CONQUER CORROSION: Key issues of the lead-cooled fast reactor design
Independent thesis Advanced level (professional degree), 20 credits / 30 HE creditsStudent thesis
The lead-cooled fast reactor (LFR) is one of the concepts of the Generation IV reactorsystems. There are some issues that have to be solved before a research orcommercial LFR can be built. The objective of this thesis was to identify these keyissues and analyse them by studying results from previous research: choice of fuel,corrosion on structural materials and corrosion/erosion on pumps.The major fuel candidates for the LFR are MOX fuel (Mixed OXide fuel), metallic fuel,nitride fuel and carbide fuel. Nitride fuel has desirable properties but its production ismore difficult than for MOX fuel.Most of today’s commercial steels are not corrosion resistant at higher temperaturesbut they could possibly be used for an LFR test demonstrator with an operatingtemperature lower than 450 ºC. A new type of steel called oxide dispersionstrengthened (ODS) steel and a new ceramic material MAXTHAL both showpromising corrosion resistance even at higher temperatures.By controlling the oxygen concentration a protective oxide film is produced. Flowingliquid coolant causes erosion and wears down the oxide film. Pumps are exposed tocoolant velocities of 10-15 m/s causing both erosion and corrosion. There is nosolution today, but MAXTHAL shows promising results in tests with liquid lead of lowvelocity. There are also other issues unsolved, such as irradiation damage onstructural materials, thus more research is needed.Economic and political aspects were not covered in this study. This thesis work wasperformed at Vattenfall Research and Development AB.
Place, publisher, year, edition, pages
2011. , 57 p.
UPTEC F, ISSN 1401-5757 ; F11023
Nuclear power, Generation-IV, lead cooled fast reactor, LFR, corrosion, MAXTHAL, MYRRHA, Lead-bismuth eutectic, LBE
IdentifiersURN: urn:nbn:se:uu:diva-149755OAI: oai:DiVA.org:uu-149755DiVA: diva2:405453
Sjöstrand, HenrikNyberg, Tomas