Research Output

2020

A Serpent2-SUBCHANFLOW-TRANSURANUS coupling for pin-by-pin depletion calculations in Light Water Reactors

García, M., Tuominen, R., Gommlich, A., Ferraro, D., Valtavirta, V., Imke, U., Van Uffelen, P., Mercatali, L., Sanchez-Espinoza, V., Leppänen, J. & Kliem, S., May 2020, In : Annals of Nuclear Energy. 139, 107213.

Research output: Contribution to journalArticleScientificpeer-review

Nuclear data sensitivity and uncertainty analysis of critical VENUS-F cores with the Serpent Monte Carlo code

Fridman, E., Valtavirta, V. & Aufiero, M., Apr 2020, In : Annals of Nuclear Energy. 138, 107196.

Research output: Contribution to journalArticleScientificpeer-review

Nuclide inventory of FIR 1 TRIGA research reactor fuel

Räty, A., Häkkinen, S. & Kotiluoto, P., 1 Jun 2020, In : Annals of Nuclear Energy. 141, p. 107352 107352.

Research output: Contribution to journalArticleScientificpeer-review

OECD/NRC PWR MOX/UO2 core transient benchmark pin-by-pin solutions using Serpent/SUBCHANFLOW

Ferraro, D., Valtavirta, V., García, M., Imke, U., Tuominen, R., Leppänen, J. & Sanchez-Espinoza, V., Nov 2020, In : Annals of Nuclear Energy. 147, 107745.

Research output: Contribution to journalArticleScientificpeer-review

Photon transport physics in Serpent 2 Monte Carlo code

Kaltiaisenaho, T., Jul 2020, In : Computer Physics Communications. 252, 107143.

Research output: Contribution to journalArticleScientificpeer-review

Serpent/SUBCHANFLOW pin-by-pin coupled transient calculations for the SPERT-IIIE hot full power tests

Ferraro, D., García, M., Valtavirta, V., Imke, U., Tuominen, R., Leppänen, J. & Sanchez-Espinoza, V., Jul 2020, In : Annals of Nuclear Energy. 142, 107387.

Research output: Contribution to journalArticleScientificpeer-review

Open Access
2 Citations (Scopus)

Serpent2-SUBCHANFLOW pin-by-pin modelling capabilities for VVER geometries

García, M., Ferraro, D., Valtavirta, V., Tuominen, R., Imke, U., Leppänen, J. & Sanchez-Espinoza, V., Jan 2020, In : Annals of Nuclear Energy. 135, 106955.

Research output: Contribution to journalArticleScientificpeer-review

4 Citations (Scopus)

Thermochemical and thermomechanical modeling of nuclear fuel

Loukusa, H., 25 Feb 2020, Aalto University. 98 p.

Research output: ThesisDissertation

Open Access

Vacancy cluster growth and thermal recovery in hydrogen-irradiated tungsten

Zibrov, M., Egger, W., Heikinheimo, J., Mayer, M. & Tuomisto, F., Apr 2020, In : Journal of Nuclear Materials. 531, 152017.

Research output: Contribution to journalArticleScientificpeer-review

2 Citations (Scopus)

Validation and verification of the FINIX fuel behavior module

Peltonen, J., Loukusa, H. & Tulkki, V., 2020, Global/Top Fuel 2019. American Nuclear Society ANS, p. 1164-1173

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Validation of the Serpent 2-HEXTRAN-SMABRE code sequence in a VVER-1000 coolant transient

Häkkinen, S., Syrjälahti, E. & Rintala, A., 9 Jun 2020, In : Journal of Nuclear Science and Technology.

Research output: Contribution to journalArticleScientificpeer-review

2019

Advanced cladding materials for accident tolerant fuels

Heikinheimo, J., Huotilainen, C., Pohja, R., Ivanchenko, M. & Loukusa, H., 31 Oct 2019, SYP2019 Proceedings. Finnish Nuclear Society, 4 p.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Open Access
4 Citations (Scopus)

Coolant-cladding interaction models in FINIX fuel behaviour module

Peltonen, J. & Loukusa, H., 31 Oct 2019, SYP2019 Proceedings. Finnish Nuclear Society, 5 p.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Open Access

Development of an object-oriented SERPENT2-SUBCHANFLOW coupling and verification with problem 6 of the VERA core physics benchmark

García, M., Ferraro, D., Valtavirta, V., Imke, U., Tuominen, R., Sanchez-Espinoza, V. & Mercatali, L., 2019, International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. American Nuclear Society ANS, p. 1424-1433

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Open Access

Evaluating the effect of decay and fission yield data uncertainty on spent nuclear fuel source term using Serpent 2

Rintala, A., 2019.

Research output: Contribution to conferenceConference articleScientificpeer-review

Extension of nodal diffusion solver of Ants to hexagonal geometry

Rintala, A. & Sahlberg, V., Sep 2019, In : Kerntechnik. 84, 4, p. 252-261

Research output: Contribution to journalArticleScientificpeer-review

FINIX - Fuel behavior model and interface for multiphysics applications - Code documentation for version 1.19.1

Loukusa, H., Peltonen, J. & Valtavirta, V., 1 Feb 2019, VTT Technical Research Centre of Finland. 92 p. (VTT Research Report; No. VTT-R-00052-19).

