Nuclear Power Industry
Special Alloys & Materials
Delivering vacuum-refined nickel-based superalloys, austenitic stainless steels, and pressure-vessel-grade low-alloy steels that meet the rigorous safety, purity, and long-term reliability requirements of pressurized water reactor (PWR) and boiling water reactor (BWR) power plants across North America and Europe.
The Global Nuclear Power Renaissance
Nuclear energy is undergoing a decisive revival across Europe and North America. As governments commit to net-zero carbon targets, nuclear power's unrivalled ability to deliver large-scale, dispatchable, carbon-free baseload electricity has moved it back to the centre of energy policy. France—home to 56 operating reactors generating nearly 70% of its national electricity—is constructing six new EPR2 units and has committed to an additional eight beyond those. The United Kingdom has revived its civil nuclear programme with the Hinkley Point C and Sizewell C projects, and Poland, Finland, the Netherlands, and Sweden are all advancing new-build or life-extension programmes. Across the Atlantic, the United States—which operates the world's largest reactor fleet—has extended the operating licences of dozens of plants beyond 60 years and is funding advanced reactor designs through the Department of Energy's Civil Nuclear Credit Program.
This global expansion places extraordinary demands on material suppliers. Every major component inside a nuclear power plant—from the reactor pressure vessel and steam generators to control rod drive mechanisms (CRDM), primary coolant piping, and pressurizer heater sleeves—must satisfy exacting metallurgical standards set by design codes such as ASME Section III (United States) and RCC-M (France and most of continental Europe). These codes specify not only chemical composition and mechanical properties but also the mandatory melting route, inclusion cleanliness, traceability from ingot to finished part, and independent third-party material certification.
Fushun Special Steel has invested systematically in the vacuum-melting and secondary-refining infrastructure required to manufacture nuclear-grade alloys to the highest internationally recognised standards. Our capability spans vacuum induction melting (VIM), vacuum arc remelting (VAR), electroslag remelting (ESR), and forge-quality billet, bar, ring, and plate production. The sections below introduce our principal product families for the nuclear power sector and provide a detailed account of our core VIM + VAR double-vacuum melting process.
Key Nuclear Components & Alloy Requirements
Modern light-water reactors contain thousands of safety-critical components, each governed by a distinct alloy specification. The table below maps the most demanding components to the principal grades in which Fushun Special Steel specialises.
| Component | Reactor Type | Material Category | Grade / Designation |
|---|---|---|---|
| Steam Generator Tubing | PWR (US / EU) | Nickel-Based Alloy | Alloy 690 / NCF 690 |
| Reactor Internals, Baffle Bolts | PWR / BWR | Nickel-Based Alloy | Alloy 625 / N06625 |
| CRDM Drive Shafts & Fasteners | PWR | Precipitation-Hardened Ni Alloy | Alloy 718 / N07718 |
| Intermediate Heat Exchangers | PWR / Gas-Cooled | Ni-Fe-Cr Alloy | Alloy 800H / W.Nr. 1.4958 |
| Waste & Reprocessing Equipment | All Types | Ni-Mo-Cr Alloy | Alloy C-276 / N10276 |
| Spent Fuel Storage & Piping | All Types | Ni-Fe-Cr-Mo Alloy | Alloy 825 / N08825 |
| Reactor Coolant Piping, Pump Casings | PWR / BWR | Austenitic Stainless Steel | 316LN / Z2 CND 17-12 |
| Core Structural Components, Shrouds | BWR / PWR | Austenitic Stainless Steel | 304L / 304LN |
| RPV Shell & Head (European) | PWR (France / Germany) | Low-Alloy Pressure Vessel Steel | 16MND5 / 20MnMoNi55 |
| RPV Shell & Head Forgings (US) | PWR / BWR (US-design) | Low-Alloy Pressure Vessel Steel | SA-508 Gr.3 Cl.1 |
Nickel-Based Superalloys for Nuclear Power
Nickel-based alloys are the cornerstone material family for modern PWR and BWR primary circuit construction. Their unique combination of high-temperature strength, outstanding resistance to stress corrosion cracking (SCC) in high-purity pressurised water, and full qualification under ASME Section III and RCC-M makes them irreplaceable in the most demanding reactor environments.
