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Strategic Infrastructure

Nuclear Fuel Cycle & Radioactive Waste

Nuclear fuel cycle and radioactive waste covers the facilities that supply and close the nuclear fuel cycle, including uranium conversion, enrichment and fuel fabrication plants, reprocessing facilities, interim spent fuel stores and geological disposal facilities. One of the capabilities of Energy Infrastructure.

International families
2,1762015 to 2024
Leading country
United States2.0× the next
All families
12khome filings included
Over five years
Falling2020 to 2024 against the five before

Year by year

Patent families by country of origin and the year of the earliest filing, 2000 to 2025; 2025 is a part year, still filling in. International families are those for which protection was sought beyond one country.

Volume

International patent families in the capability, by the year of the earliest filing.

Source: Global Institute for National Capability (GINC), 2026. Underlying patents from 107 patent offices, IFI CLAIMS and Google

Share by country

Each country's share of the year's international families, in per cent: the capability's five largest countries of origin, 2015 to 2024, and the rest of the world.

Source: Global Institute for National Capability (GINC), 2026. Underlying patents from 107 patent offices, IFI CLAIMS and Google

Country leaderboard

International patent families, 2015 to 2024, by country of origin. Growth compares the latest five full years with the five before.

Ten largest

United States

South Korea

France

Japan

China

Germany

Russia

Canada

United Kingdom

Australia

589

294

275

227

207

146

84

47

34

27

2000 to 2025
1United States58927.1%1.0×
854
2South Korea29413.5%1.3×
1,573
3France27512.6%1.1×
360
4Japan22710.4%0.4×
2,071
5China2079.5%1.5×
5,639
6Germany1466.7%0.5×
214
7Russia843.9%0.4×
472
8Canada472.2%1.5×
61
9United Kingdom341.6%1.0×
55
10Australia271.2%0.6×
36
11Italy251.1%3.2×
32
12Belgium221.0%1.2×
22
13Spain200.9%1.2×
26
14Türkiye180.8%17×
25
15Taiwan160.7%0.8×
59
16Sweden160.7%0.5×
18
17Finland130.6%0.9×
14
18Switzerland120.6%0.7×
14
19Netherlands110.5%0.4×
11
20Czechia110.5%0.4×
29
21India100.5%2.3×
16
22Austria80.4%1.0×
8
23Israel60.3%1.0×
6
24Denmark60.3%–
6
25Singapore50.2%0.7×
5
26Norway50.2%0.7×
5
27Brazil40.2%3.0×
11
28Poland30.1%0.5×
17
29New Zealand30.1%0.5×
4
30Ireland20.1%–
2
31Hungary20.1%0.0×
7
32South Africa10.0%0.0×
1
33Saudi Arabia10.0%0.0×
4
34Portugal10.0%0.0×
1
35Mexico00.0%–
2
36Malaysia00.0%–
2

Applicants

The largest applicants by international patent families, 2015 to 2024: across the world, then within each of the five countries with the most families in Nuclear Fuel Cycle & Radioactive Waste. Names are as held in the source and are not consolidated across subsidiaries.

