A Neutronic Program for Critical and Nonequilibrium Study of Mobile Fuel Reactors: The Cinsf1D Code

Journal Article · Wed Jan 15 00:00:00 EST 2003 · Nuclear Science and Engineering

OSTI ID:20804827

Lecarpentier, David; Carpentier, Vincent ^[1]

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1. Electricite de France Research and Development (France)

Molten salt reactors (MSRs) have the distinction of having a liquid fuel that is also the coolant. The transport of delayed-neutron precursors by the fuel modifies the precursors' equation. As a consequence, it is necessary to adapt the methods currently used for solid fuel reactors to achieve critical or kinetics calculations for an MSR. A program is presented for which this adaptation has been carried out within the framework of the two-energy-group diffusion theory with one dimension of space. This program has been called Cinsf1D (Cinetique pour reacteur a sels fondus 1D)

• OSTI ID: 20804827
• Journal Information: Nuclear Science and Engineering, Vol. 143, Issue 1; Other Information: Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/; Country of input: International Atomic Energy Agency (IAEA); ISSN 0029-5639
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
C CODES
COOLANTS
DELAYED NEUTRON PRECURSORS
LIQUID FUELS
MOLTEN SALT REACTORS
SOLID FUELS