Asko Arkoma

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Personal profile

Education/Academic qualification

Physical sciences, Doctorate

Fingerprint Dive into the research topics where Asko Arkoma is active. These topic labels come from the works of this person. Together they form a unique fingerprint.

  • 18 Similar Profiles
Accidents Engineering & Materials Science
Loss of coolant accidents Engineering & Materials Science
accidents Physics & Astronomy
loss of coolant Physics & Astronomy
Boiling water reactors Engineering & Materials Science
accident Earth & Environmental Sciences
Statistical methods Engineering & Materials Science
Spent fuels Engineering & Materials Science

Projects 2015 2019

Research Output 2010 2019

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
Nuclear fuels
3 Citations (Scopus)

Calculation chain for the analysis of spent nuclear fuel in long-term interim dry storage

Arkoma, A., Huhtanen, R., Leppänen, J., Peltola, J. & Pättikangas, T., 22 Apr 2018, In : Annals of Nuclear Energy. 119, p. 129–138 10 p.

Research output: Contribution to journalArticleScientificpeer-review

Spent fuels
Nuclear fuels
Computational fluid dynamics
Open Access
Loss of coolant accidents
Boiling water reactors
Sensitivity analysis
Light water reactors

Predicting fuel rod failures and their contributing factors with surrogate support vector machines in statistical LOCA analysis

Arkoma, A., 2018, Proceedings of ANS Best Estimate Plus Uncertainty International Conference (BEPU 2018): Electronic proceedings. 12 p. 281​

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

Extending the reactivity initiated accident (RIA) fuel performance code SCANAIR for boiling water reactor (BWR) applications

Arkoma, A., 1 Oct 2017, In : Nuclear Engineering and Design. 322, p. 192-203 12 p.

Research output: Contribution to journalArticleScientificpeer-review

boiling water reactors
Boiling water reactors