Conference Agenda

Study of the Operation of a Passive Heat Removal System on a Light Water Small Modular Reactor with the ASTEC V3.1.2 Code

Julie-Anne Zambaux¹, Zhexi Guo², Sicong Xiao²

1: Autorité de Sûreté Nucléaire et Radioprotection (ASNR), France; 2: Singapore Nuclear Research and Safety Institute (SNRSI), Singapore

Experimental and Numerical analysis on Safety Condenser Transient Performance based on P1.2 Experiments at the PKL Facility

Ignacio Gomez-Garcia-Torano¹, Maxime Vernassiere¹, Simon Schollenberger², Lars Dennhardt², Andreas Wielenberg³, Sebastian Buchhlotz³, Massimiliano Polidori⁴, František Lahovský⁵, Omar Sharief Al-Yahia⁶, Michaël Montout⁷

1: Commissariat à l'énergie atomique et aux énergies alternatives (CEA), France; 2: Framatome GmbH, Germany; 3: Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany; 4: Agenzia Nazionale per le Nuove Tecnologie, l'Energia e lo Sviluppo Economico Sostenibile (ENEA), Italy; 5: Nuclear Research Institute Řež (UJV), Switzerland; 6: Paul Scherrer Institut (PSI), Switzerland; 7: Electricité de France (EdF), France

Reliability Assessment of the BWRX-300 Passive Isolation Condenser System: Addressing Uncertainties in Two-Phase Natural Circulation Flow Modeling

Graeme Trundle¹, Sergey Galushin², Sean Roshan¹, Sevostian Bechta¹, Michael Söderström³, Anders Olsson²

1: Royal Institute of Technology (KTH), Sweden; 2: Vysus Group, Sweden; 3: Vattenfall AB, Sweden

Numerical Study on Steady-State Characteristics of Two-Phase Loop Thermosiphon in a Novel Small Modular Reactor

Xubin Wu, Wentao Hao, Wenwen Zhang, Zhenlei Liu, Weihua Li, Xingtuan Yang

Institute of Nuclear and New Energy Technology, Tsinghua University, China, People's Republic of

Update on Standard Wall Modeled Large Eddy Simulation on a Few Validation Test-cases

Jean-François Wald¹, Leo Deperne¹, Luc Bertolotti¹, Samuel Gaucher¹, Clément Colas¹, Sofiane Benhamadouche^1,2

1: EDF R&D, France; 2: CEREA, France

Wall-resolved LES for Predicting Turbulent Flow through Tube Bundles

Sofiane Benhamadouche

EDF R&D, France

Investigation of Pool and Containment Thermalhydraulic Behavior Using the 3D Module of CATHARE-3

Ignacio Gomez-Garcia-Torano¹, Christophe Bourcier¹, Julie-Anne Zambaux², Jeremy Bittan³

1: Commissariat à l'énergie atomique et aux énergies alternatives (CEA), France; 2: Institut de Radioprotection et de Sûreté Nucléaire (IRSN), France; 3: Electricité de France (EdF), France

Study of Flow Distribution of High Power Density Plate-Type PWR by Two-Phase Neutronics-Thermohydraulics Coupling Code

Guodong Liu¹, Ying He¹, Junren Hou¹, Meiming Qiu¹, Xingyu Zhao¹, Shanfang Huang¹, Kan Wang¹, Zhigang Li^2,3, Chuan Lu^2,3

1: Tsinghua University,China, People's Republic of; 2: Nuclear Power Institute of China, China, People's Republic of; 3: National Key Laboratory of Nuclear Reactor Technology, China, People's Republic of

Prediction of Multiphase Flow and Flow-induced Forces in a Cross-flow Tube Bundle with a Morphology-adaptive CFD Model

Marco Colombo¹, Daniele Vivaldi²

1: University of Sheffield, United Kingdom; 2: Autorité de Sûreté Nucléaire et de Radioprotection (ASNR), France

Modeling a Flexible Operation Scenario in a KWU-PWR Reactor using RELAP5/PARCS

Bárbara Navarro¹, Teresa Barrachina¹, Rafael Miró¹, Gumersindo Verdú¹, Marina García-Fenoll², José María Posada²

1: Universitat Politècnica de València, Spain; 2: Centrales Nucleares Almaraz-Trillo (CNAT), Spain

