final program - gmtrphytra4.gmtr.ma/wp-content/uploads/2018/09/program-phytra4-final-v012... ·...
TRANSCRIPT
Final Program 17 – 19 September 2018
Marrakech, Morocco
PHYTRA4 CONFERENCE
Organized in cooperation with
We would like to thank PHYTRA4 Sponsors:
Ministère de l'Energie, des Mines et du Développement
Durable
http://www.mem.gov.ma/
ANS (American Nuclear Society)
http://www.ans.org/
CEA (Commissariat à l’énergie atomique et aux énergies
alternatives, France)
http://www.cea.fr/
CNS (Canadian Nuclear Society)
https://www.cns-snc.ca/
International Nuclear SecurityEducation Network
http://iaea.org/
Radiation Safety Information Computational Center
RSICC
Computational Center
https://rsicc.ornl.gov/
University Ibn Tofaïl
Computational Center
http://www.uit.ac.ma/
Conference Honorary Chairs
K. EL MEDIOURI
CNESTEN Director General , Rabat, Morocco
&
K. MRABIT
Moroccan Regulatory Agency (AMSSNuR)
DirectorGeneral , Rabat Morocco
Conference General Chairs
Pr. L. ERRADI, GMTR President Mohammed V University
Faculty of sciences, Departement of Physics, Rabat
Pr. J. TAJMOUATI,GMTR Vice President
University Sidi Mohamed Ben Abdellah, Fez
Faculty of sciences
Conference Co-Chairs
Pr. T. El Bardouni
University A. Essaadi, Tetouan
Faculty of sciences
Organizing committee
Chairman: Pr. E. CHAKIR
Faculty of Sciences; University Ibn Tofaïl, Kénitra
L. Erradi(Univ. Mohamed V Agdal, Rabat)
J. Tajmouati(Univ. Sidi Md Ben Abdellah, Fez )
A. Jibre(CNESTEN, Rabat)
T. Elkhoukhi(CNESTEN, Rabat)
O. Elhajjaji(Univ. A. Essaadi, Tetouan)
T. El Bardouni(Univ. A. Essaadi, Tetouan)
A. Chetaine(Univ Mohamed V Agdal, Rabat)
E. Chakir(Univ. Ibn Tofaïl, Kenitra )
A. Maghnouj(Univ. Sidi Md B. Abdllah, Fez)
A. Hassini(Univ. Hassan II Ain Chok, Casablanca )
M.Azougagh (ISPITS, RABAT)
A. Guessous(Univ. I. Tofaïl, Kénitra)
E. Alibrahim(Univ. A. Essaadi, Tetouan)
A. Kharchaf(Univ. Ibn Tofaïl, Kenitra)
O. K. Bouhelal(ENIM, Rabat)
T. Marfak(AMSSNuR, Rabat)
B.Nacir (CNESTEN, Rabat)
A. Htet(CNESTEN, Rabat )
H. Boukhal(Univ. A. Essaadi, Tetouan)
M. Azahra(Univ. A. Essaadi, Tetouan)
H. Amsil(CNESTEN, Rabat)
N. Guessous(ENS, Fez)
A. Hajjani(M EMEE, Rabat)
A. Sekkouri(ONEE, Casablanca)
A. Dadouch(Univ. SidiMd B. Abdllah, Fez )
INTERNATIONAL TECHNICAL PROGRAM
COMMITTEE
Chairman: Pr. F. Rahnema
Georgia Institute of Technology, USA
Co-Chair Pr. A. Santamarina
(CEA/ Cadarache), FRANCE
P. Reuss (France) D. Greneche (France)
A. Trkov (Slovenia) F. Leszczynski (Argentina)
S. Dulla (Italy) A. Kharchaf (Morocco)
Y. Y. Azmy (USA) N. Laletin (Russia)
T. El Bardouni (Morocco) J. J. Lautard (France)
R. Sanchez (France) A. Zaetta (France)
A. M. Ougouag (USA) R. J. Ellis (USA)
A. Hébert (Canada) J. Tajmouati (Morocco)
P. Ravetto (Italy) H. Sekimoto (Japan)
R. Chawla (Switzerland) M. Tazi (Morocco)
B. Rouben (Canada) A. Chetaine (Morocco)
L. Erradi (Morocco) L. C. Leal (France)
M. Ouisloumen (USA) B. Petrovic (USA)
O. K. Bouhelal (Morocco) A. Htet (Morocco)
H. Boeck (Austria) A. Hassini (Morocco)
A. Santamarina (France) D. Bernard (France)
A. R. Haghighat (USA) P. Fougeras (France)
F. Sefidvash (Brazil) D. Zhang (USA)
J. Razvi (USA) M. Coste (France)
E. Chakir (Morocco) J. C. Bosq (France)
C.M. Diop (France) O. El Hajjaji (Morocco)
Y. Shimazu (Japan) A. Chabre (France)
I. Toumi (France) N. Guessous (Morocco)
K. Kozier (Canada) L. Vanhoenacker (Belgium)
A. Lyoussi (France) A. Maghnouj (Morocco)
G. Marleau (Canada) E. Akaho (Ghana)
M. Dahmani (Canada) A. Boufraqech (Morocco)
I. Zmijarevic (France) H. boukhal (Morocco)
C. Jouanne (France) T. Elkhoukhi (Morocco)
E. Dumonteil (France) M. Boubcher (Canada))
F. Rahnema (USA) P. Blaise (France)
S. Dababneh (Jordan) J-F. Vidal (France)
G. Verdu (Spain) J. Rodenas (Spain)
C. Ahnert (Spain) S. B. Grover (USA)
T. E. Valentine (USA) H. Mcfarlane (USA)
E. Varin (Canada) L. Sklenka (CzechRepublic)
R. Barros (Brazil) A. Hawari (USA)
A. Dadouch (Morocco) R. Barros (Brazil)
M. Azougagh (Morocco) B. Nacir (Morocco)
Daily Schedule
Sunday Monday Tuesday Wednesday
8h00-9h00
Registration
SS3 (Menara)
SS2 (Koutoubia)
RS1 (Menara)
SS5 (Koutoubia)
9h00-10h00
Opening (Agdal)
10h00-10h20 Coffee break Coffee break Coffee break
