Conference Articles

 

 

 

 

 

2015

  • Andreani M, Badillo A, Kapulla R, Smith B
    Synthesis of the oECD/NEA-PSI CFD benchmark exercise
    In: 16th international topical meeting on nuclear reactor thermal hydraulics, NURETH 2016. Vol. 3. American Nuclear Society; 2015:1787-1801.
    DORA PSI
  • Brankov V, Khvostov G, Mikityuk K, Pautz A, Restani R, Abolhassani S, et al.
    Modeling of axial distribution of released fission gas in KKL BWR fuel rods during base irradiation
    In: TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 1. Brussels: European Nuclear Society; 2015:609-619.
    DORA PSI
  • Bykov V, Volmert B, Pautz A
    Enhancement and Validation of BWR MCNP Activation Simulations for Swiss Decommissioning Planning
    Presented at: 2015 American Nuclear Society Student Conference; April 9-11, 2015; College Station, TX, USA.
    DORA PSI
  • Canepa S, Krack M, Ferroukhi H, Pautz A
    Scalability benchmarking methodology for hybrid parallel core calculations with the code nTRACER
    In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:2819-2831.
    DORA PSI
  • Chionis D, Hofer K, Pautz A
    Peak cladding temperature prediction and assessment for the Leibstadt NPP using SIMULATE-3K
    In: 2015 ANS student conference. Powering tomorrow together. La Grange Park: American Nuclear Society; 2015:(6 pp.).
    DORA PSI
  • Chollet M, Krsjak V, Cozzo C, Bertsch J
    Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels
    In: TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 1. Brussels: European Nuclear Society; 2015:502-509.
    DORA PSI
  • Chollet M, Krack M, Kuzmin A, Bertsch J, Grolimund D, Martin M
    Theoretical modelling of pristine and chromium-doped UO2
    Presented at: E-MRS 2015; May 11-15, 2015; Lille, France.
    DORA PSI
  • Clifford I, Vasiliev A, Zerkak O, Ferroukhi H, Pautz A
    Computational fluid dynamics analysis of the fluid flow and heat transfer in the core bypass region of a PWR
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:7806-7819.
    DORA PSI
  • Dehbi A
    A generalized correlation for steam condensation rates in the presence of air-helium mixtures
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2016). Vol. 10. American Nuclear Society; 2015:8347-8359.
    DORA PSI
  • Dokhane A, Zerkak O, Ferroukhi H, Gajev I, Judd J, Kozlowski T
    TRACE/SIMULATE-3K analysis of the NEA/OECD Oskarshamn-2 stability benchmark
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:4757-4770.
    DORA PSI
  • Epiney A, Canepa S, Zerkak O, Ferroukhi H
    Towards a consolidated approach for the validation of plant system codes and models: case study for a BWR fast depressurisation event
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:2157-2170.
    DORA PSI
  • Fernandez-Moguel L, Rydl A, Jaeckel B
    Analysis of Fukushima Daiichi NPP unit 3 with Melcor_2.1
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:6401-6411.
    DORA PSI
  • Fiorina C, Mikityuk K, Pautz A
    GeN-Foam: a novel multi-physics solver for reactor analysis - status and ongoing developments
    In: Federici G, Corradini ML, Klein AC, Uckan NA, Rimpault G, Cacuci DG, et al., eds. Proceedings of the American Nuclear Society. Vol. 113. Transactions of the American Nuclear Society. La Grange Park: American Nuclear Society; 2015:1132-1134. https://www.ans.org/pubs/transactions/article-38067/.
    DORA PSI
  • Geißler T, Szijarto R, Beyer M, Hampel U, Prasser H-M, Leyer S, et al.
    Experimental and numerical investigation of flow structure and heat transfer during high pressure condensation in a declined pipe at COSMEA facility
    In: Proceedings of NURETH-16. Vol. 10. International topical meeting on nuclear reactor thermal hydraulics 2015, NURETH 2015. La Grange Park: American Nuclear Society; 2015:8547-8560.
    DORA PSI
  • Giustini G, Murallidharan J, Sato Y, Niceno B, Badalassi V, Walker S
    Numerical study of heat diffusion controlled bubble growth in a pressurized liquid
    In: Proceedings of NURETH-16. Vol. 5. International topical meeting on nuclear reactor thermal hydraulics 2015, NURETH 2015. sine loco: American Nuclear Society; 2015:4069-4082.
    DORA PSI
  • Giustini G, Murallidharan J, Sato Y, Niceno B, Badalassi V, Walker S
    Numerical study of heat diffusion controlled phase growth in a pressurized liquid
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:4069-4082.
    DORA PSI
  • Grundler P, Veleva L, Gu H, Allner S, Niceno B, Ritter S
    Noble metal applications for SCC mitigation in BWRs: platinum nanoparticle penetration into crevices and cracks under controlled flow conditions