Multiscale Modelling of Forced-to-natural Circulation Experiments in Heavy Liquid Metal Test Loop NACIE

Andrea Pucciarelli¹, Pietro Stefanini¹, Ossama Halim¹, Nicola Forgione¹, Rajendrakumar Murugesan², Natesan Kumaresan², Amit Kumar Chauhan², Dhrumil Ganatra², Mohammed Muaaz Mohamed Dilshad Hussain³, Fajar Pangukir³, Akshat Mathur³, Pietro Cioli Puviani⁴, Tommaso Del Moro⁵, Dalin Zhang⁶, Yixin Zhang⁶, Vladimir Kriventsev⁷, Ivan di Piazza⁸

1: University of Pisa, Italy; 2: IGCAR, India; 3: NRG, Netherlands, The; 4: Politecnico di Torino / ENEA, Italy; 5: Sapienza University of Rome / ENEA, Italy; 6: Xi'an Jiaotong University, China, People's Republic of; 7: IAEA; 8: ENEA Brasimone Research Centre, Italy

Development of Risk Profile for Accident Sequences based on Source Term Analysis

Yunho Kim, Jaehyun Cho

Chung-Ang University, Korea, Republic of

ASNR’s Approaches to Thermal-hydraulics Support Studies for Probabilistic Safety Assessments for French Nuclear Power Plants and Other Facilities

Kimlee Bourgeois, Felix Thomann, Nadia Rahni, Guillaume Kioseyian, Gabriel Georgescu, Emmanuel Raimond

French Authority for Nuclear Safety and Radiation Protection (ASNR), France

Identification of Failure Domain Boundaries of Nuclear Passive Safety System Using Genetic Algorithm

Xicheng Wang, Aleksander Kipiela, Dmitry Grishchenko, Pavel Kudinov

Division of Nuclear Science and Engineering, Royal Institute of Technology (KTH), Sweden

Identifying and Prioritizing Knowledge Gaps for the Safe Deployment of Advanced Technology Small Modular Reactors

Cole Nathaniel Takasugi¹, Peter Yarsky¹, Piyush Sabharwall²

1: United States Nuclear Regulatory Commission, United States of America; 2: Idaho National Laboratory, United States of America

Application of an FSI Approach based on Structural Reduced-order Model for the Analysis of Flow-induced Vibrations in Nuclear Power Plants

Angel Aleksandrov Papukchiev, Hemish Mistry

Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany

High Resolution Fluid Structure Interaction Simulation of the GOKSTAD Tube Bundle

Trevor C. Franklin, Lane B. Carasik

Virginia Commonwealth University, United States of America

Flow-Induced Vibrations Simulations involving Structural Contact

Kevin Zwijsen, Ferry Roelofs

NRG PALLAS, Netherlands, The

Numerical Analysis of Flow-Induced Vibrations in Turbulent Two-Phase Cross-Flows Using a Two-Fluid Approach

Sina Tajfirooz, Kevin Zwijsen, Victor Habiyaremye, Edo Frederix, Ferry Roelofs

Nuclear Research and Consultancy Group (NRG), Netherlands, The

Vibration Analysis of a Rotating Propeller in Lead-Bismuth Eutectic through Fluid-Structure Interaction Simulation

Kamiel Ceusters^1,3, Mikhail Iarmonov¹, Kirill Makhov¹, Julio Pacio¹, Tom Verstraete², Joris Degroote³

1: Belgian Nuclear Research Centre (SCK CEN), Belgium; 2: Von Karman Institute for Fluid Dynamics (VKI), Belgium; 3: Ghent University, Belgium

Results from the New GOKSTAD Water Loop Facility for Fluid-Structure-Interaction Studies

Philippe Planquart, Muhsin Can Akkurt, Mathieu Delsipee, Lilla Koloszar

von Karman Institute, Belgium

Development of Transient Heat Pipe Reactor Modeling Capabilities in a Fully-implicit Solution Framework

Kaiyuan Zhu, Guojun Hu

University of Science and Technology of China, China, People's Republic of

Impact of Void Distribution Resolution on Neutronics in Plate-type Reactors with RMC

Ying He, Yongtang Wang, Guodong Liu, Shanfang Huang, Kan Wang

Tsinghua University, China, People's Republic of

Study on Brayton Cycle Start-up and Load Tracking Operation Characteristics of Heat Pipe Reactors

