TY - GEN
T1 - Physics analysis of the LS-VHTR
T2 - PHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics
AU - Clarno, Kevin T.
AU - Gehin, Jess C.
PY - 2006
Y1 - 2006
N2 - The Liquid-Salt-Cooled Very High Temperature Reactor (LS-VHTR), also known as the Advanced High Temperature Reactor (AHTR), is a new, large [>2400 MW(t)], passively safe, high-temperature reactor concept. It uses a graphite-matrix coated-particle fuel and a graphite moderator similar to the fuel used in modular high-temperature gas-cooled reactors, but with a clean liquid-fluoride salt coolant. The neutronics properties of various salt coolant options are considered with respect to their coefficients of reactivity for various reactor configurations. In addition, several variations on the basic graphite block design of the AHTR are considered that would simplify refueling. The results show that the coolant coefficients of reactivity are negative or very small relative to other reactivity feedbacks, such as the fuel Doppler feedback. This allows several salt-coolants, even some with a positive coolant density coefficient, to be considered for use in the AHTR. In addition, parametric studies of assembly-type clusteredrod configurations show that there is minimal impact on the reactivity coefficients and multiplication factors with appropriate cluster design choices.
AB - The Liquid-Salt-Cooled Very High Temperature Reactor (LS-VHTR), also known as the Advanced High Temperature Reactor (AHTR), is a new, large [>2400 MW(t)], passively safe, high-temperature reactor concept. It uses a graphite-matrix coated-particle fuel and a graphite moderator similar to the fuel used in modular high-temperature gas-cooled reactors, but with a clean liquid-fluoride salt coolant. The neutronics properties of various salt coolant options are considered with respect to their coefficients of reactivity for various reactor configurations. In addition, several variations on the basic graphite block design of the AHTR are considered that would simplify refueling. The results show that the coolant coefficients of reactivity are negative or very small relative to other reactivity feedbacks, such as the fuel Doppler feedback. This allows several salt-coolants, even some with a positive coolant density coefficient, to be considered for use in the AHTR. In addition, parametric studies of assembly-type clusteredrod configurations show that there is minimal impact on the reactivity coefficients and multiplication factors with appropriate cluster design choices.
KW - AHTR
KW - Gen-IV
KW - Liquid salt
KW - Reactivity coefficients
KW - VHTR
UR - https://www.scopus.com/pages/publications/33847215456
M3 - Conference contribution
AN - SCOPUS:33847215456
SN - 0894486977
SN - 9780894486975
T3 - PHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics
BT - PHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics
Y2 - 10 September 2006 through 14 September 2006
ER -