10h20-11h40
Plenary sessions (Agdal)
Session 1: from10h30 to 11h30
& Session 2: from11h30 to 12h30
RS3 (Menara)
SS2 (Koutoubia)
RS4 (Menara)
SS5 (Koutoubia)
11h40-12h30 Poster session 1 Poster session 2
12h30-14h00 Lunch
14h00-15h40
Re
gist
rati
on
SS1 (Menara)
SS2 (Koutoubia)
3RS (Menara)
SS4 (Koutoubia)
MRT & RAPID Workshop
(Menara)
15h40-16h00 Coffee break
16h00-17h40
SS1 (Menara)
SS2 (Koutoubia)
RS3 (Menara)
SS4 (Koutoubia)
MRT & RAPID Workshop
(Menara)
17h40-19h00 Closing: from17h00 to
18h00 (Agdal)
Welcome Reception 18h40-21h30 Gala Dinner
Special Sessions
SS 1 Nuclear Data Development and Application – Luiz Leal (IRSN,
France) andDavid Bernard (CEA/Cadarache – France)4T5
SS 2
Advanced Radiation Transport and Reactor Physics Methods –
FarzadRahnema (Georgia Tech – USA), PieroRavetto(Politecnico di Torino – Italy), and Ali Haghighat (Virginia Tech – USA)
SS 3
Code Verification and Validation – Integral experiments and
Uncertainty Quantification – Alain Santamarina and Jean-François
Vidal (CEA/Cadarache – France)
SS 4
Molten Salt Reactors (MSR) Research and Technology – Sandra
Dulla (Politecnico di Torino, Italy)
SS 5 New Developments in Core Design & Safety Analyses
Methodologies – Power Reactors. – Kostadin N. Ivanov (NCSU,
USA) and Mohamed Ouisloumen (Westinghouse, USA)
Regular sessions
RS 1 Reactor Thermal-Hydraulics
RS 3
Reactor physics theory and practice- P. Reuss (INSTN -
Saclay/France)
RS 4 Research Reactor utilization
Full Program
Sunday, September 16
Registration&
Opening
Ceremony
Registration
Time:14h00 to 18h30 Welcome Reception
Time:19h00 to 20h30
Monday, September 17
Registration
Time: 8h00 to 9h00 Opening Ceremony Time: 9h00 to 10h00
Coffee break
Plenary Session 1
Chairs:Pr. L. Erradi& Pr. F. Rahnema, Location: Agdal Room time: 10h30 to 11h30
Plenary
Sessions
Speaker 1 : Mr. Shah Nawaz Ahmad, (WNA S. A. for India, Middle East & South East Asia) Title: Nuclear Power in a Low Carbon Economy
Speaker 2: Mr. SATO DAISUKE (Engineering Manager at MHI LTD., Japan) Title: An Overview of PWR Reactor Cores Design focusing on MHI Experience
Speaker 3: Dr. Abderrafi M. OUGOUAG (INL, USA) Title: Methods for Neutronics of High Temperature Reactors: Drivers, Recent Progress at INL, and Outstanding Problems
Plenary Session 2 Chairs: Pr. J. Tajmouati & Pr. T. Elbardouni Location: Agdal Room Time: 11H30 to 12H30 Speaker 1: Bouzekri NACIR (CNESTEN, Morocco) Title: The Role of the Moroccan Nuclear Research Center in the development of the national infrastructure required for a NPP Speaker 2: Ms. Bouchra BOUSTANI (AMSSNuR, Morocco) Title: Current National Legislative and Regulatory Framework for Nuclear Safety and Security Speaker 3: MEMDD representative (MEMDD, Morocco) Title: The national energy strategy and particularly in terms of electricity generation
lunch Special Session1: Nuclear Data Development and Application
Chair:Frederic FERNEX(IRSN, France) - co-chair: T. El Bardouni (Univ. A. Essaadi, Tetouan)
Location: Menara Room
14h00-14h20 REACTOR NOISE AT HIGH FREQUENCIES AND
SUBCRITICAL REACTIVITY INFERENCE Adimirdos Santos, Diogo Feliciano dos Santos, Gregorio Soares de
sourza and Cesar DominguesLoureiro
PHYTRA4-SS1-001
14h20-14h40 ON A MEASUREMENT APPROACH TO SUPPORT
EVALUATION OF THERMAL SCATTERING LAW DATA Ayman Hawari
PHYTRA4-SS1-002
14h40-15h00 NUCLEAR DATA SENSITIVITY AND UNCERTAINTY
ANALYSIS FOR GADOLINIUM-BEARING FUEL ASSEMBLIES
AND RECENT NEW MEASUREMENTS OF GADOLINIUM ODD-
ISOTOPES NEUTRON CAPTURE CROSS SECTIONS
Federico Rocchi, Antonio Guglielmelli, Patirizio Console Camprini,
CritianMassimi and Luiz Leal
PHYTRA4-SS1-004
15h00-15h20 THE SPECTRUM - AVERAGED CROSS SECTION
INVESTIGATION OF SELECTED NEUTRON INDUCED
REACTIONS IN 252CF FIELD
Jan Simon, Martin Schulc, Michal Kost'al, Roberto Capote, Nicola
Burianova, Evzen Novak and Jiri M. Maly
PHYTRA4-SS1-005
Special Session 2: Advanced Radiation Transport and Reactor Physics Methods
Chair:Will Walters (PSU, USA) ; co-chair: A. Kharchaf (Univ. Ibn Toufayl, Kenitra)
Location: Koutoubia Room
14h00-14h20 SCATTERING AND THE ENTROPY OF NEUTRON SLOWING
DOWN
B. Ganapol, D. Mostacci& V.Molinari