The primary coolant environment inside a pressurised water reactor is among the most aggressive in all of engineering: water at 315–325 °C, pressure up to 157 bar, dissolved hydrogen and boric acid chemistry, high-velocity flow, and cumulative neutron fluence sustained over a 60-year design life. Materials performing reliably in this environment must be manufactured to the highest possible cleanliness standards—meaning ultra-low sulfur, phosphorus, and oxygen levels, along with strict control of tramp elements such as lead, bismuth, and thallium that can cause liquid-metal embrittlement or accelerate intergranular SCC. These requirements are precisely why the double-vacuum melting route (VIM followed by VAR) is mandated or strongly preferred by all major reactor design codes for primary-circuit nickel alloy components.
Alloy 690 (Ni-30Cr-9Fe) is today the worldwide standard for PWR steam generator tubing. Its high chromium content (28–31%) imparts exceptional resistance to primary water stress corrosion cracking (PWSCC) and intergranular attack on the secondary side. It replaced Alloy 600 in all Western new-build PWR programmes from the mid-1980s onward and is the specified material in Westinghouse AP1000, EDF/Framatome EPR, and KEPCO APR1400 designs. Produced via VIM + VAR; available as seamless tube, bar, and forgings to ASME SB-163 and RCC-M M4103.
Alloy 625 combines high molybdenum (8–10%) and niobium (3.15–4.15%) additions for outstanding pitting and crevice corrosion resistance, with tensile strength up to 965 MPa in the cold-worked condition. Used for reactor internal components, baffle bolts, core barrel fasteners, and flux thimble tubes. Its excellent weldability also makes it a preferred cladding material for carbon and low-alloy steel components exposed to primary water.
Alloy 718 is a precipitation-hardened nickel superalloy offering the highest room-temperature yield strength (≥1034 MPa STA) among commonly used nuclear alloys. Strengthened by γ″ (Ni₃Nb) and γ′ precipitates, it retains excellent strength up to 650 °C. Its sluggish age-hardening response permits welding without immediate post-weld heat treatment. Tight control of the Nb-to-Ti ratio and Al content during VIM is essential to achieve the correct precipitate volume fraction.
Alloy 800H is an iron-nickel-chromium alloy (Ni 30–35%, Cr 19–23%) engineered for high-temperature service up to 900 °C. Its controlled carbon (0.05–0.10%) and coarse grain size (ASTM No. 5 or coarser) promote long-term creep resistance, making it the standard for intermediate heat exchangers in advanced gas-cooled reactors and secondary-side heat exchange in modern PWR designs. Listed under ASME Section III and RCC-M.
Alloy 825 provides outstanding corrosion resistance in both oxidising and reducing environments, including sulfuric acid, phosphoric acid, seawater, and liquid radioactive waste streams. Additions of molybdenum (2.5–3.5%), copper (1.5–3.0%), and titanium stabilise the alloy against intergranular attack across a wide pH and temperature range. Specified for spent fuel storage containers, liquid radioactive waste processing equipment, and reprocessing plant components.
Alloy C-276 (Ni-16Mo-15Cr-4W) is one of the most corrosion-resistant engineering alloys available. Its very low carbon (≤0.01%) and silicon (≤0.08%) contents minimise grain-boundary carbide precipitation in the weld heat-affected zone—critical in fabricated nuclear waste equipment. Specified for nuclear waste vitrification systems, off-gas scrubbing equipment, and aggressive chemical environments throughout the nuclear fuel cycle.
Alloy 600 (Ni-15Cr-8Fe) was the original material of choice for first- and second-generation PWR steam generator tubing. Although superseded by Alloy 690 for new-build, it remains in service in many operating plants and continues to be specified for nozzle safe ends, thermowells, reactor vessel head penetrations, and replacement parts in legacy plants where the original material must be matched to maintain code compliance and inspection baselines.
Alloy 725 is an age-hardenable variant of Alloy 625, offering significantly higher yield strength (≥827 MPa aged) while fully retaining the parent alloy's exceptional pitting and SCC resistance in primary water environments. Increasingly specified for pressure-boundary fasteners and high-strength structural members within the reactor coolant system where both elevated strength and long-term corrosion resistance must be achieved without compromising toughness.
Nuclear-Grade Stainless Steel & Low-Alloy Pressure Vessel Steel
Beyond nickel alloys, the primary circuit of a light-water reactor depends on austenitic stainless steels for piping and core structures, and on low-alloy ferritic steels for the reactor pressure vessel—product families in which Fushun Special Steel also holds deep manufacturing expertise.