Xufan Han, Li Ge, Jianqiang Shan

Xi’an Jiaotong University, China, People's Republic of

Transient Response of Screen Wick Heat Pipes to Pulsed Dryout Conditions

Trevor Alan Melsheimer, Hansol Kim, Joseph Seo, Yassin Hassan

Texas A&M University, United States of America

Composite Wick Heat Pipe Design for High Power Experiments with Comparison to Past Experiments

Scout Bucks, Chris Balbier, Saya Lee

The Pennsylvania State Univeristy, United States of America

Parametric Experiment and Modeling Analysis of Geyser Boiling Phenomena in Sodium Heat Pipes

Zilin Su, Zeguang Li*, Huifu Wang, Dacai Zhang, Henglong Lin

Tsinghua University, China, People's Republic of

Towards a new NEA Framework for Advanced Thermalhydraulic Experiments for Nuclear Analysis and Safety Application (ATHENA)

Didier Jacquemain¹, Martina Adorni¹, Joelle Fleurot²

1: OECD NEA; 2: ASNR

Addressing Future Challenges on Analysis and Management of Accidents by International Cooperation: The Working Group on the Analysis and Management of Accidents (WGAMA)

Hideo Nakamura¹, Ahmed Bentaib², Martina Adorni³, Fulvio Mascari⁴, Pierre Ruyer⁵, Jinzhao Zhang⁶

1: Japan Atomic Energy Agency (JAEA), Japan; 2: Institut de Radioprotection et de Sureté Nucléaire (IRSN), France; 3: OECD Nuclear Energy (NEA); 4: National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA), Italy; 5: Autorité de sûreté nucléaire et de radioprotection (ASNR), France; 6: Tractebel (ENGIE), Belgium

NEA ETHARINUS Project: A Flagship Project Relevant to Thermal-Hydraulic Safety Analysis Issues

David Pialla¹, Joakim Holmstrom², Anis Bousbia Salah³, Martina Adorni⁴, Amina Younsi⁵, Sofia Carnevali⁶, Vesa Riikonen⁷, Simon Schollenberger⁸

1: EDF, France; 2: VATTENFALL-Ringhals AB, Sweden; 3: BEL V - Nuclear Safety and Analysis, Belgium; 4: OECD Nuclear Energy Agency, France; 5: ASNR, France; 6: Université Paris-Saclay, CEA, France; 7: LUT University, Finland; 8: Framatome, Germany

Key Outcomes of Recent NEA Nuclear Safety Joint Projects in Thermal-Hydraulics

Didier Jacquemain¹, Martina Adorni¹, Sangmin Lee¹, Markus Beilmann¹, Simon Philipp Shollenberger², Vesa Riikonen³, Jordi Freixa⁴, Kyoung-Ho Kang⁵, Miguel Sanchez Perea⁶, Sanjeev Gupta⁷, Martin Freitag⁷, Domenico Paladino⁸

1: OECD Nuclear Energy (NEA), France; 2: Framatome, Germany; 3: LUT University, Finland; 4: Universitat Politecnica de Catalunya, Spain; 5: Korea Atomic Energy Research Institute, Korea, Republic of; 6: Consejo de Seguridad Nuclear (CSN), Spain; 7: Becker Technologies GmbH, Germany; 8: PSI, Switwerland

Sodium Heat Pipe under Pulsed Power near Operation Limits

Pablo Diaz Gomez Maqueo, Reilly MacCoy, Rory McGrath, Chukwudi Azih

Canadian Nuclear Laboratories, Canada

Development of a High-Temperature Heat Pipe Simulation Module for the Thermal Hydraulic System Code AC²/ATHLET: Laminar Vapor Flow Modeling

Daniel Eckert¹, Philipp Schöffel¹, Fabian Weyermann¹, Andreas Schaffrath¹, Jörg Starflinger²

1: Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Germany; 2: Institute of Nuclear Technology and Energy Systems (IKE), University of Stuttgart, Germany

Parametric Optimization of Heat Pipe Design for Enhanced Thermal Performance Using Genetic Algorithm