PHYTRA4-SS2-001
14h20-14h40 A COMPARISON OF TRANSPORT METHODS FOR THE
SOLUTION OF A PROBLEM WITH SHADOWING EFFECTS IN
SPHERICAL GEOMETRY
W. J. Vieira, A. D. Caldeira&R. D. M. Garcia
PHYTRA4-SS2-012
14h40-15h00 THE ADJOINT PROBLEM AS PHYSICAL HEURISTIC FOR
LOADING PATTERN OPTIMIZATION
Ella Israeli, Erez Gilad&PieroRavetto
PHYTRA4-SS2-004
15h00-15h20 FISSILE DISTRIBUTION AND THE CRITICAL PROBLEM OF A
NUCLEAR REACTOR: A MATHEMATICAL APPROACH
P. Saracco, N.Abrate, N.Chentre, S. Dulla, & P.Ravetto
PHYTRA4-SS2-008
15h20-15h40 CONSISTENT SPATIAL EXPANSION FUNCTIONS ON
HEXAGONAL SURFACES FOR COARSE MESH TRANSPORT
METHOD
Dingkang Zhangand FarzadRahnema
PHYTRA4-SS2-022
Coffee break Special Session1: Nuclear Data Development and Application
Chair:Federico Rocchi(ENEA, Italy) ; co-chair: E. Chakir (Univ. Ibn Toufayl, Kenitra)
Location: Menara Room
16h00-16h20 NUCLEAR DATA AND APPLICATIONS AT THE NUCLEAR
SAFETY AND RADIOPROTECTION INSTITUTE: ANALYSIS,
EVALUATION AND APPLICATION
L.Leal, N. Leclaire,F. Fernex, A. Jinaphanh& I.Duhamel
PHYTRA4-SS1-006
16h20-16h40 VALIDATION OF NUCLEAR DATA LIBRARIES FOR 16O IN
RESEARCH CENTRE REZ
Martin Schulca, Michal Kost'al, Evzen Novak, Jan Simon & Luiz Leal
PHYTRA4-SS1-008
16h40-17h00
THE REFERENCE NEUTRON FIELD FOR MEASUREMENT OF
SPECTR UM AVER A GED CROSS SECTIONS
Michal Kostal
PHYTRA4-SS1-009
17h00-17h20 EVALUATION OF THERMAL SCATTERING LAW FOR LIGHT
WATER BASED ON NEW TIME-OF-FLIGHT MEASUREMENTS
AT THE INSTITUT LAUE-LANGEVIN (ILL)
PHYTRA4-SS1-011
V. Jaiswal, L. Leal, N. Leclaire,F.Real & V.Vallet
17h20-17h40 THE BENCHMARKING OF SILICON FILTERED BEAM AT LVR-
15 REACTOR
V.Juříček, M. Košťál, M. Schulc, J. Šimon, E. Losa, V.Rypar, Z.
Matěj&F. Cvachovec
,
PHYTRA4-SS1-012
17h40-18h00 ANALYSIS OF FOUR SPERT-III RIA EXPERIMENTS WITH
NUCLEAR DATA UNCERTAINTY QUANTIFICATION USING
THREE DIFFERENT COVARIANCE MATRIX LIBRARIES
A. Dokhane, A.Vasiliev, D. Rochman, H.Ferroukhi&G.Grandi
PHYTRA4-SS3-001
Special Session 2: Advanced Radiation Transport and Reactor Physics Methods
Chair:PieroRavetto (Politecnico di Torino – Italy); co-chair: A. Chetaine (Univ Mohamed V , Rabat)
Location: Koutoubia Room
16h00-16h20 A QUADRATIC CHARACTERISTIC METHOD FOR THE SN
SOLUTION
Dean Wang, TseelmaaByambaakhuu&Kangyu Ren
PHYTRA4-SS2-003
16h20-16h40 ADVANCES IN THE ADO-NODAL METHOD FOR THE
SOLUTION OF PARTICLE TRANSPORT PROBLEMS IN TWO-
DIMENSIONAL MEDIA
Liliane B. Barichello, KarineRui& Cassio B. Pazinatto
PHYTRA4-SS2-005
16h40-17h00 A RAYLEIGH QUOTIENT METHOD FOR CRITICALITY
EIGENVALUE PROBLEMS IN NEUTRON TRANSPORT
M. I.Ortega,P. N.Brown, T. S. Bailey, ChangB. & R. N.Slaybaugh
PHYTRA4-SS2-007
17h00-17h20 A LOCAL FISSION MATRIX CORRECTION METHOD FOR
HETEROGENEOUS WHOLE CORE TRANSPORT WITH RAPID
William J. Walters&Donghao He
PHYTRA4-SS2-014
17h20-17h40 RAPID CODE FORMULATION, BENCHMARKING, AND ITS VRS
A. Haghighat, N.Roskoff, V.Mascolino&Meng-Jen Wang
PHYTRA4-SS2-018
Tuesday, September 18
Special Session 3: Code Verification and Validation – Integral experiments and Uncertainty Quantification
Chair: J. F. Vidal (CEA/Cadarache) ; co-chair: H. Boukhal (Univ. A. Essaadi, Tetouan)
Location: Menara Room
8h00-8h20 IMPACT OF THE SAMARIUM DEPLETION CHAIN MODELING PHYTRA4-SS3-007
IN A PWR EQUILIBIRUM CYCLE USING DRAGON AND
DONJON
Jean-jacquesIngremeau, Julien Taforeau, Geoffrey Tixier& Alain
Hébert
8h20-8h40 BEPU METHODOLOGY FOR THE VOID FRACTION
PREDICTION IN PWR FUEL BUNDLES VALIDATED WITH
THE PSBT BENCHMARK FOR STEADY STATE AND
TRANSIENT CASES Patricio Hidalga, Rafael Miró& Agustin Abarca
PHYTRA4-SS3-008
8h40-9h00 COMBINING THE TONE’S AND SUBGROUP MODELS FOR
REFERENCE LWR SELF-SHIELDING CALCULATIONS IN
APOLLO3®
J. F. Vidal& Damien Ranaud
PHYTRA4-SS3-009
9h00-9h20 UNCERTAINTY QUANTIFICATION OF THE SPND DYNAMIC
MODEL BASED ON NON-INTRUSIVE POLYNOMIAL CHAOS
METHOD
Xingjie Peng, Lei Lou, Yun Cai, Liangzi Wang, Yingrui Yu & Qing Li
PHYTRA4-SS3-010
9h20-9h40 ON UNCERTAINTY QUANTIFICATION OF ISOTOPIC
UNCERTAINTIES USING COMPUTATIONAL VERSUS DATA
DRIVEN APPROACHES
Majdi I. Radaideh, Dean Price & Tomasz Kozlowski
PHYTRA4-RS-005
9h40-10h00 RESEARCH OF MEASUREMENT CONDITION FOR A