For nuclear service, austenitic stainless steels must meet requirements substantially more stringent than their industrial counterparts. Radiation-induced segregation (RIS) and irradiation-assisted stress corrosion cracking (IASCC) are failure modes specific to in-core materials, and their susceptibility is influenced by minor chemistry variables—particularly nitrogen, carbon, and boron content—that must be tightly controlled during steelmaking. Nitrogen-alloyed variants (the "N" suffix grades) have become the default specification in post-1990 reactor designs because nitrogen simultaneously compensates for the strength reduction of low carbon and reduces segregation tendency under irradiation.
For reactor pressure vessel steels, the critical metallurgical requirement is the minimisation of copper, nickel, and phosphorus—elements that accelerate neutron irradiation embrittlement and reduce the upper-shelf energy of the Charpy impact curve over the reactor's service life. 16MND5, 20MnMoNi55, and SA-508 Gr.3 Cl.1 are all produced to specifications that place very tight upper limits on these trace elements and mandate thorough vacuum degassing and ladle refining.
Type 316LN is the standard austenitic stainless steel for nuclear reactor coolant system piping, pump casings, and nozzle forgings. The low-carbon chemistry (≤0.030%) eliminates sensitisation risk during welding, while the nitrogen addition (0.10–0.16%) compensates for the resulting strength reduction, ensuring compliance with ASME Section III minimum yield strength requirements at elevated temperatures. For critical primary circuit applications, Fushun produces 316LN via VIM + VAR; for secondary circuit service, EAF + AOD production is available.
Type 304L and its nitrogen-strengthened variant 304LN are used extensively for BWR core shrouds, fuel channel boxes, reactor internal structural components, and secondary circuit vessels and piping. Their broad ASME Section III and RCC-M qualification history and extensive documented field performance in operating reactors across the US, France, Germany, and Japan make them the default choice for non-pressure-boundary internal structures. Nuclear-grade 304L meets strict requirements for delta-ferrite content and boron (≤0.002%).
16MND5 (France, RCC-M) and 20MnMoNi55 (Germany, KTA) are the premier low-alloy ferritic steels for European reactor pressure vessel shells, closure heads, and main nozzles. Both are produced by vacuum-degassed EAF steelmaking followed by ladle refining to achieve ultra-low sulfur (≤0.005%), phosphorus (≤0.008%), copper (≤0.10%), and cobalt (≤0.03%)—the key to long-term resistance against neutron irradiation embrittlement. Their 40+ year service history in French, German, and Belgian reactors provides an unrivalled database for 60-year life extension assessments.
SA-508 Grade 3 Class 1 is the ASME Section III-specified low-alloy steel for reactor pressure vessel forgings in US-designed nuclear plants, including Westinghouse AP1000 and GE-Hitachi ABWR. The American counterpart to French 16MND5 and German 20MnMoNi55, it shares similar Mn-Mo-Ni chemistry (Mn 1.20–1.50%, Mo 0.45–0.60%, Ni 0.40–1.00%) with the same fundamental requirement for minimal copper, phosphorus, and cobalt to resist neutron irradiation embrittlement over a 60-year design life. Produced via EAF + ladle refining + vacuum degassing and supplied as large open-die forgings.
VIM + VAR: The Gold Standard for Nuclear-Grade Alloy Melting
The double vacuum melting route—Vacuum Induction Melting followed by Vacuum Arc Remelting—is the process foundation upon which Fushun Special Steel's nuclear alloy quality is built, and the mandatory or strongly preferred melting route under all major nuclear material codes.
Stage 1 — Vacuum Induction Melting (VIM)
In the VIM furnace, carefully selected virgin raw materials—electrolytic nickel, high-purity chromium, molybdenum, niobium, and other alloying additions—are charged into a magnesia or alumina crucible surrounded by an induction coil, all enclosed within an evacuated chamber maintained at pressures typically below 1 Pa. The induction heating rapidly melts the charge, and the controlled vacuum environment performs several critical metallurgical functions simultaneously.
