The thorium molten salt reactor: Moving on from the MSBR

Briesmeister, J.F., 1997. MCNP4B – a general Monte Carlo N particle transport code. Los Alamos Laboratory Report LA-12625-M.

EDF/DER, 1977. Analyse critique du projet MSBR. HT-12/24/77.

Ignatiev, V., Merzlyakov, A., Walle, E., Boursier, J-M., 2005. Density of molten salt reactor fuel salts. Nureth, Avignon, France.

Lecarpentier, D., 2001. Le concept AMSTER, aspects physiques et sûreté. PhD Thesis. Conservatoire National des Arts et Métiers, Paris.

Merle-Lucotte, E., Heuer, D., Le Brun, C., Loiseaux, J-M., 2005. Scenarios for a worldwide deployment of nuclear energy production. LPSC 05-73, Grenoble, France.

Merle-Lucotte, E., Mathieu, L., Heuer, D., Loiseaux, J-M., Billebaud, A., Brissot, R., David, S., Garzenne, C., Laulan, O., Le Brun, C., Lecarpentier, D., Liatard, E., Meplan, O., Michel-Sendis, F., Nuttin, A., Perdu, F., 2004. Molten salt reactors and possible scenarios for future nuclear power deployment. Physor, Chicago, USA.

Nuttin, 2005, Potential of thorium molten salt reactors: detailed calculations and concept evolution with a view to large scale energy production, Progress in Nuclear Energy, 46, 77, 10.1016/j.pnucene.2004.11.001

Platonov, P.A., Chugunov, O.K., Manevsky, V.M., Karpukhin, V.I., 1995. Radiation damage and life-time evaluation of RBMK graphite stack. IAEA-TECDOC-901, pp. 79–90.

Rosenthal, 1970, Molten salt reactors – history, status, and potential, Nuclear Applications and Technology, 8, 10.13182/NT70-A28619

Walle, E., Finne, J., Picard, G., Sanchez, S., Conocar, O., Lacquement, J., 2003. Molten salt reactors: chemistry of fuel salt and fuel salt cleanup. Global, New Orleans, USA.

Tahon, B., 2004. Sgl Carbon Group, private communication.