Research output: Book/ReportReport

Open Access
File
55 Downloads (Pure)

Fuel behaviour under loca conditions estimated with fraptran

Heikinheimo, J., 2019, Fuel Modelling in Accident Conditions (FUMAC): Final Report of a Coordinated Research Project. International Atomic Energy Agency IAEA, p. 128-142 (IAEA Technical Documents; No. 1889).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleScientific

Full-core uncertainty analysis of nuclear fuel behavior

Loukusa, H., 31 Oct 2019, SYP2019 Proceedings. Finnish Nuclear Society, 4 p.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Open Access

Impact of fuel type and discharge burnup on source term

Juutilainen, P. & Häkkinen, S., 2019.

Research output: Contribution to conferenceConference articleScientificpeer-review

Jules Horowitz Reactor - the Future of European Materials Testing Reactors

Huotilainen, C., Tulkki, V., Moilanen, P., Kinnunen, P., Revuelta, A. & Bignan, G., 2019, SYP2019 Proceedings: Nuclear Science and Technology Symposium - SYP2019. Finnish Nuclear Society

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

Kraken: An upcoming Finnish reactor analysis framework

Valtavirta, V., Hovi, V., Loukusa, H., Rintala, A., Sahlberg, V., Tuominen, R. & Leppänen, J., 2019, International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. American Nuclear Society ANS, p. 786-795 10 p.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Modeling burnup-induced fuel rod deformations and their effect on transient behavior of a VVER-440 reactor core

Syrjälahti, E., Ikonen, T. & Tulkki, V., 2019, In : Annals of Nuclear Energy. 125, p. 121-131 11 p.

Research output: Contribution to journalArticleScientificpeer-review

3 Citations (Scopus)

Modeling cladding oxidation with coupled thermal-mechanics and thermal-hydraulics solvers

Loukusa, H., Peltonen, J. & Hovi, V., 2019.

Research output: Contribution to conferenceConference PosterScientificpeer-review

Modeling missing pellet surface defects with BISON

Loukusa, H., 2019, VTT Technical Research Centre of Finland. 27 p. (VTT Research Report; No. VTT-R-00067-19).

Research output: Book/ReportReport

Modeling of the SPERT transients using Serpent 2 with time-dependent capabilities

Levinsky, A., Valtavirta, V., Adams, F. P. & Anghel, V. N. P., Mar 2019, In : Annals of Nuclear Energy. 125, p. 80-98 19 p.

Research output: Contribution to journalArticleScientificpeer-review

4 Citations (Scopus)

New energy deposition treatment in the Serpent 2 Monte Carlo transport code

Tuominen, R., Valtavirta, V. & Leppänen, J., 2019, In : Annals of Nuclear Energy. 129, p. 224-232 9 p.

Research output: Contribution to journalArticleScientificpeer-review

2 Citations (Scopus)

Overview of the JET preparation for deuterium-tritium operation with the ITER like-wall

Aho-Mantila, L., Airila, M., Hakola, A., Kaltiaisenaho, T., Koivuranta, S., Likonen, J., Salmi, A., Sirén, P., Tala, T. & JET Contributors, 30 Aug 2019, In : Nuclear Fusion. 59, 11, 112021.

Research output: Contribution to journalReview ArticleScientificpeer-review

Open Access
23 Citations (Scopus)

Photonuclear reactions in serpent 2 Monte Carlo code

Kaltiaisenaho, T., 2019, International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019. American Nuclear Society ANS, p. 181-190

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Physics and chemistry of nuclear fuels (PANCHO)

Arkoma, A., Heikinheimo, J., Ikonen, T., Kättö, J., Loukusa, H., Myllykylä, E., Peltonen, J., Pohja, R., Tulkki, V. & Valtavirta, V., 2019, SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Final Report. Hämäläinen, J. & Suolanen, V. (eds.). VTT Technical Research Centre of Finland, p. 252-268 (VTT Technology; No. 349).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Open Access

Pin power reconstruction method for rectangular geometry in nodal neutronics program Ants

Rintala, A. & Sahlberg, V., 2019.

Research output: Contribution to conferenceConference articleScientificpeer-review

Serpent/SCF pin-level multiphysics solutions for the VERA Fuel Assembly benchmark

Ferraro, D., Garcia, M., Imke, U., Valtavirta, V., Leppänen, J. & Sanchez-Espinoza, V., 9 Jan 2019, In : Annals of Nuclear Energy. 128, p. 102-114 13 p.

