STARS Publications - Technical Reports

The STARS technical reports and notes are listed below. Please note that these reports and notes might contain proprietary and/or confidential data and are therefore not for public use. For further questions, please contact the project leader.

2017

S. Rahman
Large Break LOCA Analysis for the Olkiluoto 3 EPR Reactor using TRACE
PSI Technical Report TM-41-17-05 V.0 (September 2017)

S. Rahman, C. Cozzo
Core lnitialization Methodology and Scenario Specification for LB LOCA Analysis of EPR
PSI Technical Report TM-41-16-23 V.0 (September 2017)

R. Puragliesi
Computational fluid dynamics and subchannel analysis of 5x5 fuel rod assembly: verification study based on PSBT test 7T conditions
PSI Technical Report TM-41-16-26 V.0 (September 2017)

M. Pecchia
Evaluation of Power Distributions in BWR SVEA96 Optima-2 using MCNP
PSI Technical Report TM-41-17-06 V.0 (September 2017)

Y. Aounallah
Simulations of Studsvik FIX-II transient dryout tests with TRACE
PSI Technical Report TM-41-15-28 V.0 (September 2017)

A. Dokhane
Assessment of New S3K Code Version for the PSI Stability Analysis Methodology
PSI Technical Note AN-41-16-14 V.0 (August 2017)

D. Rochman
Review of decay heat calculation methods for SNF, SERPENT, FISPACT-11 and BOHR for typical PWR systems
PSI Technical Note AN-41-16-28 V.0 (August 2017)

I. Clifford
Reference TRACE KKB Full-core Large Break LOCA Analysis
PSI Technical Report TM-41-16-19 V.0 (August 2017)

J.J. Herrero, A. Vasiliev
Preliminary Reference Loading Curves obtained for NAGRA's SNF Disposal Canister with PSI BUCSS-R Methodology
PSI Technical Report TM-41-16-25 V.0 (May 2017)

V. Brankov, G. Khvostov, K. Mikityuk
OECD HRP Technical Visit and LOCA Data Analysis
PSI Technical Report TM-41-14-04 V.0 (April 2017)

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2016

R. Puragliesi
CFD URANS transient analyses of boron dilution in EPRTM type reactor pressure vessel
PSI Technical Report TM-41-16-17 V.0 (December 2016)

C. Cozzo
Technical Note - Review of the Default SiC Models in FALCON v1.1 for Cladding Material
PSI Aktennotiz AN-41-16-12 V.0 (November 2016)

D. Wicaksono
Technical Note - Summary of PSI participation in the OECD/NEA PREMIUM Benchmark
PSI Memorandum SB-RND-ACT-006-13.007 (November 2016)

Y. Aounallah
An Inventory for the "Separate-Effect" Tests and TRACE Simulations Scripting for the Post-Dryout Database
PSI Technical Report TM-41-14-22 V.0 (October 2016)

A. Vasiliev
SIMULATES preliminary assessment with KKG CMSYS models
PSI Technical Report TM-41-16-05 V.0 (October 2016)

D. Rochman
Scoping Analyses towards Global Methodology for CASMO Uncertainty and Bias Quantification - Case Study for KKG UR3 Sample
PSI Technical Report TM-41-15-09 V.1 (July 2016)

D. Rochman
244Cm calculations after fuel irradiation: preparatory analysis of PIE data and nuclear data libraries
PSI Technical Report TM-41-16-09 V.0 (July 2016)

D. Rochman
Quantification of Uncertainties and Biases in CASM0-5 Calculations of 244Cm Nuclide Compositions for the Ul, U2, U7, BMl and BM5 samples
PSI Technical Report TM-41-16-10 V.0 (July 2016)

I. Clifford
Technical Note - Deficiencies in the Fuel Rod Ballooning Model of TRACE v5.0p4
PSI Technical Note SB-XTK-ACT-003-16.002 V.1 (July 2016)

C. Cozzo
Technical Note - Fuel Rod Models: Review of the TRACE v5840 models compared to those of FALCON MOD01 v29
PSI Technical Note SB-XTK-ACT-003-16.001 V.1 (July 2016)

