Physics and chemistry of nuclear fuels (PANCHO)

Asko Arkoma; Janne Heikinheimo; Timo Ikonen; Joonas Kättö; Henri Loukusa; Emmi Myllykylä; Jussi Peltonen; Rami Pohja; Ville Tulkki; Ville Valtavirta

Physics and chemistry of nuclear fuels (PANCHO)

Asko Arkoma, Janne Heikinheimo, Timo Ikonen, Joonas Kättö, Henri Loukusa, Emmi Myllykylä, Jussi Peltonen, Rami Pohja, Ville Tulkki, Ville Valtavirta

Research output: Chapter in Book/Report/Conference proceeding › Chapter or book article › Professional

Abstract

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.

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

Access to Document

https://publications.vtt.fi/pdf/technology/2019/T349.pdf

1 Report

SAFIR2018: The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Final Report
Hämäläinen, J. (ed.) & Suolanen, V. (ed.), Mar 2019, VTT Technical Research Centre of Finland. 498 p. (VTT Technology; No. 349).
Research output: Book/Report › Report

Open Access

Cite this

Arkoma, A., Heikinheimo, J., Ikonen, T., Kättö, J., Loukusa, H., Myllykylä, E., Peltonen, J., Pohja, R., Tulkki, V., & Valtavirta, V. (2019). Physics and chemistry of nuclear fuels (PANCHO). In J. Hämäläinen, & V. Suolanen (Eds.), SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Final Report (pp. 252-268). VTT Technical Research Centre of Finland. VTT Technology No. 349 https://publications.vtt.fi/pdf/technology/2019/T349.pdf

@inbook{67359735ac2744d8945710b02fd27363,

title = "Physics and chemistry of nuclear fuels (PANCHO)",

abstract = "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{\textquoteright}s thesis is to be finalized from the work performed in this project.",

author = "Asko Arkoma and Janne Heikinheimo and Timo Ikonen and Joonas K{\"a}tt{\"o} and Henri Loukusa and Emmi Myllykyl{\"a} and Jussi Peltonen and Rami Pohja and Ville Tulkki and Ville Valtavirta",

year = "2019",

language = "English",

series = "VTT Technology",

publisher = "VTT Technical Research Centre of Finland",

number = "349",

pages = "252--268",

editor = "Jari H{\"a}m{\"a}l{\"a}inen and Vesa Suolanen",

booktitle = "SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018",

address = "Finland",

}

Arkoma, A , Heikinheimo, J, Ikonen, T, Kättö, J, Loukusa, H, Myllykylä, E , Peltonen, J , Pohja, R , Tulkki, V & Valtavirta, V 2019, Physics and chemistry of nuclear fuels (PANCHO). in J Hämäläinen & V Suolanen (eds), SAFIR2018 - The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Final Report. VTT Technical Research Centre of Finland, VTT Technology, no. 349, pp. 252-268. <https://publications.vtt.fi/pdf/technology/2019/T349.pdf>

Physics and chemistry of nuclear fuels (PANCHO). / Arkoma, Asko ; Heikinheimo, Janne; Ikonen, Timo et al.

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 -

Physics and chemistry of nuclear fuels (PANCHO)

Abstract

Publication series

Access to Document

Fingerprint

Research output

SAFIR2018: The Finnish Research Programme on Nuclear Power Plant Safety 2015-2018: Final Report

Cite this