Macian-Juan, Rafael: search on Z-Library

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1

Steady-state reactor physics of the dual fluid reactor concept

Wang, Xiang, Macian-Juan, Rafael

Journal:

International Journal of Energy Research

Year:

2018

Language:

english

File:

PDF, 9.34 MB

english, 2018

2

Features and performance of a coupled three-dimensional thermal-hydraulic/kinetics TRAC-PF1/NEM pressurized water reactor (PWR) analysis code

Kostadin N. Ivanov, Rafael Macian-Juan, Adi Irani, Anthony J. Baratta

Journal:

Annals of Nuclear Energy

Year:

1999

Language:

english

File:

PDF, 165 KB

english, 1999

3

A statistical methodology for quantification of uncertainty in best estimate code physical models

Paolo Vinai, Rafael Macian-Juan, Rakesh Chawla

Journal:

Annals of Nuclear Energy

Year:

2007

Language:

english

File:

PDF, 1011 KB

english, 2007

4

[ASME 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference - Anaheim, California, USA (Monday 30 July 2012)] Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Co - CFD Simulation of Direct Contact Condensation With ANSYS CFX Using Locally Defined Heat Transfer Coefficients

Ceuca, Sabin Cristian, Macián-Juan, Rafael

Year:

2012

Language:

english

File:

PDF, 1.62 MB

english, 2012

5

Static and transient pin-by-pin simulations of a full PWR core with the extended coupled code system DYNSUB

Daeubler, Miriam, Trost, Nico, Jimenez, Javier, Sanchez, Victor, Stieglitz, Robert, Macian-Juan, Rafael

Journal:

Annals of Nuclear Energy

Year:

2015

Language:

english

File:

PDF, 1.09 MB

english, 2015

6

[ASME 2017 25th International Conference on Nuclear Engineering - Shanghai, China (Sunday 2 July 2017)] Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues - Comparative Study of Basic Reactor Physics of the DFR Concept Using U-Pu and TRU Fuel Salts

Wang, Xiang, Macian-Juan, Rafael

Year:

2017

Language:

english

File:

PDF, 4.87 MB

english, 2017

7

Mechanical analysis of the bow deformation of a row of fuel assemblies in a PWR core

Wanninger, Andreas, Seidl, Marcus, Macián-Juan, Rafael

Journal:

Nuclear Engineering and Technology

Year:

2018

Language:

english

File:

PDF, 4.08 MB

english, 2018

8

Front Cover Image

Wang, Xiang, Macian-Juan, Rafael

Journal:

International Journal of Energy Research

Year:

2018

File:

PDF, 240 KB

2018

9

Analysis of the capability of system codes to model cavitation water hammers: Simulation of UMSICHT water hammer experiments with TRACE and RELAP5

Werner Barten, Audrius Jasiulevicius, Annalisa Manera, Rafael Macian-Juan, Omar Zerkak

Journal:

Nuclear Engineering and Design

Year:

2008

Language:

english

File:

PDF, 2.43 MB

english, 2008

10

Photonuclear Benchmarks of C, Al, Cu, Ta, Pb, and U from the ENDF/B-VII Cross-Section Library ENDF7U Using MCNPX

Frankl, Matthias, Macián-Juan, Rafael

Journal:

Nuclear Science and Engineering

Year:

2016

Language:

english

File:

PDF, 1.44 MB

english, 2016

11

One- and two-dimensional standing pressure waves and one-dimensional travelling pulses using the US-NRC nuclear systems analysis code TRACE

Werner Barten, Annalisa Manera, Rafael Macian-Juan

Journal:

Nuclear Engineering and Design

Year:

2008

Language:

english

File:

PDF, 2.68 MB

english, 2008

12

[ASME 2013 21st International Conference on Nuclear Engineering - Chengdu, China (Monday 29 July 2013)] Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes - Experimental Investigation of CCFL in Large Diameter Hot-Leg Geometry

Al Issa, Suleiman, Macián-Juan, Rafael

Year:

2013

Language:

english

File:

PDF, 1.17 MB

english, 2013

13

[ASME 2017 25th International Conference on Nuclear Engineering - Shanghai, China (Sunday 2 July 2017)] Volume 6: Thermal-Hydraulics - Comparative Study of Thermal-Hydraulic Behavior of the DFR Using U-Pu and TRU Salt Fuels

Wang, Xiang, Macian-Juan, Rafael

Year:

2017

Language:

english

File:

PDF, 1.10 MB

english, 2017

14

Numerical diffusion and the tracking of solute fields in system codes: Part II. Multi-dimensional flows

Rafael Macian-Juan, John H. Mahaffy

Journal:

Nuclear Engineering and Design

Year:

1998

Language:

english

File:

PDF, 869 KB

english, 1998

15

[ASME 14th International Conference on Nuclear Engineering - Miami, Florida, USA (July 17–20, 2006)] Volume 2: Thermal Hydraulics - Predictions of Critical Heat Flux in Annular Pipes with TRACE V4.160 Code

Jasiulevicius, Audrius, Macian-Juan, Rafael

Year:

2006

Language:

english

File:

PDF, 282 KB

english, 2006

16

Numerical diffusion and the tracking of solute fields in system codes: Part I. One-dimensional flows

Rafael Macian-Juan, John H. Mahaffy

Journal:

Nuclear Engineering and Design

Year:

1998

Language:

english

File:

PDF, 311 KB

english, 1998

17

Experimental investigation and CFD validation of countercurrent flow limitation (CCFL) in a large-diameter PWR hot-leg geometry

Al Issa, Suleiman, Macian-Juan, Rafael

Journal:

Journal of Nuclear Science and Technology

Year:

2016

Language:

english

File:

PDF, 1.26 MB

english, 2016

18

Numerical diffusion and the tracking of solute fields in system codes: Part III. Application to a boron dilution transient analysis in the AP600

Rafael Macian-Juan, Kostadin Ivanov, John H Mahaffy

Journal:

Nuclear Engineering and Design

Year:

1998

Language:

english

File:

PDF, 258 KB

english, 1998

19

[ASME 2014 22nd International Conference on Nuclear Engineering - Prague, Czech Republic (Monday 7 July 2014)] Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory - Multi-Scale 2D Sensitivity Analysis of the TALL-3D Experiment

Geffray, Clotaire, Macián-Juan, Rafael

Year:

2014

Language:

english

File:

PDF, 2.00 MB

english, 2014

20

Integration of the subchannel thermal-hydraulic code SubChanFlow into the reactor dynamics code PARCS: Development and testing based on a computational benchmark

Basualdo, Joaquín R., Sánchez-Espinoza, Victor, Stieglitz, Robert, Macián-Juan, Rafael

Journal:

Progress in Nuclear Energy

Year:

2019

File:

PDF, 3.45 MB

2019

21

ICONE15-10194 ASSESSMENT OF THE CHF MODELS IN TRACE CODE AGAINST ROD BUNDLE EXPERIMENTAL DATA

Jasiulevicius, Audrius, Macian-Juan, Rafael

Journal:

The Proceedings of the International Conference on Nuclear Engineering (ICONE)

Year:

2007

File:

PDF, 784 KB

2007

22

Thermal Hydraulics Analysis of the Distribution Zone in Small Modular Dual Fluid Reactor

Liu, Chunyu, Li, Xiaodong, Luo, Run, Macian-Juan, Rafael

Journal:

Year:

2020

File:

PDF, 6.88 MB

2020

23

Droplets entrainment ratio in a PWR hot-leg pipe geometry

Al Issa, Suleiman, Macian-Juan, Rafael

Journal:

Nuclear Engineering and Design

Year:

2018

Language:

english

File:

PDF, 2.08 MB

english, 2018

24

[ASME 2017 25th International Conference on Nuclear Engineering - Shanghai, China (Sunday 2 July 2017)] Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues - Development of a Multiphysics Approach With ANSYS CFX and PARCS for Local Analysis of Neutron Oscillation