A. Dokhane
Analyses of SPERT-III RIA Experiments with Quantification of Nuclear Data Uncertainties for Tests 43, 60 ,70, 81 and 86 using various VCM libraries
PSI Technical Report TM-41-16-16 V.0 (July 2016)

A. Vasiliev
Preliminary assessment of the CASM0-4/SIMULATE-3/MCNPX modelling performance for the KKL first surveillance capsule dosimetry data analysis
PSI Technical Report TM-41-15-27 V.0 (May 2016)

J.J. Herrero
Bounding case analysis of spent nuclear fuel operated in Swiss PWR and loaded in disposal canister
PSI Technical Report TM-41-16-07 V.0 (April 2016)

M. Pecchia
Methodology for automatizing the representation of heterogeneous material dataset with temperature effects in large scale MCNP models
PSI Technical Report TM-41-15-31 V.0 (April 2016)

M. Pecchia
New PSI methodology for manufacturing and technological uncertainty quantification
PSI Technical Report TM-41-14-24 V.0 (April 2016)

R. Mukin
Review of PKL lll TRACE model under G7.1 counterpart test simulation
PSI Technical Report TM-41-15-29 V.0 (March 2016)

I. Clifford
Post-test analysis of OECD ROSA-2 Test 4 (SGTR) using TRACE
PSI Technical Report TM-41-15-04 V.0 (March 2016)

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2015

H. Ferroukhi
Development and Verification of a Methodology for SIMULATE-3K Analyses at Sub-Critical Core Conditions
PSI Technical Report TM-41-15-33 V.0 (December 2015)

H. Ferroukhi, O. Zerkak, P. Mala
PSI Contribution to D12.41 Advanced Solutions with SIMULATE-3K to the NURESAFE PWR MSLB Benchmark
NURESAFE Report D12.41 (December 2015)

M. Pecchia
Methodology for evaluating PWR ex-core detector response and weighting functions using MCNP and its application for KKG
PSI Technical Report TM-41-15-17 V.0 (December 2015)

R. Puragliesi
PSI/LRS Contribution to the Analytical Exercise on OECD/NEA/CSNI PKL-3 Project ROCOM Test T2.3: Investigation of in-Vessel Flow Mixing During Cold Leg Accumulator Injection ( Based on PKL-3 Test H3.1 )
PSI Technical Note, SB-RND-ACT-015-14.001 (November 2015)

O. Leray
Shark X V.2.1 - Fission Yield perturbation methodology: Implementation of correlations and application on the LWR PROTEUS Phase II Ul Sample
PSI Technical Report TM-41-15-22 V.0 (October 2015)

Y. Aounallah
Simulations of KKM Steam Line Breaks under "Hot" Standby conditions with TRACE
PSI Technical Report TM-41-13-19 V.0 (October 2015)

A. Dokhane
TRACE/SIMULATE-3K Analysis of the Oskarshamn-2 Stability Event and Comparison to TRACE/PARCS and SIMULATE-3K Stand-alone
PSI Technical Report TM-41-15-14 V.0 (October 2015)

D. Rochman
Scoping Analyses towards Global Methodology for CASMO Uncertainty and Bias Quantification - Case Study for KKG UR3 Sample
PSI Technical Report TM-41-15-09 V.0 (October 2015)

R. Nguyen Van Ho
Nuclear Data Uncertainty Propagation for LWR Fuel Assembly Lattices
PSI Technical Report TM-41-15-21 V.0 (October 2015)

R. Ngayam-Happy
Assessment of the PERFORM-60 platform for the simulation and prediction of irradiation-induced embrittlement of a RPV steel characteristic of Swiss nuclear reactors
PSI Technical Report TM-41-15-23 V.0 (October 2015)

J.J. Herrero
Review of international status on burnup credit implementation for long term spent nuclear fuel disposal
PSI Technical Report TM-41-15-24 V.0 (October 2015)

