US3856517A - Irradiation swelling resistant alloy for use in fast neutron reactors - Google Patents

Irradiation swelling resistant alloy for use in fast neutron reactors Download PDF

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Publication number
US3856517A
US3856517A US00419017A US41901773A US3856517A US 3856517 A US3856517 A US 3856517A US 00419017 A US00419017 A US 00419017A US 41901773 A US41901773 A US 41901773A US 3856517 A US3856517 A US 3856517A
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United States
Prior art keywords
irradiation
silicon
fast
swelling
neutron
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US00419017A
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English (en)
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J Bates
J Straalsund
J Holmes
M Paxton
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US Atomic Energy Commission (AEC)
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US Atomic Energy Commission (AEC)
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Priority to US00419017A priority Critical patent/US3856517A/en
Priority to GB4840374A priority patent/GB1435290A/en
Priority to FR7438616A priority patent/FR2252415B3/fr
Priority to DE19742455894 priority patent/DE2455894A1/de
Priority to JP49135239A priority patent/JPS5084413A/ja
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    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C38/00—Ferrous alloys, e.g. steel alloys
    • C22C38/18—Ferrous alloys, e.g. steel alloys containing chromium
    • C22C38/40—Ferrous alloys, e.g. steel alloys containing chromium with nickel
    • C22C38/44—Ferrous alloys, e.g. steel alloys containing chromium with nickel with molybdenum or tungsten
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C38/00—Ferrous alloys, e.g. steel alloys
    • C22C38/001—Ferrous alloys, e.g. steel alloys containing N
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/06—Casings; Jackets
    • G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the basic composition in weight percent is, in addition to iron, chromium, 16.0 to 18.0; nickel, 11.0 to 14.0; molybdenum, 2.0 to 4.0; silicon, 1.1 to 2.0; manganese, 1.00 to 2.00; nitrogen, 0.04 to 0.06; carbon, 0.04 to 0.08; with certain limitation on other minor constituents.
  • the core structures of nuclear reactors impose severe material problems because of the high temperatures, mechanical stresses, exposure to flowing coolants, and as a unique problem, neutron irradiation.
  • a class of materials that has found wide acceptance is that of the stainless steels. They have been used both for the structural components and for the fuel tubes. The latter are long tubes of small, typically A to inch diameter and one to a few hundredths inch in thickness. They are filled with the nuclear fuel, usually uranium dioxide, plutonium dioxide or a mixture of the two. They are located closely adjacent to each other and are surrounded by the coolant.
  • the coolant is usually water, although in some cases carbon dioxide or helium is used.
  • the radiation causes dissociation of the water into hydrogen and oxygen.
  • the austenitic stainless steels, particularly AISI types 304 and 316 have excellent resistance to corrosion under these conditions.
  • the coolant is usually molten sodium, which is very corrosive to ferritic steels.
  • the austenitic stainless steels show excellent resistance to corrosion by sodium. They also have excellent high temperature mechanical properties.
  • fast power reactors which are usually cooled by molten sodium, are expected to subject some of the materials to fast fluences of at least 1.5 X 10 n/cm and perhaps 10 n/cm at temperatures in the range of 600 F to l,500 F. Volume increases in excess of 10% have already been observed in an existing fast neutron reactor. the EBR-II near Idaho Falls, Idaho. Swelling of this magnitude is unacceptable for power reactors.
  • the core is formed of hexagonal ducts which are closed packed. Some of these ducts enclose assemblies of fuel elements, while in others there are control rods containing neutron absorbers. Swelling in the ducts is particularly troublesome because gradients in swelling give rise to large amounts of bending and distortion.
  • AISI 316 is the preferred material for the fuel tubes and the ducts. since it exhibits less swelling than AISI 304, the other stainless steel commonly used in nuclear reactors, apparently due to its molybdenum content of 2.0 to 3.0 percent by weight. Nevertheless. as indicated above. the problem persists.
  • the swelling behavior of metal under neutron irradiation is a function both of the fluence and of operating temperature. This results in a rather complex relationship.
  • the coolant ordinarily enters at one end of the fuel elements, flows along them and exits at the other end. The temperature is therefore lowest at one end of the fuel rodsand highest at the other end.
  • the neutron flux, and therefore the total fluence received by the material follows the wellknown cosine law with the maximum at the midpoint of the fuel rod.
  • the expected conditions for a typical liquid metal cooled fast breeder reactor are shown approximately in FIG. 2.
  • the solid curve shows the expected fluence along the reactor axis and the dotted curve shows the mid-wall cladding temperature under full power operating conditions. For this particular reactor, it is expected that the most severe swelling will occur at a.