First, dissolved gases are removed: hydrogen, nitrogen, and oxygen partial pressures are dramatically reduced, driving these elements out of solution and suppressing the formation of harmful oxide and nitride inclusions. Second, volatile tramp elements—lead, bismuth, tellurium, selenium, and thallium—which severely degrade hot workability and can promote liquid-metal embrittlement or accelerate intergranular SCC in service, are selectively evaporated under vacuum and removed from the melt. Third, precise chemistry control is achieved through sequential addition of alloying elements, with each addition verified by rapid optical emission spectrometry before the melt is tapped. For precipitation-hardening alloys such as Alloy 718, the exact Nb-to-Ti ratio and aluminium content must be controlled to narrow tolerances that directly govern the volume fraction and morphology of strengthening precipitates in the finished product.
Stage 2 — Vacuum Arc Remelting (VAR)
The VIM electrode is transferred to the VAR furnace, where it serves as the consumable electrode in a direct-current vacuum arc. The arc is struck between the electrode tip and the growing ingot in a water-cooled copper mold, melting the electrode at a precisely controlled rate and allowing clean metal to solidify upward in a shallow, near-flat molten pool. The entire remelting operation occurs under vacuum at pressures typically below 0.1 Pa, with continuous automatic control of arc current, voltage, electrode gap, and melt rate throughout the process cycle.
The VAR process delivers three transformative metallurgical benefits. First, macrosegregation is eliminated: the controlled directional solidification prevents solute redistribution, shrinkage pipe, and freckle formation that occur in conventionally poured ingots. Second, inclusions are dramatically reduced: remaining oxide or nitride particles float to the electrode top and are removed in the discard crop, ensuring the usable ingot body is essentially inclusion-free. Third, compositional homogeneity is maximised: the controlled solidification cycle progressively reduces micro-segregation at grain boundaries and within dendrites to levels unachievable by conventional melting, resulting in more consistent mechanical properties and improved fatigue performance throughout the entire product cross-section.
Why VIM + VAR Is Non-Negotiable for Nuclear Service
Nuclear operators and their regulators require mandatory documentation of the melting route as a procurement condition, retained for the lifetime of the component—often exceeding 60 years. ASME SB-163, SB-564, SB-166, and the corresponding RCC-M M-series material specifications all explicitly require or strongly prefer VIM + VAR double-vacuum melting for primary-circuit nickel alloy components. No alternative melting route can consistently achieve the required combination of low dissolved gas content, freedom from tramp elements, absence of large inclusions, and compositional homogeneity that nuclear service demands across a 60-year design life.
At Fushun Special Steel, our VIM + VAR production facility has been continuously upgraded to support nuclear-scale ingot production. Our nuclear quality management system operates under ISO 9001:2015 with nuclear-specific supplements, encompassing full first-article qualification, material test reports (MTRs), and certified material test certificates (CMTCs) traceable to individual heats and remelt sequences. For the most demanding applications, Fushun also offers triple-melt sequences (VIM + ESR + VAR or VIM + VAR + VAR) as specified by end users or design codes.
Code Compliance & Certifications
Supplying nuclear power plants demands the highest level of quality management, independent material certification, and full documentary traceability. Fushun Special Steel's nuclear product programme is built on a comprehensive foundation of internationally recognised codes and standards.
Nuclear material procurement is governed by a strict hierarchy of codes, standards, and owner specifications. Design codes—ASME Section III in the United States and RCC-M in France and most European PWR programmes—specify material properties, required melting routes, mandatory testing, documentation requirements, and authorised inspection agency involvement. Below these sit the material specifications: the ASME SB series for nickel and non-ferrous alloys, the ASME SA series for steels, and the RCC-M M-series.
Fushun Special Steel maintains a complete qualification programme supporting nuclear material procurement under all major applicable codes. Our quality management system includes nuclear-specific procedures for material certification, non-conformance control, concession management, and long-term records retention that satisfy the requirements of 10 CFR Part 50 Appendix B (US NRC Quality Assurance Criteria for Nuclear Power Plants) and IAEA Safety Guide GS-G-3.1. All material certificates are issued at EN 10204 Type 3.1 or Type 3.2 as specified by the customer. Fushun actively welcomes customer source inspections and witness testing at our melting and forging facilities.
Partner with Fushun Special Steel for Your Nuclear Programme
Our technical and commercial team is available to review your material specifications, discuss VIM + VAR qualification requirements, and propose the optimum alloy grade and product form for your application. Contact us for product datasheets, MTR samples, first-article qualification plans, and delivery schedules.
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