M. Krack, C. Cozzo, H. Ferroukhi
First Interim Report for the Falcon Code Development activity within the PSl-EPRI collaboration agreemen
PSI Technical Note AN-41-15-06 V.1 (August 2015)

D. Zhang
Bundle Reconstruction History Method for Direct Whole Core Calculations with the Code nTRACER
PSI/EPFL Master Thesis Report SB-RND-ACT-013-14.001 (August 2015)

Z. Guo
Simulation of Irradiation Damage in Chromium-doped LWR Fuel
PSI/EPFL Master Thesis Report SB-RND-ACT-012-14.001 (August 2015)

O. Leray
Technical Note - AREVA CASMO-5 Analyses 2015 - PWR Lattices
PSI Memorandum SB-XTK-ACT-001-13.001, March 12, 2015

D. Zhang
Pin-by-Pin Fuel Depletion with Higher- Order 3-D Transport Methods
PSI/EPFL Semester Project Report (January 2015)

Z. Guo
Simulation of Irradiation Damage in Cr-doped LWR Fuel
PSI/EPFL Semester Project Report (January 2015)

H. Yao
Direct Generation of Plant System Simulation Models using CAD Geometry
PSI/EPFL Semester Project Report (January 2015)

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2014

O. Leray
New developments of the UQ/SA platform for deterministic depletion calculations: Shark-X v2.0
PSI Technical Report TM-41-14-19 V.0 (December 2014)

M. Pecchia
Assessment of MCNPX burnup capability in fuel assembly models and preliminary isotopic inventory uncertainty quantification
PSI Technical Report TM-41-14-05 V.0 (December 2014)

J.J. Herrero
OECD/NEA WPNCS BUC Phase 7 benchmark analysis for decay and criticality codes assessment
PSI Technical Report TM-41-14-06 V.0 (December 2014)

L. Zhou, R. Puragliesi
Assessment of a STAR-CCM+ CFD model for EPR JULIETTE coolant mixing tests at stationary conditions
PSI Technical Report TM-41-14-08 V.0 (December 2014)

G. Perret
Criticality safety evaluation of the UNIBAS fuel storage
PSI Technical Report TM-41-14-17 V.0 (September 2014)

D. Wicaksono, O. Zerkak, A. Pautz
PSI Contribution to PREMIUM Phase IV - Post-Test Uncertainty Quantification of FEBA and PERICLES Reflood Tests
PSI/EPFL Report, September 2014

H. Perrier
Development of a Hybrid Deterministic/Stochastic Depletion Scheme
PSI/EPFL Master Thesis Report (September 2014)

C. Liu
Development and Optimization of Fast Solution Algorithms for the Fuel Depletion Equations
PSI/EPFL Master Thesis Report (September 2014)

A. Dupre
Modelling and validation enhancements of the PSI Fast Neutron Fluence MCNPX based computational scheme using recent KKG experimental data
PSI/EPFL Master Thesis Report (September 2014)

Q. Zhou
Validation and Verifcation of OpenFOAM CFD Tool for Buoyancy Driven Turbulent Mixing Problems in a Reactor Pressure Vessel
PSI/EPFL Master Thesis Report (September 2014)

L. Rossinelli
Coupling of SERPENT and SIMULATE-3 for BWR full core simulations
PSI/EPFL Master Thesis Report (September 2014)

A. Epiney
WP1.2 Higher-resolution PWR MSLB simulation D12.22 ? FLICA4 input models for PWR MSLB analysis
PSI/NURESAFE Report D12.22 Version 0 (May 2014)

D. Wicaksono, O. Zerkak, A. Pautz
PSI Contribution to PREMIUM Phase IV - Post-Test Uncertainty Quantification of FEBA and PERICLES Reflood Tests
PSI/EPFL Report, April 2014

J. Freixa
Small Break LOCA Analysis for the Olkiluoto 3 EPR [TM] Reactor
PSI Technical Report TM-41-13-22 V.0 (March 2014)