REACTOR NOISE MEASUREMENT IN THE POWER
OPERATION OF KYOTO UNIVERSITY REACTOR, KUR Sin-ya Hohara, Kunihiro Nakajima, Atsushi Sakon, Kengo Hashimoto
&Tadafumi Sano
PHYTRA4-RS-029
Special Session 2: Advanced Radiation Transport and Reactor Physics Methods
Chair:AlirezaHaghighat (Virginia Tech, USA) ; co-chair: A. Maghnouj (Univ. SidiMd B. Abdllah, Fez)
Location: Koutoubia Room
8h00-8h20 A GLOBAL-LOCAL APPROACH FOR TIME-DEPENDENT
LATTICE HOMOGENIZATION
Peter Schwanke & Eleodor Nichita
PHYTRA4-SS2-009
8h20-8h40 ESTIMATION OF MONOENERGETIC NEUTRON SOURCE
DISTRIBUTION IN FUEL REGIONS FOR A PRESCRIBED POWER
DENSITY GENERATON IN SUBCRITICAL X-Y GEOMETRY
FISSION-CHAIN REACTING SYSTEMS
Leonardo R. C. Moraes, Hermes A. Filho&Ricardo C. Barros
PHYTRA4-SS2-010
8h40-9h00 A SIMPLIFIED SPACE-TIME MULTIPHYSICS MODEL FOR THE
CABRI CORE
Alain Hébert& Lucas Fede
PHYTRA4-SS3-002
9h00-9h20 DESIGN OF A SPECIAL CORE FOR LARGE GRAPHITE
INSERTION STUDIES IN THE LR-0 REACTOR
T. Czakoj, E.Losa& M.Košťál
PHYTRA4-SS3-005
9h20-9h40 ON THE PROMPT TIME EIGENVALUE ESTIMATION FOR
SUBCRITICAL MULTIPLYING SYSTEMS
N.Chentre, P.Saracco, S.Dulla& P.Ravetto
PHYTRA4-RS-013
9h40-10h00 METHODS OF SOLUTION FOR THE NEUTRON CHAIN
SURVIVAL PROBABILITY
Patrick F. O’Rourke &Anil K. Prinja
PHYTRA4-SS2-019
Coffee break Regular Session 3: Reactor physics theory and practice
Chair: A. Ougouag (INL, USA) ; co-chair: A. Hassini (Univ. Hassan Ii Ain Chok, Casablanca)
Location: Menara Room
10H20-10H40 VALKIN-FVM-Sn: 3D MODAL NEUTRON CODE WITH THE
FINITE VOLUME METHOD FOR THE DISCRETE ORDINATES
TRANSPORT EQUATION
A. Bernal, R.Miro, G. Verdu& J. E. Roman
PHYTRA4-RS-030
10h40-11h00 NEUTRONICS LIVENED UP BY COMPUTER
Paul Reuss
PHYTRA4-RS-014
11h00-11h20 IMPLEMENTATION OF THE MULTIGROUP TELEGRAPH BASED P1
APPROXIMATION AND COMPARISON TO THE MULTIGROUP
DIFFUSION BASED P1 APPROXIMATION IN GEN-FOAM
Jason Hou, M. RamzyAltahhan, Paolo Balestra&Maria Avramova
PHYTR4-SS4-009
11h20-11h40 C4P - TRAIN NEUTRONICS TOOL FOR SUPPORTING SAFETY
STUDIES OF INNOVATIVE FAST REACTORS
A. Rineiski& V.Sinitsa
PHYTR4-SS4-011
Special Session 2: Advanced Radiation Transport and Reactor Physics Methods Chair:FarzadRahnema (Georgia Tech – USA) ; co-chair: N. Guessous (ENS, Fez)
Location: Koutoubia Room
10H20-10H40 INCOMPLETE HOMOGENIZATION FOR EXPLICIT TREATMENT
OF BURNABLE POISONS, CONTROL RODS AND LOCALIZED PHYTRA4-SS2-023
STRONG HETEROGENEITIES
Jui-Yu Wang& Abderrafi Ougouag
10h40-11h00 STATUS AND NEW FEATURES OF THE HIGH-FIDELITY
REACTOR PHYSICS COMPUTATIONAL CODE NECP-X
Liangzhi Cao, Zhouyu Liu, Jun Chen, Chen Zhao, Qingmng He
&Hongchun Wu
PHYTR4-SS4-010
11h00-11h20 AN OPTIMAL COMPARISON BETWEEN R-Z AND HEX-Z
MODELS IN B&B NEUTRONICS CALCULATIONS
Chris Keckler,Massimiliano Fratoni& Ehud Greenspan
PHYTRA4-SS2-017
11h20-11h40 VALIDATION OF MOX CORE REACTIVITY VERSUS FLUX
VARIATION. FEEDBACK ON DELAYED NEUTRON DATA
A. Santamarina & J-F. Vidal
PHYTRA4-SS3-003
Poster session 1
Lunch Regular Session 3: Reactor physics theory and practice
Chair:A. Hébert (EPM, Canada) ; co-chair: O. K. Bouhelal (ENIM, Rabat)
Location: Menara Room
14h00-14h20 HIGH PERFORMANCE COMPUTING TECHNIQUES APPLIED TO
THE RESOLUTION OF THE NEUTRON DIFFUSION EQUATION
V. Vidal, F.Squillace, M. Chillaron Perez & G.Veru
PHYTRA4-SS2-021
14h20-14h40 STUDY OF NEUTRON TRANSPORT CALCULATION USING
ISOGEOMETRIC ANALYSIS METHOD
Riho Horita, W.F.G. Van Rooijen& Danny Lathouwers
PHYTRA4-SS2-011
14h40-15h00 THREE DIMENSIONAL SN NEUTRON TRANSPORT
CALCULATIONS WITH ISO-GEOMETRIC ANALYSIS (IGA)
W.F.G. van Rooijen&Riho Horita
PHYTRA4-SS2-013
15h00-15h20 n-DOTEC RESULTS FOR ANALYTICAL BENCHMARK 1D and
C5G7 BENCHMARK 2D
S. Moratóa, A. Bernala, Jose E. Romanb, R. Miróa& G. Verdú
PHYTRA4-SS2-015
15h20-15h40 A SEMI-ANALYTIC SOLUTION ON THE 1D SN TRANSPORT
EQUATION BY DECOUPLING THE IN-SCATTERING OPERATOR
Anderson English &Zeyun Wu
PHYTRA4-SS2-020
Special Session 4: Molten Salt Reactors (MSR) Research and Technology
Chairs:SandraDulla (Polito, Italy)& Jiri Krepel (PSI, Switzerland)
Location: Koutoubia Room 14h00-14h20 IDENTIFICATION AND STUDY OF INCIDENTAL AND
ACCIDENTAL SCENARIOS FOR THE MOLTEN SALT FAST