Du, Zhuoqi, Seidl, Marcus, Macián-Juan, Rafael

Year:

2017

Language:

english

File:

PDF, 786 KB

english, 2017

25

Numerical investigation of models for drag, lift, wall lubrication and turbulent dispersion forces for the simulation of gas–liquid two-phase flow

Yamoah, Stephen, Martínez-Cuenca, Raúl, Monrós, Guillem, Chiva, Sergio, Macián-Juan, Rafael

Journal:

Chemical Engineering Research and Design

Year:

2015

Language:

english

File:

PDF, 5.82 MB

english, 2015

26

Steam condensation simulation in a scaled IRWST-ADS simulator with GOTHIC 8.1

Estévez-Albuja, Samanta, Jimenez, Gonzalo, Al Issa, Suleiman, Macián-Juan, Rafael, Fernández-Cosials, Kevin, Queral, César

Journal:

Nuclear Engineering and Design

Year:

2018

Language:

english

File:

PDF, 4.15 MB

english, 2018

27

Validation of the Serpent 2-DYNSUB code sequence using the Special Power Excursion Reactor Test III (SPERT III)

Knebel, Miriam, Mercatali, Luigi, Sanchez, Victor, Stieglitz, Robert, Macian-Juan, Rafael

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 2.89 MB

english, 2016

28

Image-processing of time-averaged interface distributions representing CCFL characteristics in a large scale model of a PWR hot-leg pipe geometry

Al Issa, Suleiman, Macián-Juan, Rafael

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 3.23 MB

english, 2017

29

Propagation of void fraction uncertainty measures in the RETRAN-3D simulation of the Peach Bottom turbine trip

Paolo Vinai, Rafael Macian-Juan, Rakesh Chawla

Journal:

Annals of Nuclear Energy

Year:

2011

Language:

english

File:

PDF, 1.91 MB

english, 2011

30

DYNSUB: A high fidelity coupled code system for the evaluation of local safety parameters – Part I: Development, implementation and verification

Armando Miguel Gomez-Torres, Victor Hugo Sanchez-Espinoza, Kostadin Ivanov, Rafael Macian-Juan

Journal:

Annals of Nuclear Energy

Year:

2012

Language:

english

File:

PDF, 3.74 MB

english, 2012

31

DYNSUB: A high fidelity coupled code system for the evaluation of local safety parameters – Part II: Comparison of different temporal schemes

Armando Miguel Gomez-Torres, Victor Hugo Sanchez-Espinoza, Kostadin Ivanov, Rafael Macian-Juan

Journal:

Annals of Nuclear Energy

Year:

2012

Language:

english

File:

PDF, 1012 KB

english, 2012

32

Multi-scale uncertainty and sensitivity analysis of the TALL-3D experiment

Geffray, Clotaire, Macián-Juan, Rafael

Journal:

Nuclear Engineering and Design

Year:

2015

Language:

english

File:

PDF, 2.49 MB

english, 2015

33

High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW

Daeubler, Miriam, Ivanov, Aleksandar, Sjenitzer, Bart L., Sanchez, Victor, Stieglitz, Robert, Macian-Juan, Rafael

Journal:

Annals of Nuclear Energy

Year:

2015

Language:

english

File:

PDF, 5.90 MB

english, 2015

34

[ASME 2013 21st International Conference on Nuclear Engineering - Chengdu, China (Monday 29 July 2013)] Volume 4: Thermal Hydraulics - Validation of a Hybrid Surface Renewal Theory Based HTC Model for the Simulation of Condensation Induced Water Hammer

Ceuca, Sabin Cristian, Macián-Juan, Rafael

Year:

2013

Language:

english

File:

PDF, 1.31 MB

english, 2013

35

Integration of the subchannel thermal-hydraulic code SubChanFlow into the reactor dynamics code PARCS: Development and testing based on a computational benchmark

Basualdo, Joaquín R., Sánchez-Espinoza, Victor, Stieglitz, Robert, Macián-Juan, Rafael

Journal:

Progress in Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 3.45 MB

english, 2019

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