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2013

A. Dupre
Towards modeling and validation enhancements of the PSI Fast Neutron Fluence MCNPX based computational scheme using recent KKG experimental data
EPFL/ETHZ Semester Project Report (December 2013)

H. Perrier
Reactivity benchmark analysis and code reactivity prediction
EPFL/ETHZ Semester Project Report (December 2013)

L. Rossinelli
Neutronic Data Generation for BWR Models, Comparison of SERPENT and CASMO-5
EPFL/ETHZ Semester Project Report (December 2013)

Q. Zhou
Verification of OpenFOAM CFD Tool for Steady-state Simulations of a Reactor Pressure Vessel Based on ROCOM Test 1.1 Conditions
EPFL/ETHZ Semester Project Report (December 2013)

G. Khvostov
Parameter optimization for the Halden LOCA test IFA-650.14 using the FALCON fuel behaviour code
PSI Technical Report TM-41-13-15 V.0 (December 2013)

G. Perret, P. Grimm
Basel Reactor Fuel Characteristics for Transport Purposes
PSI Technical Report TM-41-13-12 V.0 (October 2013)

M. Hursin
Development of SHARKX-v1.1 - Methodology Description and Verification
PSI Technical Report TM-41-13-14 V.0 (October 2013)

A. Nigam
OECD/NRC BFBT Pressure Drop and Void Distribution Benchmark with Sub-channel Code COBRA-TF
European Master Project Report(September 2013)

A. Gairola
Application of coupled GOTHIC-TRACE codes for the simulation of a postulated LOCA in a nuclear power plant
European Master Project Report(September 2013)

M. Pecchia, H. Ferroukhi
Parametric Study of Bismuth-Lead Alloy Irradiation in Nuclear Reactors
PSI Technical Report TM-41-13-20 V.0 (September 2013)

A. Vasiliev, S. Canepa
Analysis of KKL dosimeter sets 1, 2, 3 and 4 irradiated during cycles 1, 2, 3 and 12 with CASM0-4/SIMULATE-3/MCNPX-2.4.0 system of codes
PSI Technical Report TM-41-13-08 V.0 (August 2013)

Y. Yun
Analysis of fuel failure conditions of selected ramp rods within SCIP-11 programme
PSI Technical Report TM-41-13-09 V.0 (August 2013)

Y. Yun
Investigation of fuel failure conditions during power ramp: Modelling exercise within SCIP-11 programme (intermediate report)
PSI Technical Report TM-41-12-13 V.0 (August 2013)

D. Wicaksono
Comparison Studies of Monte-Carlo-Based Depletion Codes
PSI Technical Report TM-41-13-13 V.0 (August 2013)

M. Pecchia
Update of the PSI Criticality Safety Evaluation Methodology using MCNPX2.7 and ENDF/B-VI1.1
PSI Technical Report TM-41-13-10 V.0 (August 2013)

J. Freixa
Remarks on consistent development of plant nodalizations: an example of application to the ROSA integral test facility
PSI Technical Report TM-41-12-07 V.0 (August 2013)

Y. Aounallah
Simulations of a "High-Pressure" MSIV closure ATWS for KKM with the TRACE/SIMULATE-3K (TS3K) coupled code
PSI Technical Report TM-41-13-02 V.0 (August 2013)

S. Bogetic
Development and Verification of TRACE/PARCS Methodology for Analyses of the Swiss Reactors
EPFL/ETHZ Master Thesis Report (July 2013)

G. Khvostov
Post-test Analysis of the IFA-650.12 Halden LOCA Experiment using the FALCON Code coupled to FRELAX Model
PSI Technical Report TM-41-13-04 V.0 (May 2013)

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2012

S. Bogetic
Assessment of Cross-Section Interface for PARCS Modelling and Analysis of a Swiss LWR
EPFL/ETHZ Semester project Report (December 2012)

T. Gudmundsson, S. Canepa, K. Nikitin
Development of the data linkage tool COBALT for best-estimate LWR analysis with the coupled TRACE/S3K code
PSI Technical Report TM-41-10-19 V.0 (December 2012)