REACTOR
D. Gérardin, M. Allibert, D. Heuer, A. Laureau, J.Martinet & E.Merle
PHYTR4-SS4-002
14h20-14h40 FUEL CYCLE SUSTAINABILITY OF MOLTEN SALT
REACTOR CONCEPTS IN COMPARISON WITH OTHER
SELECTED REACTORS
Jiri Krepel, Boris Hombourger&EvzenLosa
PHYTR4-SS4-004
14h40-15h00 IMPACT OF A VOLUMETRIC HEAT SOURCE ON THE CFD
ANALYSIS OF MOLTEN SALT REACTORS
Carlo Fiorina
PHYTR4-SS4-001
15h00-15h20 MULTI-PHYSICS ANALYSIS OF THE FUEL ADDITION
TRANSIENT FOR MOLTEN SALT REACTORS
Tianliang Hu, Liangzhi Cao&Massimiliano Fratoni
PHYTR4-SS4-008
15h20-15h40 MODELLING AND SIMULATION OF A LIQUID FUEL MOLTEN
SALT REACTOR CORE USING GEN-FOAM
Sandesh Bhaskar, Muhammad Altahhan, DevshibhaiZiyad, Paolo
Balestra, Jason Hou, Maria Avramova
PHYTR4-SS4-003
Coffee break Regular Session 3: Reactor physics theory and practice
Chair: Pr. P. Reuss (INSTN/Saclay,France) ; co-chair: J. Tajmouati (Univ. SidiMd Ben Abdellah, Fez)
Location: Menara Room
16h00-16h20 FEYNMAN- Α ANALYSIS FOR A SUBCRITICAL REACTOR
SYSTEM DRIVEN BY AN UNSTABLE SPALLATION NEUTRON
SOURCE IN THE KYOTO UNIVERSITY CRITICAL ASSEMBLY
K. Nakajima, A. Sakon, Sin-yaHohara, K. Hashimito, M. Yamanaka, T.
SanCheol& Ho Pyeon
PHYTRA4-RS-009
16h20-16h40 AN EFFICIENT SOLUTION FOR THE 2D-C5G7 USING SP3
EQUATIONS
A.Vidal-Ferrandiz, A. Carreno, G. Verdu& D.Ginestar
PHYTRA4-RS-033
16h40-17h00 APPLICATION OF GAME THEORY PRINCIPLES ON THE
SENSITIVITY ANALYSIS OF THE TWO-GROUP HOMOGENIZED
CROSS-SECTIONS
Majdi Radaideh, Stuti Surani, Daniel O’Grady & Tomasz Kozlowksi
PHYTRA4-SS1-007
17h00-17h20 PRELIMINARY APPLICATION OF RADIATION AND
SHIELDING CODE SYSTEM OF COSINE CODE PACKAGE Yeshuai Sun, Wen Song, Yao Qin, Xing Wang, Hui Yu &Yixue Chen
PHYTRA4-RS-016
17h20-17h40
17h40-18h00
TABLE LOOKUP OF NODAL EQUIVALENCE PARAMETERS
WITH COVARIANCE DATA
P. M. Bokov, D. Botes&S A Groenewald
VARIANCE-BASED SENSITIVITY ANALYSIS OF THE REACTOR
KINETIC PARAMETERS
MajdiRadaideh,William A. Wieselquist& Tomasz Kozlowski
PHYTRA4-RS-032
PHYTRA4-RS-011
18h00-18h20 DETERMINISTIC ANALYSIS OF POWER PEAKING
FACTORS OFTHE MOROCCAN TRIGA MARK-II
RESEARCH REACTOR O. Jai, O. El Hajjaji, T. El Bardouni, J. Tajmouati, H. Boukhal
& A. Didi
PHYTRA4-RS-67
Special Session 4: Molten Salt Reactors (MSR) Research and Technology
Chair:Stefano Lorenzi (PoliMi, Italy) ; co-chair:B. Nacir (Cnesten, Rabat)
Location: Koutoubia Room
16h00-16h20 ANALYSIS OF THE VOID REACTIVITY EFFECT IN THE
MOLTEN SALT FAST REACTOR: IMPACT OF THE HELIUM
BUBBLING SYSTEM
Eric Cervi, Stefano Lorenzi, LelioLuzzi& Antonio Cammi
PHYTR4-SS4-007
16h20-16h40 Analytical Modelling of the Emergency Draining Tank for the
Molten Salt Fast Reactor
M. Massone, S. Wang, & A.Rineiski
PHYTR4-SS4-006
16h40-17h00 PRELIMINARY ASSESSMENT OF THE FREE-PLUG MELTING
BEHAVIOR IN THE MOLTEN SALT FAST REACTOR
Marco Tiberga, Devaaja Shafer, Danny Lathouwers, Jan
LeenKloosterman
PHYTR4-SS4-005
Wednesday, September 19
Regular Session 1: Reactor Thermal-Hydraulics
Chairs:Y. Boulaych (Cnesten, Rabat)
Location: Menara Room
8h00-8h20 DEVELOPMENT OF A THREE-DIMENSIONAL TWO-PHASE
FLOW ANALYSIS CODE FOR NUCLEAR REACTOR THERMAL PHYTRA4-RS-002
HYDRAULICS: PART 1. THEORY AND VERIFICATION
Seung-Jun Lee,Yun Je Cho, JaeeRyong Lee, IkKyu Park
& Han Young Yoon
8h20-8h40 DEVELOPMENT OF A THREE-DIMENSIONAL TWO-PHASE
FLOW ANALYSIS CODE FOR NUCLEAR REACTOR THERMAL
HYDRAULICS: PART 2. APPLICATION AND VALIDATION
Yun-Je Cho,Seung-Jun Lee, Jae Ryong Lee,IkKyu Park
& Han Young Yoon
PHYTRA4-RS-023
8h40-9h00 DEVELOPMENT OF A NEW ONE-DIMENSIONAL SOLVER
USING OPENFOAM
C. Gomez-Zarzuela, C. Pena-Monferrer, S. Chiva& R. Miro
PHYTRA4-RS-017
9h00-9h20 COMPARISON THE COOLANT TEMPERATURES CALCULATED
BY CODE SC-INT WITH EXPERIMENTAL DATA OBTAINED ON
THE FACILITY KC
D. R. Kireeva & D. A. Oleksyuk
PHYTRA4-RS-018
9h20-9h40 ANALYSIS AND SIMULATION OF AN IBLOCA COUNTERPART
TEST IN ATLAS AND LSTF
M. Lorduy, S. Gallardo & G.Verdú
PHYTRA4-RS-022
9h40-10h00 EVALUATION OF COMBINED NUCLEAR - SOLAR POWER
CYCLE: VERIFICATION AND VALIDATION OF SIMULATION
NimaFathi
PHYTRA4-RS-021
Special Session 5: New Developments in Core Design & Safety Analyses Methodologies – Power Reactors.