    In: 17th international conference on environmental degradation of materials in nuclear power systems-water reactors. Toronto, Ontario, Canada: Canadian Nuclear Society; 2015:1577-1592.
    DORA PSI
  • Herrero JJ, Pecchia M, Ferroukhi H, Canepa S, Vasiliev A, Caruso S
    Computational scheme for burnup credit applied to long term waste disposal
    In: ICNC 2015 - international conference on nuclear criticality safety. LaGrange Park, IL, USA: American Nuclear Society; 2015:1783-1791.
    DORA PSI
  • Hombourger B, Pautz A, Krepel J, Mikityuk K
    Fuel cycle analysis of a Molten Salt Reactor for Breed-and-Burn mode
    In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015:910-916.
    DORA PSI
  • Hursin M, Joo HG, Downar TJ
    Assessment of thermal hydraulic feedbacks effects during modeling of a RIA using direct whole core transport solution
    In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:2394-2405.
    DORA PSI
  • Hursin M, Rossinelli L, Ferroukhi H, Pautz A
    BWR full core analysis with SERPENT/SIMULATE-3 hybrid stochastic/determinstic code sequence
    In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:1794-1806.
    DORA PSI
  • Kapulla R, Kelm S, Mignot G, Paranjape S, Paladino D
    Experimental and numerical results for the erosion dynamics of a vertical helium-air jet interacting with a helium rich layer
    In: Proceedings of ICAPP 2015. Vol. 49. INIS. Paris: SFEN; 2015:15242 (16 pp.). https://inis.iaea.org/search/search.aspx?num=10&orig_q=RN%3a49005001&lang=en-US&login=false&user=External&src=&sort=date:D:L:d1&sortorder=ascending&search-option=Everywhere&q=+inmeta:ConferenceTitle%3DICAPP%25202015%253A%2520Nuclear%2520Innovations%2.
    DORA PSI
  • Kelm' S, Kapulla R, Allelein HJ
    Erosion of a confined stratified layer by a vertical jet - detailed assessment of a CFD approach against the OECD/NEA PSI benchmark
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). Vol. 6. American Nuclear Society; 2015:4462-4475.
    DORA PSI
  • Krepel J, Brankov V, Mikityuk K
    Selection of initial fuel composition for the ESFR core based on the knowledge of its equilibrium closed cycle parameters
    In: Track 8 - deployment and scenarios. Vienna: International Atomic Energy Agency; 2015:(9 pp.).
    DORA PSI
  • Kriventsev V, Rineiski A, Pfrang W, Perez-Martin S, Mikityuk K, Khvostov G
    Benchmark on behavior of MOX fuel pin under irradiation at nominal power in sodium fast reactor
    In: TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 2. Brussels: European Nuclear Society; 2015:550-559.
    DORA PSI
  • Krohn B, Sharabi M, Nicenou B, Prasser HM, Bijleveld H, Shams A, et al.
    Turbulent gas mixing in strong density stratified shear and non-shear flows
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). Vol. 6. International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. LaGrange Park, IL, USA: American Nuclear Society; 2015:4436-4449.
    DORA PSI
  • Leray O, Pecchia M, Vasiliev A, Ferroukhi H, Pautz A, Perrier H
    Development, verification and test application of a hybrid CASMO-5/SERPENT depletion scheme
    In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:1781-1793.
    DORA PSI
  • Mala P, Canepa S, Ferroukhi H, Pautz A
    Preparation of pin-by-pin nuclear libraries with superhomogenization method for nTRACER and DORT core calculations
    In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:775-786.
    DORA PSI
  • Mignot G, Paranjape S, Kapulla R, Paladino D
    Performance of hydrogen mitigation systems for a scaled accident scenario: overview of ERCOSAM project experimental results for the PANDA facility
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:5456-5469.
    DORA PSI
  • Murallidharan J, Giustini G, Sato Y, Ničeno B, Badalassi V, Walker SP
    Interface tracking based evaluation of bubble growth rates in high pressure pool boiling conditions
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:6530-6542.
    DORA PSI
  • Newman GR, Jordan KA, Perret G
    GCFR-PROTEUS experimental program benchmark analysis
    In: Uckan NA, Federici G, Michal R, Corradini ML, Tompkins B, Klein AC, et al., eds. Transactions of the American nuclear society. Vol. 113. Transactions of the American Nuclear Society. American Nuclear Society; 2015:186-189.
    DORA PSI
  • Paladino D, Kapulla R, Mignot G, Paranjape S
    Combined effects of cooler and spray activation on the hydrogen distribution in the presence of a jet flow
