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Sodium-Cooled Fast Reactors,” Proceedings of the International Conference on the Safety of Fast Reactors, Aix-En-Provence, September 19–22, 1967, Pp

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Sodium-Cooled Fast Reactors,” Proceedings of the International Conference on the Safety of Fast Reactors, Aix-En-Provence, September 19–22, 1967, Pp Canadian Nuclear Safety Commission Information Seminar on Sodium Fast Reactors Presented by: George Flanagan, ORNL Tanju Sofu, ANL December 10-11, 2018 Module 1 – Introduction ORNL is managed by UT-Battelle, LLC for the US Department of Energy 1 Seminar is Arranged by Modules • Module 1—Introduction • Module 2—SFR Neutronics • Module 3—SFR Coolants and Thermal Hydraulics • Module 4—Fuel Characteristics • Module 5—SFR Systems and Components • Module 6—Safety and Accident Analysis • Module 7—Licensing Issues • Module 8—Containment Systems • Module 9—Selected SFR Operating Experience • Module 10—Summary of PWR, 4S, and PRISM Characteristics 2 Module 1 – Introduction The seminar modules are is arranged by topic. Information in the modules may be repeated when relevant to other modules. 2 Sodium Fast Reactor CNSC information Seminar Objectives Provide an understanding of • Sodium fast reactor (SFR) technology • Experience related to safety to support CNSC assessment, review, regulation, and licensing of SFR systems 3 Module 1 – Introduction 3 Why A Sodium Fast Reactor? Positive Aspects • Faster neutron spectrum can be used for breeding or transmutation of transuranic waste products • Sodium is an excellent heat transfer agent with high- temperature boiling point • Sodium allows low-pressure components • Sodium allows high-thermal efficiency and superheated steam conditions 4 Module 1 – Introduction 4 Positive Aspects of Sodium Fast Reactors (continued) • Sodium is compatible with structural components (stainless steels) and metallic fuels • Electromagnetic pumps and flow instrumentation are possible • Large supply of sodium is available due to extensive use in chemical industry • Internal breeding of plutonium can result in long times before refueling • Large database from EBR-II, CRBR and FFTF programs (but many years old) 5 Module 1 – Introduction SFR technology was chosen over other coolants (see subsequent slides) for breeder reactors. Subsequently, the slower growth of nuclear reactors and ample supplies of uranium made the need for breeders less urgent. SFRs also offer a way of burning transuranic fission products and minimizing the capacity needed for permanent repositories. 5 Challenging Aspects of Sodium Fast Reactors • Requires compact core to minimize slowing down of neutrons due to sodium moderating effect • High temperatures can lead to thermal stresses and creep in structural materials • Sodium burns on contact with air or water— requires inert cover gas • Sodium containing systems must be in inerted cells and concrete must be steel lined • Sodium freezes at 100C and components and piping must be trace heated 6 Module 1 – Introduction Sodium‐cooled fast reactors, however, do have some disadvantages that require appropriate design considerations. These will be addressed in the subsequent slides and modules, with a view toward future regulatory actions. 6 Challenging Aspects of Sodium Fast Reactors (continued) • Core is not in most reactive configuration—neutronic excursions possible with core compaction (severe accidents) • Sodium and sodium-oxide and -hydroxide aerosols are not benign • Sodium is opaque making ISI and refueling difficult • No established regulatory experience in Canada • Sodium is incompatible with oils and most foreign materials • Sodium fast reactors require higher initial fuel enrichment 7 Module 1 – Introduction 7 History of SFRs • Liquid-metal fast reactors were among the first to be designed, built, and operated • The first ever electrical power was generated by EBR-I, which fed into the power system for Arco, Idaho • Most of the initial designs were intended to support the development of breeder reactors • More detailed information on certain plants is provided in Module 9 – Selected SFR Operating Experience • Detailed information for SFR power levels, temperatures, configuration, and dates of operation are given in IAEA “Fast Reactor Database,” IAEA-TECDOC-1531, 2006 8 Module 1 – Introduction Details of all SFRs can be found in reference 1. Ref 1. International Atomic Energy Agency, Fast Reactor Database, 2006 Update, IAEA‐ TECDOC‐1531, December, 2006. 8 Summary of LMR Experience Dates of major events Plant Start of First electricity First full-power First criticality Final shutdown construction generation operation Rapsodie (France) 1962 January 1967 March 1967 April 1983 KNK-II (Germany) October 1972 April 1978 1978 October 1991 FBTR (India) 1972 October 1985 1994 1996 PEC (Italy) January 1974 Project canceled JOYO (Japan) February 1970 July 2003 October 2003 DFR (UK) 1954 1959 1962 1963 1977 BOR-60 (Russian 1964 1968 1969 1970 Federation) EBR-II (USA) June 1958 August 1964 1965 1998 Fermi (USA) August 1956 August 1963 August 1966 October 1970 1975 FFTF (USA) June 1970 February 1980 December 1980 1996 BR-10 (Russian 1956 1958 1959 December 2003 Federation CEFR (China) May 2000 To be determined Ref: International Atomic Energy Agency, Fast Reactor Database, 2006 Update, IAEA-TECDOC-1531, December 2006. 