Linjie Xu, Panhe Ge, Gu Hu

China Institute of Atomic Energy, China, People's Republic of

A Flexible Coupling Approach for Heat Pipe Microreactor Analysis

Mario A. Ponce Tovar^1,2, Cynthia Camila Güttlein^1,3, Ivor David Clifford¹, Alexey Cherezov¹, Hakim Ferroukhi¹

1: Paul Scherrer Institut, Switzerland; 2: Eidgenössische Technische Hochschule Zürich (ETH Zurich), Switzerland; 3: École Polytechnique Fédérale de Lausanne (EPFL), Switzerland

Neutronics and Planned Coupled Neutronics-Thermal hydraulics Simulations of a Heat Pipe Cooled MMR Core

Norman Dünne¹, Jeremy Bousquet¹, Andreas Wielenberg¹, Andreas Schaffrath¹, Jörg Starflinger²

1: Gesellschaft für Anlagen- und Reaktorsicherheit (GRS), Germany; 2: University of Stuttgart, Germany

Design Study to Develop an Experimental Facility for a Microreactor Process Heat Application: Cement Calcination

Scout Bucks¹, Ama Dahanayake¹, Erik Hisahara¹, Martin Nieto-Perez¹, Saya Lee¹, Sola Talabi², Sathish Krishnamoorthy³

1: The Pennsylvania State Univeristy, United States of America; 2: Pittsburgh Technical, United States of America; 3: Nazareth Cement Plant, Heidelberg Materials US Inc., United States of America

Test Results of an HTSE Experimental Facility Integrating with a Helium Loop for Low Carbon Hydrogen Production

In-Woo Son, Sin-Yeob Kim, Sung-Deok Hong, Byung-Ha Park, Chan-Soo Kim

Korea Atomic Energy Research Institute, Korea, Republic of

NuScale Integrated Energy System for Petrochemical Plant Emissions Reduction

Jose Reyes, Luis DePavia, John Swanson

NuScale Power, United States of America

Performance Analysis of the Nuclear-powered IECT Propulsion System

Hangqian Liu^1,2, Ao Zhang¹, Xiang Wang*¹

1: Harbin Engineering University, China, People's Republic of; 2: University of Science and Technology of China, China, People's Republic of

Multi-objective Decisions on Integrated Energy Systems Planning and Operation for Industrial Combined Heat and Power Supply

So-Bin Cho^1,2, Junyung Kim¹, Václav Novotný¹, Rami M. Saeed¹, Todd Allen², Xiaodong Sun²

1: Idaho National Laboratory, United States of America; 2: University of Michigan, United States of America

A Realistic Metric for Latent Heat Thermal Energy Storage Systems to be Paired with Advanced Reactors

Beau Walsh, Guanyu Su

UC Berkeley, United States of America

The IAEA Benchmark on Transition from Forced to Natural Circulation with NACIE Heavy Liquid Metal Loop

Ivan Di Piazza¹, L. Ren², X. Xu², R. Zhang³, H. Li³, D. Zhang³, A. Batta⁴, A.G. Class⁴, M. Rajendrakumar⁵, A.K. Chauhan⁵, G. Dhrumil⁵, K. Natesan⁵, D. Martelli¹, P. Lorusso¹, F. Lodi¹, P. Cioli Puviani¹, T. Del Moro¹, R. Da Vià¹, M. Tarantino¹, F. Giannetti⁶, C. Ciurlini⁶, G. Caruso⁶, B. Calgaro⁷, K. Zeng⁸, P. Stefanini⁹, A. Pucciarelli⁹, N. Forgione⁹, O. Abedelhalim⁹, J. Han¹⁰, Y. Jung¹⁰, B. Ha Park¹⁰, F. Roelofs¹¹, M.M.M.D. Hussain¹¹, F. Pangukir¹¹, A. Mathur¹¹, D. Dupleac¹², M. Mladin¹³, C. Dobrinoiu¹³, A. Baisov¹⁴, A. Zalesov¹⁴, I. Aulov¹⁴, A. Vlasenko¹⁵, E. Moiseenko¹⁵, O. Ilyasova¹⁵, N. Mosunova¹⁵, V. Vereshchagin¹⁶, A. Ekimov¹⁶, A. Moiseev¹⁶, K. Sergeenko¹⁶, L. Golibrodo¹⁶, A. Krutikov¹⁶, A. Zefirova¹⁶, E. Biiushkina¹⁶, K. Mikityuk¹⁷, D. Shaver¹⁸, A. Moisseytsev¹⁸, J. Liao¹⁹, N. Virgili²⁰, V. Kriventsev²⁰

