Abstract
The chemical experiments on nuclear fuel materials aimed to investigate characteristics of initial dissolution of crystalline ThO2 by adding 229Th tracer into the aqueous phase, and were conducted for total 534 days. The experimental campaign on cladding creep demonstrated that the VTT equipment is capable of performing suitable transient tests which support modelling efforts.
Three DSc theses were finalized based on the ongoing cladding creep modelling work, the modelling of fuel behavior in design basis accidents and fuel pellet dissolution experiments. One Master’s thesis is to be finalized from the work performed in this project.
| Original language | English |
|---|---|
| Title of host publication | SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018 |
| Subtitle of host publication | Final Report |
| Editors | Jari Hämäläinen, Vesa Suolanen |
| Publisher | VTT Technical Research Centre of Finland |
| Pages | 252-268 |
| ISBN (Electronic) | 978-951-38-8682-0 |
| Publication status | Published - 2019 |
| MoE publication type | D2 Article in professional manuals or guides or professional information systems or text book material |
Publication series
| Series | VTT Technology |
|---|---|
| Number | 349 |
| ISSN | 2242-1211 |
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Physics and chemistry of nuclear fuels (PANCHO). / Arkoma, Asko; Heikinheimo, Janne; Ikonen, Timo; Kättö, Joonas; Loukusa, Henri; Myllykylä, Emmi; Peltonen, Jussi; Pohja, Rami; Tulkki, Ville; Valtavirta, Ville.
SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Final Report. ed. / Jari Hämäläinen; Vesa Suolanen. VTT Technical Research Centre of Finland, 2019. p. 252-268 (VTT Technology; No. 349).Research output: Chapter in Book/Report/Conference proceeding › Chapter or book article › Professional
TY - CHAP
T1 - Physics and chemistry of nuclear fuels (PANCHO)
AU - Arkoma, Asko
AU - Heikinheimo, Janne
AU - Ikonen, Timo
AU - Kättö, Joonas
AU - Loukusa, Henri
AU - Myllykylä, Emmi
AU - Peltonen, Jussi
AU - Pohja, Rami
AU - Tulkki, Ville
AU - Valtavirta, Ville
PY - 2019
Y1 - 2019
N2 - PANCHO has been the essential platform for the ongoing development of FINIX fuel behaviour module and its accompanying automatic validation system. FINIX has been published through the OECD/NEA Data Bank, and has been licensed by several institutions around the world. The studies on fuel behaviour in accident conditions have been framed within the international projects, where the accident simulation codes have been tested and validated. A coupling between SCANAIR and GENFLO codes has been developed in the project.The chemical experiments on nuclear fuel materials aimed to investigate characteristics of initial dissolution of crystalline ThO2 by adding 229Th tracer into the aqueous phase, and were conducted for total 534 days. The experimental campaign on cladding creep demonstrated that the VTT equipment is capable of performing suitable transient tests which support modelling efforts.Three DSc theses were finalized based on the ongoing cladding creep modelling work, the modelling of fuel behavior in design basis accidents and fuel pellet dissolution experiments. One Master’s thesis is to be finalized from the work performed in this project.
AB - PANCHO has been the essential platform for the ongoing development of FINIX fuel behaviour module and its accompanying automatic validation system. FINIX has been published through the OECD/NEA Data Bank, and has been licensed by several institutions around the world. The studies on fuel behaviour in accident conditions have been framed within the international projects, where the accident simulation codes have been tested and validated. A coupling between SCANAIR and GENFLO codes has been developed in the project.The chemical experiments on nuclear fuel materials aimed to investigate characteristics of initial dissolution of crystalline ThO2 by adding 229Th tracer into the aqueous phase, and were conducted for total 534 days. The experimental campaign on cladding creep demonstrated that the VTT equipment is capable of performing suitable transient tests which support modelling efforts.Three DSc theses were finalized based on the ongoing cladding creep modelling work, the modelling of fuel behavior in design basis accidents and fuel pellet dissolution experiments. One Master’s thesis is to be finalized from the work performed in this project.
M3 - Chapter or book article
T3 - VTT Technology
SP - 252
EP - 268
BT - SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018
A2 - Hämäläinen, Jari
A2 - Suolanen, Vesa
PB - VTT Technical Research Centre of Finland
ER -