor
|
Burns, Joseph R.
|
|
|
115 |
C |
p. 403-414
|
artikel
|
| 49 |
RELAP5 analysis of hydrodynamic loads in response to PORV actuation
|
Lim, Jaehyok
|
|
|
115 |
C |
p. 459-465
|
artikel
|
| 50 |
Research on the non-uniform inflow characteristics of the canned nuclear coolant pump
|
Wang, Yuehui
|
|
|
115 |
C |
p. 423-429
|
artikel
|
| 51 |
Scaled neutron point kinetics (SUNPK) equations for nuclear reactor dynamics: 2D approximation
|
Espinosa-Paredes, Gilberto
|
|
|
115 |
C |
p. 377-386
|
artikel
|
| 52 |
SERPENT validation and optimization with mesh adaptive search on stereolithography geometry models
|
Talamo, Alberto
|
|
|
115 |
C |
p. 619-632
|
artikel
|
| 53 |
Simulation of dryout phenomenon and transient heat transfer performance of the once-through steam generator based on heat transfer partition
|
Shen, Zhenyu
|
|
|
115 |
C |
p. 268-279
|
artikel
|
| 54 |
Simulation study of frequency control characteristics of a generation III + nuclear power plant
|
Wang, Pengfei
|
|
|
115 |
C |
p. 502-522
|
artikel
|
| 55 |
Spatial analysis of unprotected transients in heterogeneous sodium fast reactors
|
Laureau, A.
|
|
|
115 |
C |
p. 554-564
|
artikel
|
| 56 |
Structural assessment of jet impingement loads under postulated main steam line break conditions
|
Kim, Seung Hyun
|
|
|
115 |
C |
p. 611-618
|
artikel
|
| 57 |
The linear source approximation and particle conservation in the Method of Characteristics for isotropic and anisotropic sources
|
Ferrer, Rodolfo M.
|
|
|
115 |
C |
p. 209-219
|
artikel
|
| 58 |
Transient 3D heat transfer analysis up to the state of Dryout in fuel rods
|
Martins, Rodolfo Ienny
|
|
|
115 |
C |
p. 39-54
|
artikel
|
| 59 |
Transient 3D simulation for heating and melting process of PWR core after SBO
|
Zhang, Xiaoying
|
|
|
115 |
C |
p. 256-267
|
artikel
|
| 60 |
Void fraction measurement of the air-water two-phase flow in the sub-channel of a rod bundle geometry based on an impedance meter
|
Yu, Bin
|
|
|
115 |
C |
p. 480-486
|
artikel
|
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