1: ENEA, Italy; 2: CIAE, China, People's Republic of; 3: XJTU, China, People's Republic of; 4: KIT, Germany; 5: IGCAR, India; 6: UniRoma La Sapienza, Italy; 7: Newcleo, Italy; 8: NINE, Italy; 9: UniPi, Italy; 10: KAERI, Korea, Republic of; 11: NRG, Netherlands; 12: PUB, Romania; 13: RATEN ICN, Romania; 14: Gidropress, Russian Federation; 15: IBRAE RAN, Russian Federation; 16: NIKIET, Russian Federation; 17: PSI, Switzerland; 18: ANL, United States of America; 19: Westinghouse, United States of America; 20: IAEA, Austria

CFD Validation on Liquid Metal Flow in 19 Wire Wrapped Bundle Flow Investigated in the IAEA Coordinated Research Project CRP-I31038 Using NACIE Experimental Data

Abdalla Batta, Andreas G. Class

Karlsruher Institut für Technologie (KIT), Germany

CFD Benchmark for Non-uniform Heating Experiments in NACIE Rod Bundle

Akshat Mathur¹, Konstantin Sergeenko^2,3, Ivan Di Piazza⁴, Vladimir Kriventsev⁵, Ming Jin⁶, Shize Ouyang⁶, Danna Zhou⁶, Haoyang Li⁷, Dalin Zhang⁷, Abdalla Batta⁸, Andreas G. Class⁸, Aleksander Grah⁹, Roberto Da Vià⁴, Pietro Cioli Puviani^4,10, Andrea Pucciarelli¹¹, Ossama Halim¹¹, Yohan Jung¹², Ferry Roelofs¹, Dhrumil Ganatra¹³, Amit Kumar Chauhan¹³, Rajendrakumar Murugesan¹³, Natesan Kumaresan¹³, Andrei Moiseev², Luka Golibrodo^2,3, Alexey Krutikov^2,3, Anna Zefirova²

1: NRG, Netherlands, The; 2: NIKIET, Russian Federation; 3: JSC PRORYV, Russian Federation; 4: ENEA, Italy; 5: IAEA, Austria; 6: IANS, China, People's Republic of; 7: Xi'an Jiaotong University, China, People's Republic of; 8: KIT-ITES, Germany; 9: JRC, European Commission; 10: Politecnico di Torino, Italy; 11: University of Pisa, Italy; 12: KAERI, Korea, Republic of; 13: IGCAR, India

Development and Testing of High-Temperature Heat Pipes for Micro Modular Reactors: Initial Findings from the MISHA Project

Ruggero Meucci, Rudi Kulenovic, Jörg Starflinger

Universität Stuttgart - Institute for Nuclear Energy and Energy Systems, Germany

Strategic Collaboration between CNL and KAERI on Small Modular Reactor Safety Thermal-Hydraulics

Sun-Kyu Yang¹, Robert Bowden¹, Penny Neal¹, Andrew Morreale¹, Ali Siddiqui¹, Kyoung-Ho Kang², Ki-Yong Choi²

1: Canadian Nuclear Laboratories, Canada; 2: Korea Atomic Energy Research Institute, Korea, Republic of

CFD Analysis of CHF Characteristics in Vertical and Inclined Tubes

Yujiao Peng, Huanjun Kong, Ya Li, Jianqiang Shan, Miao Gui

Xi'an Jiaotong University, China, People's Republic of

Evaluation of Rod-Bundle Critical Heat Flux using MARS-KS Subchannel Analysis

Nhan Hien Hoang¹, Seong-Su Jeon¹, Jehee Lee¹, Ju-Yeop Park²

1: FNC Technology, CO., LTD., Korea, Republic of; 2: Korea Institute of Nuclear Safety, Korea, Republic of

Assessment of CTF Performance against Critical Heat Flux Rod Bundle Database

Vinicius de Melo Monteiro, Juliana Pacheco Duarte

University of Wisconsin-Madison, United States of America

Assessment of CTF for Steady-state and Transient Post-CHF Conditions

Robert K Salko, Vineet Kumar, Nathan A Capps

Oak Ridge National Laboratory, United States of America

Uncertainity Quantification and Model Improvement in CTF for Dryout and Reflood Models