S. Belaid, J. Freixa
PKL Ill G7.1 counterpart test simulation using the US-NRC thermal-hydraulic best estimate system code TRACE
PSI Technical Report TM-41-12-08 V.0 (December 2012)

Y. Aounallah
Two-Phase Blowdown Prediction with TRACE based on General Electric Level-Swell Experiments
PSI Technical Report TM-41-11-26 V.0 (December 2012)

Y. Yun
Brief survey of the available data and correlations for major MOX fuel properties
PSI Technical Report TM-41-12-10 V.0 (December 2012)

D. Papini, C. Adamsson
Project PASSPORT - Survey of available experiments for validation of containment/primary system code coupling
PSI Technical Report TM-42-12-08, Version 0 (November 2012)

O. Zerkak, D. Wicaksono, I. Gajev
Evaluation of different thermal-hydraulics - neutron kinetics temporal coupling schemes for the analysis of the OECD/NEA BWR Turbine Trip Benchmark
NURISP Report D.3.2.2&3, Version 0 (August 2012)

W. Wieselquist
CASM0-5MX: Tools for Sensitivity Analysis and Uncertainty Quantification with respect to Nuclear Data in CASM0-5M
PSI Technical Report TM-41-12-09, Version 0 (July 2012)

T-W. Kim, D. Karanki
Development of a Discrete Dynamic Event Tree Analysis Tool ADS-TRACE
PSI Technical Report TM-41-12-04, Version 0 (July2012)

I. Gajev, O. Zerkak
Report on the exploration of adaptive coupling in the time-domain
NURISP Report D.3.2.2.4, Version 0 (June 2012)

M. Hursin
Scoping Study towards the Establishment of a Methodology for Preparation of Few-Group Homogenized Neutronic Data for LWR 3-D Core Analyses using the SERPENT Code
PSI Technical Report TM-41-12-03, Version 0 (June 2012)

D. Wicaksono
Development and Assessment of an Improved Temporal Coupling for TRACE/S3K Analysis
EPFL/ETHZ Master Thesis Report, June 2012

P. Zvoncek
Multi-objective Neutronics Optimization of Inert Matrix Fuel with CASM0-5M and MATLAB's Genetic Algorithm
PSI Technical Report TM-41-12-06, Version 0 (June 2012)

P. Grimm. A. Vasiliev, H. Ferroukhi
Assessment of AREVA Methodology for Tramp Uranium Estimations
PSI Technical Report TM-41-12-02, Version 0 (March 2012)

A. Vasiliev, W. Wieselquist, H. Ferroukhi, S. Canepa
CASMO/SIMULATE/MCNPX-based methodology for FNF modelling for BWRs; Models set up and test validation studies for KKL reactor.
PSI Technical Report TM-41-11-17, Version 0 (March 2012)

T-W. Kim
OECD/NRC Benchmark based on NUPEC PWR Subchannel and Bundle Test (PSBT)- Phase-2: DNB Benchmark
PSI Technical Report TM-41-11-29, Version 0 (March 2012)

T-W. Kim
OECD/NRC Benchmark based on NUPEC PWR Subchannel and Bundle Test (PSBT)- Phase-1 : Steady-state and Transient Bundle tests
PSI Technical Report TM-41-11-23, Version 0 (March 2012)

Y. Yun
Evaluation of ALPS LOCA experiments using KKL fuel
PSI Technical Report TM-41-10-27 Version 1 (March 2012)

S. Canepa, W. Wieselquist, H. Ferroukhi
NURISP SP1- Report on PWR schemes and benchmark analysis results using APOLLO2 and TRIPOLI4
NURISP Report D1.4.3b, Revision 1 (January 2012)

D. Wicaksono
Evaluation of The Current TRACE/S3K Temporal Coupling for Two Selected LWR Transients
EPFL/ETHZ Semester Work Report (January 2012)

P. Zvoncek
Inert Matrix Fuel Calculations with CASMO-5
EPFL/ETHZ Semester Work Report (January 2012)