Global

2,176 international families

COMMISSARIAT ENERGIE ATOMIQUE · France

KOREA HYDRO & NUCLEAR POWER CO · South Korea

KOREA ATOMIC ENERGY RES · South Korea

WESTINGHOUSE ELECTRIC CO LLC · United States

CHINA GENERAL NUCLEAR POWER · China

CGN POWER CO LTD · China

92

67

59

50

35

33

United States

589 international families

WESTINGHOUSE ELECTRIC CO LLC

HOLTEC INTERNATIONAL

TERRAPOWER LLC

DEEP ISOLATION INC

SHINE TECHNOLOGIES LLC

BWXT ADVANCED TECH LLC

50

32

23

22

15

13

South Korea

294 international families

KOREA HYDRO & NUCLEAR POWER CO

KOREA ATOMIC ENERGY RES

KEPCO NUCLEAR FUEL CO LTD

KOREA RADIOACTIVE WASTE AGENCY

KOREA HYDRO NUCLEAR POWER CO LTD

KOREA ATOMIC ENERGY RESEARCH INST

67

58

27

18

8

5

France

275 international families

COMMISSARIAT ENERGIE ATOMIQUE

CENTRE NAT RECH SCIENT

FRAMATOME SA

ORANO NUCLEAR PACKAGES AND SERVICES

TN INT

ORANO CYCLE

92

25

25

25

23

20

Japan

227 international families

HITACHI GE NUCLEAR ENERGY LTD

EBARA CORP

NIPPON CHEMICAL IND

TOSHIBA KK

HITACHI LTD

MITSUBISHI HEAVY IND LTD

27

13

11

11

10

10

China

207 international families

CHINA GENERAL NUCLEAR POWER

CGN POWER CO LTD

CHINA NUCLEAR POWER TECHNOLOGY RES INST CO LTD

UNIV TSINGHUA

CHINA NUCLEAR POWER ENG CO LTD

CHINA NUCLEAR POWER INST CO LTD

35

33

25

22

19

18

Similar capabilities

The nine capabilities that share the most international patent families with Nuclear Fuel Cycle & Radioactive Waste, 2015 to 2024: the families counted in both as a share of those counted in either. Each card shows its five largest countries.

Critical Technology

Advanced Nuclear & Fusion

31.7% shared · 1,775 families in both

United States

China

South Korea

Japan

France

1,350

770

623

609

519

National Security

Stockpile Stewardship & Sustainment

16.7% shared · 364 families in both

United States

Japan

France

China

Germany

118

62

39

27

23

Strategic Infrastructure

Nuclear Generation

13.6% shared · 753 families in both

China

United States

South Korea

Japan

France

973

912

510

459

398

Critical Technology

Nuclear Medicine & Radioisotope Technologies

1.4% shared · 200 families in both

United States

China

Japan

Germany

South Korea

4,153

2,013

1,410

792

720

Trade & Investment

Strategic Supply Security

1.1% shared · 122 families in both

Japan

China

United States

South Korea

Germany

2,305

1,800

1,307

1,130

383

Strategic Infrastructure

Processing & Refining

1.0% shared · 279 families in both

United States

China

Japan

Germany

France

5,663

3,476

2,794

1,548

1,459

Strategic Infrastructure

Research & Scientific Facilities

0.9% shared · 49 families in both

United States

Japan

Germany

China

United Kingdom

964

589

405

369

209

Strategic Infrastructure

Water Supply & Treatment

0.8% shared · 219 families in both

United States

China

Japan

South Korea

Germany

5,013

4,301

3,866

1,986

1,665

Strategic Infrastructure

Wastewater & Sanitation

0.8% shared · 234 families in both

United States

China

Japan

South Korea

Germany

5,326

5,281

4,432

2,243

2,077

Crosswalk

How Nuclear Fuel Cycle & Radioactive Waste is matched to the patent classifications. The entries below were chosen for it; each stands for itself and everything beneath it in the scheme, 127 Cooperative entries in all. A patent family counts when any of its codes, in either scheme and at any office, falls under one of them. Codes since retired are placed under the entries that replaced them.

EntryTitle in the schemeWhy it is chosenCPC codesIPC codesDocuments
B01D59/00Separation of different isotopes of the same chemical elementIsotope separation, including uranium enrichment272922,573
C01G43/00Compounds of uraniumUranium compounds, including conversion products12810,570
C22B60/02Obtaining thorium, uranium, or other actinidesExtraction of uranium, thorium and other actinides24214,412
G21C21/02Manufacture of fuel elements or breeder elements contained in non-active casingsManufacture of reactor fuel elements887,811
G21C19/42Reprocessing of irradiated fuelReprocessing of irradiated nuclear fuel559,264
G21F5/00Transportable or portable shielded containersShielded casks for transport and storage of radioactive material161433,459
G21F9/00Treating radioactively contaminated material; Decontamination arrangements thereforTreatment and disposal of radioactive waste3519117,141

CPC and IPC codes are the codes in use on patent documents, at any office, that fall under the entry. Documents is the larger of the two schemes' counts of documents carrying one of them. An entry with no IPC codes can be told apart only in the Cooperative scheme.