9 Module 1 – Introduction Ref: International Atomic Energy Agency, Fast Reactor Database, 2006 Update, IAEA‐ TECDOC – 1531, December 2006, p14. 9 Summary of LMR Experience (continued) Plant Dates of major events (demonstration or Start of First electricity First full-power prototype fast First criticality Final shutdown reactors) construction generation operation Phenix (France 1968 1973 1973 March 1974 1973, finished in 1985; in 1991 the Government announced that SNR-300 should not proceed to commence SNR-300 (Germany operation PFBR (India) 2003 To be determined MONJU (Japan) 1985 1994 1995 PFR (UK) 1966 1974 1975 1977 March 1994 CBRBP (USA) Project canceled BN-350 (Kazakhstan) 1964 November 1972 1973 Mid-1973 April 1999 BN-600 (RF) 1967 February 1980 April 1980 December 1981 Not determined ALMR (USA) Not determined Kalimer-150 Not determined (Republic of Korea) SVBR-75/100 (RF) To be determined BREST-OD-300 (RF) To be determined 10 Module 1 – Introduction BN‐600 is discussed in more depth in the Module 9 – Selected SFR Operating Experience 10 Summary of LMR Experience (continued) Plant Dates of major events (commercial size Start of First electricity First full-power First criticality Final shutdown reactors) construction generation operation Super-Phenix 1 1976 1985 1986 1986 1998 (France) Super-Phenix 2 Project subsumed into EFR (France) SNR 2 (Germany Project subsumed into EFR DFBR (Japan) Not determined CDFR (UK) Project subsumed into EFR BN-1600 (RF) Project subsumed into BN-1800 BN-800 (RF) 2002 2012 (planned) 2014 EFR Not determined ALMR (USA) Not determined SVBR-75/100 (RF) Not determined BN-1800 (RF) Not determined BREST-1200 (RF) Not determined JSFR-1500 (Japan) Not determined 11 Module 1 – Introduction These slides indicate that many advanced nations have pursued SFR breeder technology, but the various European efforts have been subsumed into the EFR program, which has not led to a construction decision. The CRBR (Clinch River Breeder Reactor) design was significantly completed when it was cancelled. 11 Loop and Pool Designs • Two major types of layouts have been considered for SFRs—LOOP and POOL types. These are described in more depth later. • The LOOP type has the components separated and connected by piping, where the POOL type has the core, pumps, intermediate heat exchangers, etc., internal to a primary sodium pool 12 Module 1 – Introduction 12 Example of Loop Configuration FFTF Loop-Type Primary and Secondary Systems Ref: J. Cahalan, Sodium Fast Reactor, NRC White Flint, 6-21-07, Rev. Oct. 2008—Components are separated, housed in separate cells, and connected by piping. 13 Module 1 – Introduction Ref: Cahalan, J., Sodium Fast Reactor, NRC White Flint, 6‐21‐07 rev Oct 2008 Components are separated, housed in separate cells, and connected by piping 13 Example of Pool Configuration • Core, primary piping, IHX, and primary pumps are in a pool of sodium Steam generator and balance of plant are external to pool, connected through an intermediate heat transfer system. Ref: http://ne.doe.gov/geniv/document/gen iv roadman/pdf 14 Module 1 – Introduction Reference: http://ne.doe.gov/gen iv/document/gen iv roadmap/pdf Core, pumps, primary sodium, IHX, in pool of sodium. Only steam generator is external to pool. 14 Key SFR Characteristics Compared to LWRs COOLANT FLUID Liquid sodium (SFR) Water (LWR) • Highly reactive with air or • Compatible with air water • Low boiling point (100C at • High boiling point (980C at 1 atm) 1 atm) • High-pressure operation (14 • Low pressure operation MPa for PWRs, 10 MPa for ~1 atm (0.1 MPa pump head BWRs) plus static head) • Low thermal conductivity • Very high thermal • Highly corrosive (requires conductivity Zircaloy cladding) • Compatible with appropriate • Transport of mostly corrosion structural materials (mostly products stainless steels) • Transparent • Activates to 24Na and 22Na under neutron irradiation • Opaque 15 Module 1 – Introduction 15 Key SFR Characteristics Compared to LWRs (cont.) PLANT SYSTEMS SFR LWR • Low-pressure operation • High-pressure operation • Thin vessels • Thick vessels • Need for nonreactive cover gas • Opaqueness and chemical reactivity • No need for inert cover gas (steam in complicates fuel handling—generally pressurizers) done with vessel head in place • Fuel handling easier because of “direct” • High temperatures allow more efficient access (vessel head off) power conversion system • Temperatures limited by water • Requires intermediate coolant loop pressurization limits • No concerns for thermal shock • Intermediate
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