Vineet Kumar, William Gurecky, Robert Salko

Oak Ridge National Laboratory, United States of America

Multi-field Simulations of Liquid Film Dryout in Rod Bundle Geometry

Cole Jacob Dunbar¹, Roman William Morse², Jean Marie Le Corre³, Juliana Pacheco Duarte¹

1: University of Wisconsin-Madison, United States of America; 2: Massachusetts Institute of Technology, United States of America; 3: Westinghouse Electric Sweden AB, Sweden

Hydrogen Production by Steam Reforming Technology Using HTGR or SMR

Huang Zhang, Chengye Wu, Zhiyi Peng, Junyi Wang, Huaqiang Yin

Tsinghua University, China, People's Republic of

Evaluating Hydrogen Production by Electrolysis Coupled with Passive Molten Fast Salt Reactor (PMFR)

Jihun Im¹, Jae Hyung Park¹, Seungmin Lee¹, JinHo Song¹, Sung Joong Kim^1,2

1: Department of Nuclear Engineering, Hanyang University, Korea, Republic of; 2: Institute of Nano Science & Technology, Hanyang University, Korea, Republic of

Development and Analysis of the ARC Fusion Reactor Integrated Solar-based Energy System: Both Electrical and Non-electrical Applications for Hydrogen Production and Desalination

Sulenur Asal, Adem Acir

Gazi University, Turkiye

Experimental Thermal Performance Evaluation of a Sodium Heat Pipe Assembly for Space Nuclear Reactors

Sin-Yeob Kim, Byung-Ha Park, In-Woo Son, Chan-Soo Kim

Korea Atomic Energy Research Institute, Korea, Republic of

Re-entry Thermal Testing for Nuclear-Powered Thermoelectric Generators in Space Using 0.4MW Plasma Jet Facility

Moon Won Song, Philyong Oh, Gunwoo Choi

Jeonbuk National University, Korea, Republic of

Multiphysics Coupling Simulation and Output Characteristics Analysis of Thermionic Space Reactor TOPAZ-II

Jianwei Wang, Xufan Han, Li Ge, Jianqiang Shan

Xi’an Jiaotong University, China, People's Republic of

Boiling Water Reactor Core Stability Analysis: Modeling of Out-of-Phase Oscillations using TRACEv5p9/PARCSv3.4.3

Bárbara Navarro, Teresa Barrachina, Rafael Miró, Gumersindo Verdú

Universitat Politècnica de València, Spain

Experimental Investigation of Heaving Motion Effect on Flow Boiling CHF with Axially Cosine-shaped Power Profile Heater

Ja Hyun Ku¹, Heepyo Hong¹, Hyukjae Ko¹, Gi Won Bae¹, Jin-Seong Yoo², Goon-Cherl Park¹, Hyoung Kyu Cho¹

1: Seoul National University, Korea, Republic of; 2: ETH Zürich, Switzerland

Study on the Performance of Improved Gyroid TPMS Structure Heat Exchanger

Nailiang Zhuang, Yangyang Li, Qiqian Zhai, Xiaopeng Zhao, Hangbin Zhao

Nanjing University of Aeronautics and Astronuatics, China, People's Republic of

A Lagrangian-Lagrangian Elastic Body-Incompressible Flow Calculation Method (MPH-MPH) for Fluid-Deformable Structure Interaction

Ryo Yokoyama, Shuichiro Miwa, Koji Okamoto

The University of Tokyo, Japan

Surrogate-Based Multi-Objective Design Optimization of Tree-Shaped Fins with Uniform Branch End Distribution for Latent Heat Thermal Energy Storage

Hansol Kim, Joseph Seo, Yassin Hassan

Texas A&M University, United States of America

Thermal-hydraulic Analysis of Energy Storage and Intermediate Heat Transfer Systems for Tokamak Fusion Reactors

Francesco Colliva¹, Cristiano Ciurluini¹, Bruno Gonfiotti², Amelia Tincani², Fabio Giannetti¹

1: Sapienza University of Rome, Nuclear Engineering Research Group (NERG), Italy; 2: ENEA Brasimone Research Centre, Italy