The Cooperative codes in use that count towards Nuclear Fuel Cycle & Radioactive Waste: 127 codes on 137,647 documents. The full crosswalk is in the cpc-to-capability.csv download.

CodeTitleUnder entryHow placedDocuments
G21F9/12Processing by absorption; by adsorption; by ion-exchangeG21F9/00In the scheme6,848
G21C21/02Manufacture of fuel elements or breeder elements contained in non-active casingsG21C21/02In the scheme5,010
G21F9/30ProcessingG21F9/00In the scheme4,875
G21F9/02Treating gasesG21F9/00In the scheme4,645
G21F9/06ProcessingG21F9/00In the scheme4,467
G21F5/12Closures for containers; Sealing arrangementsG21F5/00In the scheme3,930
G21F9/28Treating solidsG21F9/00In the scheme3,650
G21F9/34Disposal of solid wasteG21F9/00In the scheme3,641
G21C19/46Aqueous processes, e.g. by using organic extraction means, including the regeneration of these meansG21C19/42In the scheme3,121
G21F9/36Disposal of solid waste by packaging; by balingG21F9/00In the scheme3,093
G21F5/008Containers for fuel elementsG21F5/00In the scheme2,970
G21F5/005Containers for solid radioactive wastes, e.g. for ultimate disposalG21F5/00In the scheme2,933
G21F5/015Transportable or portable shielded containers for storing radioactive sources, e.g. source carriers for irradiation units; Radioisotope containersG21F5/00In the scheme2,874
C22B60/026Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries liquid-liquid extraction with or without dissolution in organic solventsC22B60/02In the scheme2,592
G21F5/14Devices for handling containers or shipping-casks, e.g. transporting devices loading and unloading, filling of containersG21F5/00In the scheme2,587
G21F5/06Details of, or accessories to, the containersG21F5/00In the scheme2,497
C01G43/025Uranium dioxideC01G43/00In the scheme2,298
G21F5/10Heat-removal systems, e.g. using circulating fluid or cooling finsG21F5/00In the scheme2,262
G21F9/305Glass or glass like matrixG21F9/00In the scheme1,989
B01D59/34Separation by photochemical methodsB01D59/00In the scheme1,934
C01G43/00Compounds of uraniumC01G43/00In the scheme1,877
G21F9/00Treating radioactively contaminated material; Decontamination arrangements thereforG21F9/00In the scheme1,821
G21F9/004Decontamination of the surface of objects with chemical or electrochemical processes of metallic surfacesG21F9/00In the scheme1,803
G21F9/04Treating liquidsG21F9/00In the scheme1,789
G21F9/08Processing by evaporation; by distillationG21F9/00In the scheme1,766
G21F5/00Transportable or portable shielded containersG21F5/00In the scheme1,751
G21F9/001Decontamination of contaminated objects, apparatus, clothes, food; Preventing contamination thereofG21F9/00In the scheme1,673
C01G43/01Oxides; HydroxidesC01G43/00In the scheme1,654
G21F9/32Processing by incinerationG21F9/00In the scheme1,577
G21C19/48Non-aqueous processesG21C19/42In the scheme1,573
C22B60/0265Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries extraction by solid resinsC22B60/02In the scheme1,393
G21F9/008Apparatus specially adapted for mixing or disposing radioactively contamined materialG21F9/00In the scheme1,350
G21F5/012Fuel element racks in the containersG21F5/00In the scheme1,328
G21F5/08Shock-absorbers, e.g. impact buffers for containersG21F5/00In the scheme1,241
G21F9/16Processing by fixation in stable solid mediaG21F9/00In the scheme1,240
G21F9/14Processing by incineration; by calcination, e.g. desiccationG21F9/00In the scheme1,233
G21F9/304Cement or cement-like matrixG21F9/00In the scheme1,164
G21F9/002Decontamination of the surface of objects with chemical or electrochemical processesG21F9/00In the scheme1,162
G21F9/125Processing by absorption; by adsorption; by ion-exchange by solvent extractionG21F9/00In the scheme1,105
G21F9/10Processing by flocculationG21F9/00In the scheme1,101
C22B60/0291Obtaining thorium, uranium, or other actinides obtaining thoriumC22B60/02In the scheme1,021
G21F9/302Processing by fixation in stable solid media in an inorganic matrixG21F9/00In the scheme1,018