Chairs:Jason Hou(North Carolina State University), co-chair: O. Elhajjaji (Univ. A. Essaadi, Tetouan) Location: Koutoubia Room
8h00-8h20 NEW IMPLEMENTATION OF SECOND-ORDER DISCONTINUITY
FACTOR FOR SIMPLIFIED P3 THEORY IN NEM
Yuchao Xu, Jason Hou&Kostadin N. Ivanov
PHYTRA4-SS5-002
8h20-8h40 ASSESSMENT OF RECENT IMPROVEMENTS IN PARAGON
LATTICE PHYSICS CODE FOR PWR GADOLINIUM POISONED
CORES
Jose Herrero, Ho Q. Lam, Juan A. Lazano&Mohamed Ouisloumen
PHYTRA4-SS5-003
8h40-9h00 PRELIMINARY RESULTS ON AN ULTRA-FINE ENERGY GROUP
STRUCTURE THAT QUANTIFIES AND CONTROLS THE ERROR
IN MULTIGROUP CROSS SECTIONS
AbderrafiOugouag andJui-Yu (Raymond) Wang
PHYTRA4-SS5-011
9h00-9h20 PARAGON2/ANC QUALIFICATION FOR COMBUSTION
ENGINEERING PWR CORES ANALYSES
Mohamed Ouisloumen& Ho Q. Lam
PHYTRA4-SS5-005
9h20-9h40 A 2D/1D METHOD FOR CONSISTENT BURNUP
PARAMETRIZATION OF CROSS SECTIONS IN SFR FUEL
DEPLETION CALCULATIONS
Bastien Faure, Pascal Archier& Laurent Buiron
PHYTRA4-SS2-002
9h40-10h00 OPPORTUNITY OF USING URANIUM METAL FUEL IN PWR
REACTORS
V.E Kuzin& L.V. Levanov
PHYTRA4-SS5-006
Coffee break Regular Session 4: Research Reactor Utilization Chair: J. Rodenas (UPV, Spain) ; co-chair: H. Amsil (CNESTEN, Rabat) Location: Koutoubia Room
10h20-10h40 EDUCATION AND TRAINING ACTIVITIES USING MA-1
RESEARCH REACTOR: INTERNET REACTOR LABORATORY
(IRL) PROJECT
Chafik El Younoussi
PHYTRA4-RS-055
10h40-11h00 ESTIMATION OF SOME IRRADIATION PARAMETERS IN A
NUCLEAR REACTOR TO OBTAIN RADIONUCLIDES WITH
EXEMPT ACTIVITY
José Ródenas& Salvador Aledó
PHYTRA4-RS-06
11h00-11h20 THE NEUTRON IMAGING INSTRUMENT (NRAD) AT
MAAMORA TRIGA REACTOR
Afaf Ouardi
PHYTRA4-RS-69
Special Session 5: New Developments in Core Design & Safety Analyses Methodologies – Power Reactors.
