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

M. Pecchia
LRS methodology for activation studies and preliminary application to KKG ex-core regions
PSI Technical Report TM-41-17-14 V.0 (October 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)