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14     CHAPTER 2 Nuclear reactor designs




                         Higher temperatures can enable higher thermodynamic efficiencies in electricity
                         production and can provide process heat for applications such as high-temperature
                         electrolysis of water to produce hydrogen. The designs under consideration include
                         both new concepts and resurrection of some older concepts that previously failed to
                         reach commercialization.
                            Ref. [4], prepared by OECD Nuclear Energy Agency, provides a technology
                         roadmap update on generation IV (gen-IV) reactors. The gen-IV reactor concepts
                         under consideration are the following [4]

                         •  Gas-Cooled Fast Reactor (GCFR): The GCFR is a breeder reactor that uses
                            helium gas to carry the heat from fuel elements comprising the reactor core.
                         •  Lead-cooled Fast Reactor (LFR): The LFR is a breeder reactor that uses liquid
                            lead to carry heat from fuel elements comprising the reactor core.
                         •  Molten Salt Reactor (MSR): The MSR is a fluid-fuel reactor. Fuel is dissolved in
                            a molten salt that flows through the core. The MSR concept permits continuous
                            processing to remove fission products and add fresh fuel, but this is accomplished
                            at the cost of complex plumbing and materials handling. MSR designs include
                            fast reactors (no moderator) and thermal reactors (prismatic graphite block with
                            channels for fluid fuel-bearing salts)
                         •  Sodium-Cooled Fast Reactor (SFR): The SFR is a breeder reactor that uses liquid
                            sodium to carry heat from fuel elements comprising the reactor core.
                         •  Supercritical Water-Cooled Reactor (SCWR): The SCWR is an outgrowth of
                            current designs. It operates at much higher temperatures and pressures than
                            current light water reactors.
                         •  Very-High Temperature Reactor (VHTR): The VHTR uses helium coolant that
                            flows through a core consisting of graphite impregnated with fuel particles.
                            Designs include plants that use the Brayton Cycle instead of a steam cycle. Hot
                            gas passes directly to a gas turbine in a Brayton cycle.




                         2.7 Advanced reactors
                         At the time when this book was written, many new reactor designs were under con-
                         sideration and a few were experiencing prototype construction. Since the focus of
                         this book is reactor dynamics and control, most readers would consider inclusion
                         of detailed descriptions of these designs to be superfluous and unnecessary for their
                         study. But, since some of these designs will likely be implemented, some readers will
                         find that they are involved in their analysis and are consequently interested in infor-
                         mation about them. Information about sodium fast reactors, gas-cooled reactors,
                         molten salt reactors, and integral small modular reactors is presented in Appendix
                         B. This appendix is not to be considered as essential material for every reader. Rather
                         it should be considered as a resource that can be accessed when some of these reactor
                         designs reach maturity and implementation. It is expected that instructors in univer-
                         sity courses will choose to alert students that this appendix exists, but probably to
                         skip it in course presentation.
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