Chair: Mohamed Ouisloumen (Westinghouse, USA) ; co-chair: D. Sato (MHI, Japan)
Location: Koutoubia Room 10h20-10h40 LEAD-BISMUTH-COOLED FAST REACTOR BLESS-D:
NEUTRONICS DESIGN AND BURN-UP CALCULATION
Ziguan Wang, Linsen Li, YeohEing Yee&Yaodong Chen
PHYTRA4-SS5-007
10h40-11h00 COUPLED NEUTRONICS AND THERMAL-MECHANICAL
SIMULATIONS OF ANNULAR THORIUM-PLUTONIUM FUEL
Klara InsulanderBjörk
PHYTRA4-SS5-009
11h00-11h20 IMPROVED CORE CONCEPTUAL DESIGN OF SUPERCRITICAL
WATER-COOLED REACTOR CSR150
Di Lu, Lianjie Wang&Bangyang Xia
PHYTRA4-SS5-010
Poster session 2
Lunch
14h00-16h30
Workshop: MRT Methodology and RAPID Code System Alireza Haghighat (Virginia Tech Research Center)
(Location: Menara Room)
17h00-18h00
Closing Ceremony: from 17:00 to 18:00 (Location: Agdal Room)
Full Program (Poster session)
Poster session 1(Reactor Physics)
18,September STUDY ON NEUTRONICS PERFORM ANCE OF HAFNIUM HYDRIDE AS
THERMAL REACTOR CONTROL ROD MATERIAL HUANG Shi-en& Zhao Wenbo
PHYTRA4-SS3-011
CRITICAL EXPERIMENT BENCHMARK VALIDATION OF COSLATC
Yuhang Yan,Shuo Li Chenglin Zhu,Tongrui Yang & Xing Wang PHYTRA4-SS3-012
COUPLED THREE DIMENSIONAL NEUTRONICS AND THERMAL- HYDRAULICS
ANALYSIS FOR SCWR CORE TYPICAL TRANSIENTS Lianjie Wang, Lu Di, Zhao Wenbo, Xia Bangyang& Li Qing
PHYTRA4-RS-031
EFFECT OF TEMPERATURE AND FUEL BURNUP ON REACTIVITY OF HEU CORE
OF MNSR USING DRAGON5/DONJON5. J. Al Zain, O. El Hajjaji, T. El Bardouni
PHYTRA4-RS-36
THERMAL NEUTRON SCATTERING DATA FOR ZrHxM.Elbarbari, T.Elbardouni,
H. Elyaakoubi&Y.Boulaich PHYTRA4-RS-37
DETERMINATION OF THE THERMAL-HYDRAULIC PARAMETERS OF TRIGA
MARK-II REACTOR H. Bougueniz, T. El Bardouni, M. Lahdour, K. Benalilou, Y. Boulaich&B.Nacer
PHYTRA4-RS-39
SENSITIVITY ANALYSIS FOR THERMAL HYDRAULIC SAFETY PARAMETERS OF
THE MOROCCAN TRIGA MARK II RESEARCH REACTOR USING THE PARET/ANL CODE Y. Boulaich, B. Nacir, B. El Bakkari, T.El Bardouni&C. El Younoussi
PHYTRA4-RS-40
OPTIMIZATION OF A NEW CUBOID NUCLEAR FUEL CELL CONCEPT FOR LONG
LIFE SMR S. Charouq, H. Amsil, A.Chetaine, A. Benchrif, O. Kabach, A.Jalil, O.Lebied
PHYTRA4-RS-42
LOW ENRICHEMENT URANIUM (LEU)-FUELED SLOWPOKE-2 NUCLEAR
REACTOR VALIDATION WITH THE MONTE-CARLO BASED OPENMC CODE A. El Mtili, O.El Hajjaji&T.El Bardouni
PHYTRA4-RS-48
ANALYSIS OF THE RECENT NUCLEAR DATA THROUGH A FAST BENCHMARKS HIGHLY
ENRICHED URANIUM STUDY USING THE MONTE CARLO CODE MCNP6.1
S. El Ouahdani, H.Boukhal, M.Makhloul&M.Kaddour PHYTRA4-RS-50
NEUTRONIC MODELING AND CALCULATIONS OF THE NHR-5 REACTOR USING DRAGON AND DONJON CODES H. El Yaakoubi, H.Boukhal, T.El Bardouni, K.Benaalilou, M.Elbarbari, M.Lahdour, L. Erradi&E.Chakir
PHYTRA4-RS-52
OPENMC MONTE CARLO MODELLING OF TRIGA RESEARCH REACTOR
A. Jalil, A.Chetaine, O.Kabach, H.Amsil, K.Embarch, K.Laraki&H.Marah PHYTRA4-RS-59
NEUTRONIC AND THERMAL-HYDRAULIC ANALYSIS OF TRIGA MARK II
REACTOR USING WIMSD, CITATION AND PARET COMPUTER CODES K. Benaaliloua, T. El Bardounia, H. El Yaakoubia, E. Chhama, M. El Barbaria, H. Bougueniza, B. El Bakkarib, Y. Boulaichb, C. El Younoussib&B. Nacirb
PHYTRA4-RS-62
A NEW PACKAGE FOR SOLUTION OF MULTIGROUP NEUTRON TRANSPORT
EQUATION IN A SLAB GEOMETRY M. Lahdour, T.El Bardouni, H.Boukhal, E.Chakir, O.El Hajjaji, M. Mohammed &H. Bougueniz
PHYTRA4-RS-63
ANALYSIS OF TEMPERATURE REACTIVITY FEEDBACK FOR SLOWPOKE-2
RESEARCH REACTOR USING DRAGON5 AND DONJON5 CODE SYSTEM O. Jai, O.El Hajjaji, T. El Bardouni, J.Tajmouati, H. Boukhal&A. Didi
PHYTRA4-RS-68
ANALYSIS OF THE CREOLE EXPERIMENT ON THE REACTIVITY TEMPERATURE
COEFFICIENT OF THE UO2 LIGHT WATER MODERATED LATTICES USING MCNP6.1 S. El Ouahdani, H.Boukhal, T. El Bardouni, M.Makhloul, A.Ahmed &
H.El yaakoubi
PROCESSING OF THE ENDF/B-VIII.0Β6 NEUTRON CROSS-SECTION DATA LIBRARY AND TESTING WITH CRITICAL BENCHMARKS AND OKTAVIAN SHIELDING BENCHMARKS O. Kabach, A. Chetaine, A. Darif, A. Jalil,A. Saidi, A. Benchrif and
H. Amsil
PHYTRA4-RS-49
PHYTRA4-RS-82
AN ADDITIONAL IRRADIATION CHANNEL INSIDE THE TRIGA MARK II RESEARCH REACTOR CORE TO IMPROVE THE CAPACITY OF RADIOISOTOPES PRODUCTION E. Chham, T. El Bardouni, K.Benaalilou, B. El Bakkari, Y.Boulaich, C. El Younoussi &B. Nacir
