Page 248 - Dynamics and Control of Nuclear Reactors
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APPENDIX B Advanced reactors      249




                     Both reactor designs use TRISO (Tristructural Isotropic) small fuel particles
                  (0.5mm) that can withstand high temperatures and contain fission products.
                  A TRISO coated fuel particle consists of an outer pyrolytic carbon layer
                  (0.92mm outer diameter), followed by a silicon carbide and an inner pyrolytic car-
                  bon layers, and an inner porous carbon buffer. The fuel kernel is in the center of the
                  particle. The silicon carbide’s high melting temperature (1600°C) protects against
                  particle failure.
                     Regardless of the specific reactor design, all advanced gas-cooled reactors have
                  the following features:
                  •  Chemically inert Helium coolant
                  •  Single phase Helium coolant (no issues due to boiling)
                  •  Negligible neutron absorptions in Helium coolant (zero coolant temperature
                     coefficient of reactivity
                  •  High thermal conductivity in graphite (avoids hot spots)
                  •  Slow response to perturbations due to large heat capacity
                  •  Dominant negative fuel temperature coefficient of reactivity due to the Doppler
                     effect
                  •  Power stabilizes after a perturbation with no control action.

                  All of these features combine to enhance gas-cooled reactor safety. Both large and
                  small versions of gas-cooled reactors are candidates for implementation.


                  B.6.2 Liquid metal fast breeder reactors
                  The potential for breeding in fast reactors has been realized since the early days of
                  nuclear power and a number of prototype reactors have been operated (Refs. 18–20).
                  Two large fast reactors (BN 600 and BN 800) are operating in in Russia as this book
                  is being written (2018) and fast reactors are under construction in China [21] and
                  India [22].
                     Sodium fast reactors (SFRs) are a class of advanced reactor design that uses
                  sodium to remove heat from the reactor core, and transfer to heat exchangers and
                  steam generators. SFRs typically fall into one of two design categories: pool-type
                  and loop-type. Pool-type SFRs feature primary coolant system components such
                  as pumps and intermediate heat exchangers positioned inside the reactor vessel.
                  In loop-type reactors, these components are exterior to the reactor vessel. Pool-type
                  configurations reduce the possibility of many accident scenarios present in light
                  water reactors.
                     Since sodium (Na-23) atoms are heavier than hydrogen and oxygen atoms, neu-
                  trons lose less energy in collisions with sodium atoms than hydrogen and oxygen in
                  LWRs, thus enabling fast fission reactions. Sodium has a large range of temperatures
                  (371–1156K) in the liquid phase enabling the absorption of significant heat in the
                  liquid phase. A large sodium reservoir provides excellent thermal inertia against
                  overheating. Because of the high boiling point of sodium (compared to operating
                  temperatures), it is not necessary to pressurize the primary loop, thus enabling the
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