  • Our invention involves an alloy which exhibits, as compared to AISI 304 and 316 stainless steels, reduced void formation even in the annealed condition, improved high temperature yield strength and ultimate tensile strength to withstand the high stresses generated in LMFBR (liquid metal cooledfast breeder reactor) components, and improved cold work stability. It has fabrication characteristics (i.e., forgeability, weldability) comparable to AISI 304 and 316 stainless steels.
  • the new steel is an A181 316 steel modified to have a specific range of silicon content considerably greater than that of the usual AISI 316 steel. Since type 316 differs from type 304 in having a higher molybdenum content, the new steel differs from AISI 304 in having both higher molybdenum and higher silicon contents. Preferably. the molybdenum content is somewhat higher than the usual 316 steel.
  • the new steel contains specific quantities of carbon and manganese falling within the AISI 316 range, which are necessary to restrain void formation, yet not produce undue hardening. It also contains specific quantities of nitrogen to give the proper mechanical properties while limiting the effects of neutron irradiation. Limits are placed on other minor constituents.
  • FIG. 1 is a graph showing qualitatively the relationship of swelling and fluence due to different swelling mechanisms.
  • FIG. 2 is a graph showing typical operating temperatures and fluence at different points in a fast reactor core.
  • FIG. 3 is a graph showing change in density on neutron irradiation of basically AISI 316 stainless steels containing varying amounts of silicon.
  • FIG. 4 is a semi-logarithmic graph showing the number of voids per cubic centimeter produced by neutron irradiation of basically AISI 316 stainless steels containing varying amounts of silicon.
  • FIGS. 5a and 5b are graphs showing the high temperature yield strengths and ultimate strengths respectively of basically AISI 316 stainless steels containing varying amounts of silicon.
  • FIG. 6 is a graph showing the recrystallization temperatures of cold worked basically AISI 316 stainless steels containing varying amounts of silicon.
  • FIG. 7 is a graph showing high temperature ductilities of basically AISI 316 stainless steels containing various amounts of silicon.
  • silicon is believed to be the most potent because of the following criteria that it meets: (I) It exhibits a high degree of chemical interaction (compound formation) with the principle constituents in the steel; (2) it has a high solubility limit in the steel which allows it to be atomistically dispersed in the matrix; (3) it is a substitutional impurity (occupies normal lattice site when in solution) and therefore has a very low mobility; and (4) its concentration range inthe alloy is sufficiently low that the electronic bonding state around the impurity is drastically different from the electronic configuration around the majority of lattice sites (i.e., the electronic state in the immediate vicinity of a lattice site is occupied by silicon is vastly different from the electronic state in the vicinity of a lattice site occupied by a chromium, iron, or nickel atom).
  • the steel it is necessary that the steel contain specific proportions of molybdenum, manganese, and carbon in order to possess thet desired resistance to void formation although these proportions may overlap or fall within the normal limits of AISI 316 stainless steel. It should also contain limited amounts of nitrogen to give the proper mechanical property for nu clear use. Too much nitrogen is undesirable; however, because the neutron reaction with nitrogen involves the emission of alpha radiation which is damaging to the metal.
  • the amounts of cobalt and boron should be kept as low as possible since both are neutron poisons which reduce the performance of the reactor and the neutron reaction with cobalt produces cobalt-6O which emits hard gamma radiation and has a long half life, making it difficult to handle the equipment after it has been used in the reactor.
  • Copper, phosphorus and sulfur are limited because of their adverse effects on mechanical properties.
  • compositions of the alloys constituting this invention are listed in Table I.
  • a silicon content of about 1.1% to 2.0% therefore produces a dramatic improvement. There is nothing to indicate that, in this respect, further increase in silicon concentration would be disadvantageous. However, too high a silicon content has adverse effects on weldture, heating various samples to various temperatures,
  • the high temperature ductilities were determined by measuring the tensile elongation at 1,400 F. Results are plotted in FIG. 7. The data results are too scattered to definitely indicate a trend. but there appears to be no adverse effect from increased silicon content.
  • FIGS. 5a and 5b Still other samples which had received the 20% cold work were subjected to tensile tests at 1,400 F and the 0.2% yield strength and ultimate strength determined. The results are plotted in FIGS. 5a and 5b, FIG. 5a showing the yield strength and FIG. 5b the ultimate strength in "kilopounds" per square inch. Note that increasing the silicon content increases both the yield point and the ultimate strength.
  • a stainless steel alloy resistant to void formation under irradiation by fast neutrons consisting essentially of the following:

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  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Metallurgy (AREA)
  • Physics & Mathematics (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Organic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Treatment Of Steel In Its Molten State (AREA)
  • Particle Accelerators (AREA)
US00419017A 1973-11-26 1973-11-26 Irradiation swelling resistant alloy for use in fast neutron reactors Expired - Lifetime US3856517A (en)

Priority Applications (5)

Application Number Priority Date Filing Date Title
US00419017A US3856517A (en) 1973-11-26 1973-11-26 Irradiation swelling resistant alloy for use in fast neutron reactors
GB4840374A GB1435290A (en) 1973-11-26 1974-11-08 Irradiation swelling resistant alloy for use in fast neutron reactors
FR7438616A FR2252415B3 (Direct) 1973-11-26 1974-11-25
DE19742455894 DE2455894A1 (de) 1973-11-26 1974-11-26 Stahllegierung
JP49135239A JPS5084413A (Direct) 1973-11-26 1974-11-26

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US00419017A US3856517A (en) 1973-11-26 1973-11-26 Irradiation swelling resistant alloy for use in fast neutron reactors

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JP (1) JPS5084413A (Direct)
DE (1) DE2455894A1 (Direct)
FR (1) FR2252415B3 (Direct)
GB (1) GB1435290A (Direct)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2318237A1 (fr) * 1975-07-16 1977-02-11 Us Energy Aciers allies austenitiques ayant une resistance accrue au gonflement produit par des neutrons rapides
US4361443A (en) * 1979-10-22 1982-11-30 Japan Atomic Energy Research Institute Solid solution strengthened iron-base austenitic alloy
US4560407A (en) * 1981-03-20 1985-12-24 Hitachi, Ltd. Alloy for use in a radioactive ray environment and reactor core members
US5680424A (en) * 1996-02-28 1997-10-21 Westinghouse Electric Corporation PWR radial reflector
US20230141492A1 (en) * 2021-11-10 2023-05-11 Westinghouse Electric Company Llc Bottom nozzle with protective insert

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP4625239B2 (ja) * 2003-03-24 2011-02-02 白川 利久 沸騰水型原子炉の冷却水出口温度高温化用高温燃料集合体
JP2007177259A (ja) * 2005-12-27 2007-07-12 Sumitomo Metal Ind Ltd 原子力用オーステナイト系ステンレス鋼およびその製造方法

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3301668A (en) * 1964-02-24 1967-01-31 Atomic Energy Authority Uk Stainless steel alloys for nuclear reactor fuel elements
US3523788A (en) * 1967-06-02 1970-08-11 United States Steel Corp Austenitic stainless steel of improved stress corrosion resistance
US3563728A (en) * 1968-03-12 1971-02-16 Westinghouse Electric Corp Austenitic stainless steels for use in nuclear reactors

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3301668A (en) * 1964-02-24 1967-01-31 Atomic Energy Authority Uk Stainless steel alloys for nuclear reactor fuel elements
US3523788A (en) * 1967-06-02 1970-08-11 United States Steel Corp Austenitic stainless steel of improved stress corrosion resistance
US3563728A (en) * 1968-03-12 1971-02-16 Westinghouse Electric Corp Austenitic stainless steels for use in nuclear reactors

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2318237A1 (fr) * 1975-07-16 1977-02-11 Us Energy Aciers allies austenitiques ayant une resistance accrue au gonflement produit par des neutrons rapides
US4361443A (en) * 1979-10-22 1982-11-30 Japan Atomic Energy Research Institute Solid solution strengthened iron-base austenitic alloy
US4560407A (en) * 1981-03-20 1985-12-24 Hitachi, Ltd. Alloy for use in a radioactive ray environment and reactor core members
US5680424A (en) * 1996-02-28 1997-10-21 Westinghouse Electric Corporation PWR radial reflector
US20230141492A1 (en) * 2021-11-10 2023-05-11 Westinghouse Electric Company Llc Bottom nozzle with protective insert
US11817226B2 (en) * 2021-11-10 2023-11-14 Westinghouse Electric Company Llc Bottom nozzle with protective insert

Also Published As

Publication number Publication date
FR2252415B3 (Direct) 1977-08-26
JPS5084413A (Direct) 1975-07-08
FR2252415A1 (Direct) 1975-06-20
DE2455894A1 (de) 1975-05-28
GB1435290A (en) 1976-05-12

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