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). Vol. 2. American Nuclear Society; 2015:1502-1515.
    DORA PSI
  • Paladino D, Kiselev A
    Main outcomes from the EURATOM-ROSATOM ERCOSAM SAMARA parallel projects for hydrogen safety of LWR
    In: Proceedings of ICAPP 2015. Vol. 49. INIS. Paris: SFEN; 2015:15357 (11 pp.). https://inis.iaea.org/search/search.aspx?orig_q=RN:49004920.
    DORA PSI
  • Papini D, Andreani M, Ničeno B, Prasser H-M, Steiner P, Klugel J-U
    Simulation of hydrogen distribution in the containment during a severe accident with fast hydrogen-steam release
    In: Proceedings of NURETH-16. Vol. 2. International topical meeting on nuclear reactor thermal hydraulics 2015, NURETH 2015. sine loco: American Nuclear Society; 2015:1474-1487.
    DORA PSI
  • Paranjape S, Kapulla R, Mignot G, Paladino D
    Parametric study on density stratification erosion caused by a horizontal steam jet interacting with a vertical plate obstruction
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:4490-4503.
    DORA PSI
  • Park S, Fernandez-Moguel L, Prasser H-M, Birchley J, Steinbrück M, Seifert H-J
    Effect of nitriding during an air ingress scenario
    In: TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 2. Brussels: European Nuclear Society; 2015:380-390.
    DORA PSI
  • Pecchia M, Herrero JJ, Ferroukhi H, Vasiliev A, Canepa S, Pautz A
    COMPLINK: a versatile tool for automatizing the representation of material data in MCNP models
    In: ICNC 2015 - international conference on nuclear criticality safety. LaGrange Park, IL, USA: American Nuclear Society; 2015:513-522.
    DORA PSI
  • Pelloni S, Aufiero M, Bortot S, Krepel J, Mikityuk K, Panadero AL, et al.
    Sodium void map preparation for the safety analysis of Sodium-cooled Fast Reactors by using the Monte Carlo code Serpent
    In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015. https://www.sfen.org/.
    DORA PSI
  • Puragliesi R, Zerkak O, Pautz A, Zhou Q
    Assessment of OpenFOAM CFD toolbox for gravity driven mixing flows in a Reactor Pressure Vessel
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:952-965.
    DORA PSI
  • Qian G, González-Albuixech VF, Niffenegger M, Sharabi M
    Probabilistic pressurized thermal shocks analysis for a reactor pressure vessel by considering plume effect
    In: Proceedings of the ASME 2015 pressure vessels and piping conference. Materials and fabrication. Vol. 6A. Pressure vessels and piping conference. New York City: American Society of Mechanical Engineers ASME; 2015:PVP2015-45963 (9 PP.). https://doi.org/10.1115/PVP2015-45963
    DORA PSI
  • Rahman S, Karanki DR, Epiney A, Zerkak O, Dang VN
    Ranking of uncertain parameters for dynamic event tree analysis: a case study based on a Station Black Out scenario
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:5734-5747.
    DORA PSI
  • Rýd A, Jäckel B, Klügel J-U, Steiner P
    Melt-concrete interface heat transfer models and coolability models: PWR analyses with MELCOR/CORCON and CORQUENCH
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:484-498.
    DORA PSI
  • Vasiliev A, Rochman D, Zhu T, Pecchia M, Ferroukhi H, Pautz A
    Towards application of neutron cross-section uncertainty propagation capability in the criticality safety methodology
    In: ICNC 2015 - international conference on nuclear criticality safety. LaGrange Park, IL, USA: American Nuclear Society; 2015:606-615.
    DORA PSI
  • Wicaksono D, Zerkak O, Pautz A
    A methodology for global sensitivity analysis of transient code output applied to a reflood experiment model using TRACE
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:4862-4879.
    DORA PSI
  • Zboray R, Dangendorf V, Mor I, Tittelmeier K, Bromberger B, Prasser H-M
    Time-resolved fast neutron radiography of air-water two-phase flows
    In: Lehmann EH, Kaestner AP, Mannes D, eds. Proceedings of the 10th world conference on neutron radiography (WCNR-10) Grindelwald, Switzerland October 5-10, 2014. Vol. 69. Physics procedia. sine loco: Elsevier; 2015:551-555. https://doi.org/10.1016/j.phpro.2015.07.078
    DORA PSI

Peak Cladding Temperature Prediction And Assessment For The Leibstadt Npp Using Simulate-3k
D. Chionis, K. Hofer, A.Pautz
Proc. American Nucl. Societ Student Conference 2015, College Station, Tx Texas A&M University, April 9-11, 2015


Enhancement And Validation Of Bwr Mcnp Activation Simulations For Swiss Decommissioning Planning
V. Bykov
Proc. American Nucl. Societ Student Conference 2015, College Station, Tx Texas A&M University, April 9-11, 2015