Research output: Contribution to journalArticleScientificpeer-review

6 Citations (Scopus)

Serpent and TRIPOLI-4® transient calculations comparisons for several reactivity insertion scenarios in a 3D PWR minicore benchmark

Ferraro, D., Faucher, M., Mancusi, D., Zoia, A., Valtavirta, V., Leppänen, J. & Sanchez-Espinoza, V. H., Aug 2019, International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2019). American Nuclear Society ANS, p. 1734-1743 10 p.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Serpent validation using giacint facility experimental data from a control rod insertion transient

Talamo, A., Gohar, Y. A., Valtavirta, V., Leppänen, J., Sikorin, S., Mandzik, S., Polazau, S. & Hryharovich, T., Aug 2019, International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2019). American Nuclear Society ANS, p. 2657-2663 7 p.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

SuperFINIX — A flexible-fidelity core level fuel behavior solver for multi-physics applications

Valtavirta, V., 2019.

Research output: Contribution to conferenceConference articleScientificpeer-review

2007

The 3D Core Thermohydraulics and Neutronics Solution in the TRAB-SMABRE Accident and Transient Code

Miettinen, J., Räty, H. & Daavittila, A., 2007, Proceedings: 15th International Conference on Nuclear Engineering, ICONE15. Japan Society of Mechanical Engineers, 7 p.

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

Open Access
2004

The coupled code TRAB-3D-SMABRE for 3D transient and accident analyses

Miettinen, J. & Räty, H., 2004, SAFIR, The Finnish Research Programme on Nuclear Power Plant Safety 2003 - 2006: Interim Report. Espoo: VTT Technical Research Centre of Finland, p. 38-45 (VTT Tiedotteita - Research Notes; No. 2272).

Research output: Chapter in Book/Report/Conference proceedingChapter or book articleProfessional

Open Access
1995

Simulations of pressure and salinity fields at Äspö

Löfman, J. & Taivassalo, V., 1995, Stockholm: Svensk Kärnbränslehantering AB (SKB). 121 p. (SKB International Cooperation Report; No. 95-01).

Research output: Book/ReportReport

Open Access

The representation of conceptual models

Taivassalo, V., 1995, The Role of Conceptual Models in Demonstrating Repository Post-Closure Safety. Paris: OECD, p. 159-173

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

Tulipesän hallinta konenäön ja kvalitatiivisen mallin avulla

Translated title of the contribution: Burner management by image processing and qualitative modellingHirvonen, J., Lilja, R., Ikonen, K. & Nihtinen, J., 1995. 4 p.

Research output: Contribution to conferenceConference articleProfessional

1994

Assessing the velocity of the groundwater flow in bedrock fractures

Taivassalo, V. & Poteri, A., 1994, Helsinki: Voimayhtiöiden ydinjätetoimikunta. 55 p. (YJT Raportti, Vol. 94-17).

Research output: Book/ReportReport

Full 3D stress field analysis is to become the generalized fracture parameter

Ikonen, K. & Raiko, H., 1994, Proceedings of the 5th Finnish Mechanics Days. Mäkinen, R. A. E. & Neittaanmäki, P. (eds.). Jyväskylä: University of Jyväskylä, p. 391-398 (University of Jyväskylä. Laboratory of Scientific Computing. Report; No. 3/1994).

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Groundwater flow analyses in preliminary site investigations: Modelling strategy and computer codes

Taivassalo, V., Koskinen, L. & Meling, K., 1994, Helsinki: Voimayhtiöiden ydinjätetoimikunta. 89 p. (YJT Raportti, Vol. 94-04).

Research output: Book/ReportReport

Interactive simulation and visualisation in APROS nuclear applications

Puska, E-K., Hämäläinen, A., Kontio, H. & Niemi, J., 1994, Proceedings of the SIMS'94 Simulation Conference. Langemyr, L. (ed.). Stockholm: Scandinavian Simulation Society SIMS, p. 150-155

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Large displacement finite difference analysis of rectangular window panes in dynamic shock loadings

Ikonen, K., 1994, Proceedings of the 5th Finnish Mechanics Days. Mäkinen, R. A. E. & Neittaanmäki, P. (eds.). Jyväskylä: University of Jyväskylä, p. 45-52 (University of Jyväskylä. Laboratory of Scientific Computing. Report; No. 3/1994).

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

Modelling of fracture geometry the preliminary site investigations for a nuclear waste repository

Poteri, A. & Taivassalo, V., 1994, Helsinki: Voimayhtiöiden ydinjätetoimikunta. 71 p. (YJT Report; No. 8/1994).

Research output: Book/ReportReport

Modelling the LPT2 pumping and tracer test at Äspö: Pumping test

Taivassalo, V., Koskinen, L., Laitinen, M., Löfman, J. & Meszaros, F., 1994, Stockholm: Svensk Kärnbränslehantering AB (SKB). 163 p. (SKB International Cooperation Report, Vol. 94-12).

Research output: Book/ReportReport

Simulation of the groundwater flow of the Kivetty area

Taivassalo, V. & Mészáros, F., 1994, Helsinki: Voimayhtiöiden ydinjätetoimikunta. 145 p. (YJT Raportti, Vol. 94-03).

Research output: Book/ReportReport

The INTRAVAL project: Analysis of the tracer experiments at Finnsjön by the VTT/TVO project team

Hautojärvi, A. & Taivassalo, V., 1994, Helsinki: Voimayhtiöiden ydinjätetoimikunta. 73 p. (YJT Raportti, Vol. 94-24).

Research output: Book/ReportReport