PHYTRA4-RS-43
SENSITIVITY, UNCERTAINTY AND ADJUSTMENT OF 238U CAPTURE CROSS-SECTION (ENDF/-VII.1 library) USING MCNP6.1 CODE M.Makhloul, H. Boukhal, T. El Bardouni, M.Kaddour, E.Chakir, M. Maged, S. El ouhadani
PHYTRA4-RS-66
Poster session 2 (Nuclear and Radiation Applications)
19, September
MODELING AND SIMULATION OF THERMAL AND SWELLING EFFECT INDUCED ON STEEL COLLIMATOR PLUG FOR PGAA FACILITY OF MOROCCAN TRIGA MARK II REACTOR UNDER DIFFERENT NEUTRON IRRADIATION LEVELS B. El Mokhtari, A.Chetaine, L. El amri, H.Amsil, K.Embarch, A.Benchrif, H.Bounouira, K.Laraki, H. Marah &C. El Younoussi
PHYTRA4-RS-47
SIMULATION OF RADIOACTIVE CLOUD DISPERSION AFTER AN ACCIDENTAL
RELEASE OF I131 FROM TRIGA RESEARCH REACTOR A. El Ouardy, J.Tajmouati, B.Ebakkari, B. Nacir, Y. Boulaich&C.El Younoussi
PHYTRA4-RS-51
NEUTRON DETECTOR CHARACTERISTICS
A. El Yazzaoui& A. Kharchaf PHYTRA4-RS-53
SIMULATION OF THE RADIOLOGICAL CONSEQUENCES OF A RADIOACTIVE
RELEASE AT TRIGA RESEARCH REACTOR H. Ghninou, A. EL Ouardy, B. El Bakkari, J.Tajmouati, B.Nacir, Y.boulaich&C.El Younoussi
PHYTRA4-RS-56
THERMAL HYDRAULIC SAFETY ANALYSIS OF THE I-131 PRODUCTION
EXPERIMENT IN STEADY AND TRANSIENT STATES B.Hjira, M. Yjjou, Y.Boulaich, J.Tajmouati, B.Nacir, B. El Bakkari& C. El Younoussi
PHYTRA4-RS-58
SAPPHIRE FILTER IMPACT ON PGAA FACILITY NEUTRON SPECTRA OF THE
MOROCCAN TRIGA MARK II RESEARCH REACTOR A. Jalil, A.Chetaine, H.Amsil, K.Embarch, K.Laraki&H.Marah
PHYTRA4-RS-60
DOSE RATE MAPPING FOR PGAA FACILITY AT THE MOROCCAN TRIGA MARK
II RESEARCH REACTOR A. Jalil, A.Chetaine, H.Amsil, K.Embarch, K.Laraki&H.Marah
PHYTRA4-RS-61
MECHANICAL AND THERMAL BEHAVIOUR ANALYSIS DURING IODINE 131
PRODUCTION PROCESS IN THE MOROCCAN TRIGA MARK II REACTOR CORE M. Yjjou, B. Hjira, Y. Boulaich, J. Tajmouati, B. Nacir, B. El Bakkari& C. El Younoussi
PHYTRA4-RS-70
STUDY AND DEVELOPMENT OF GASEOUS DETECTORS FOR NEUTRON
DETECTION AND NUCLEAR REACTOR CONTROL IN THE CURRENT NUCLEAR INSTRUMENTATION A. El Hajami, A.Dadouch, A.Maghnouj& J. Tajmouati
PHYTRA4-RS-45
FLUENCE TO LOCAL SKIN ABSORBED DOSE CONVERSION COEFFICIENTS FOR MONOENERGETIC ELECTRONS AND POSITRONS USING MONTE CARLO. Hassan Al Kanti, O. El Hajjaji, T. El Bardouni, H.Boukhal&M.Mohammed
PHYTRA4-RS-35
STUDY OF AIRGAP EFFECTS ON DELIVERED DOSE FOR HIGH RADIOTHERAPY
QUALITY: MONTE CARLO STUDY M. Bencheikh,A.Maghnouj&J.Tajmouati
PHYTRA4-RS-71
SPALLATION YIELD OF NEUTRONS PRODUCED IN natHg AND 136Xe TARGET BOMBARDED WITH 0.1 GeV TO 3 GeV PROTON BEAMA. Didi, A.Dadouch, J.Tajmouati, A.Maghnouj, H. El Bekkouri, O.Jai
PHYTRA4-RS-72
MODELING AND SIMULATION OF INDUCED RADIOACTIVITY WITH DIFFERENT
NEUTRON REGIME IRRADIATION ON STEEL COLLIMATOR PLUG OF THE PGAA FACILITY OF MOROCCAN TRIGA MARK II REACTOR B. El Mokhtari, A.Chetaine,H.Amsil, K.Embarch, K.Laraki, H.Marah & El C.Younoussi
PHYTRA4-RS-38
MODELING AND OPTIMIZATION OF THE SUPERMIRROR NEUTRON GUIDE
DEDICATED TO THE PGAA FACILITY OF THE MOROCCAN TRIGA MARK II REACTOR L. El amri, A.Chetaine, B. El mokhtari, H. Amsil, K. Embarch, A. Benchrif, H.Bounouira, K.Laraki, H.Marah
PHYTRA4-RS-44
NEUTRON ACTIVATION CALCULATION OF THE CENM TRIGA MARK II
RESEARCH REACTOR COMPONENTS USING MCNP CODE S.El Maliki El Hlaibi, T. El Bardouni, Y.Boulaich, B.Nacir, B.El Bakkari&C.El Younoussi PRODUCTION THRESHOLD IMPACT ON A GEANT4 CALCULATION OF THE POWER DEPOSITION IN THE MEGAPIE SPALLATION TARGET A. Lamrabet, A. Maghnouj, J. Tajmouati EGSnrc MONTE CARLO CALCULATIONS OF FLUX TO DOSE RATE CONVERSION FACTORS FOR PHOTONS M. Maged T. El Bardouni, E. Chakir, H. Boukhal, M. Azougagh METEOROLOGICAL FACTORS INFLUENCING THE 7BE AND 210PB CONCENTRATIONS IN GROUND LEVEL AIR IN THE CITY OF TETOUAN (MOROCCO, 35°34′ 42″ N, 5°22′ 06″ W) A. Houali , M. Azahra , T. El Bardouni, M.A.Ferro –Garcia ASSESSMENT OF NATURAL RADIOACTIVITY AND RADIOLOGICAL HAZARDS IN RAW PHOSPHATE E. deiaa
PHYTRA4-RS-46
PHYTRA4-RS-81
PHYTRA4-RS-83
PHYTRA4-RS-84
PHYTRA4-RS-87