G21F9/165Cement or cement-like matrixG21F9/00In the scheme1,013
G21F9/007Recovery of isotopes from radioactive waste, e.g. fission productsG21F9/00In the scheme1,006
C22B60/04Obtaining plutoniumC22B60/02In the scheme997
C22B60/0278Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries by chemical methodsC22B60/02In the scheme989
B01D59/44Separation by mass spectrographyB01D59/00In the scheme969
G21F5/02Transportable or portable shielded containers with provision for restricted exposure of a radiation source within the containerG21F5/00In the scheme934
G21F9/22Disposal of liquid waste by storage in a tank or other containerG21F9/00In the scheme927
C22B60/02Obtaining thorium, uranium, or other actinidesC22B60/02In the scheme919
B01D59/26Separation by extracting by sorption, i.e. absorption, adsorption, persorptionB01D59/00In the scheme914
C22B60/0213Obtaining thorium, uranium, or other actinides obtaining uranium by dry processesC22B60/02In the scheme908
C01G43/06FluoridesC01G43/00In the scheme891
G21F9/162Processing by fixation in stable solid media in an inorganic matrix, e.g. clays, zeolitesG21F9/00In the scheme888
G21F9/307Processing by fixation in stable solid media in polymeric matrix, e.g. resins, tarsG21F9/00In the scheme888
B01D59/50Separation involving two or more processes covered by different groups selected from groups B01D59/02, B01D59/10, B01D59/20, B01D59/22, B01D59/28, B01D59/34, B01D59/36, B01D59/38, B01D59/44B01D59/00In the scheme856
B01D59/32Separation by chemical exchange by exchange between fluidsB01D59/00In the scheme808
G21F9/005Decontamination of the surface of objects by ablationG21F9/00In the scheme795
G21C19/44Reprocessing of irradiated fuel of irradiated solid fuelG21C19/42In the scheme736
G21F5/002Containers for fluid radioactive wastesG21F5/00In the scheme726
C22B60/0295Obtaining thorium, uranium, or other actinides obtaining other actinides except plutoniumC22B60/02In the scheme711
G21F9/167Processing by fixation in stable solid media in polymeric matrix, e.g. resins, tarsG21F9/00In the scheme707
B01D59/30Separation by chemical exchange by ion exchangeB01D59/00In the scheme702
G21F9/20Disposal of liquid wasteG21F9/00In the scheme693
G21F9/308Processing by melting the wasteG21F9/00In the scheme682
G21C19/42Reprocessing of irradiated fuelG21C19/42In the scheme676
B01D59/04Separation by phase transition by distillationB01D59/00In the scheme672
G21F5/018Syringe shields or holdersG21F5/00In the scheme666
G21F9/24Disposal of liquid waste by storage in the ground; by storage under water, e.g. in oceanG21F9/00In the scheme663
C22B60/0234Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors sulfurated ion as active agentC22B60/02In the scheme622
B01D59/18Separation by diffusion by separation jetsB01D59/00In the scheme605
B01D59/20Separation by centrifugingB01D59/00In the scheme593
B01D59/00Separation of different isotopes of the same chemical elementB01D59/00In the scheme566
G21C21/10Manufacture of fuel elements or breeder elements contained in non-active casings by extrusion, drawing, or stretching by rolling, e.g. "picture frame" techniqueG21C21/02In the scheme552
C22B60/0247Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using basic solutions or liquorsC22B60/02In the scheme516
C22B60/0208Obtaining thorium, uranium, or other actinides obtaining uranium preliminary treatment of ores or scrapC22B60/02In the scheme509
C22B60/0252Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurriesC22B60/02In the scheme499
C22B60/0239Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors nitric acid containing ion as active agentC22B60/02In the scheme457
G21F9/18Processing by biological processesG21F9/00In the scheme442
G21F9/301Processing by fixation in stable solid mediaG21F9/00In the scheme436
C01G43/066PreparationC01G43/00In the scheme433
C22B60/0226Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquorsC22B60/02In the scheme427
B01D59/12Separation by diffusion by diffusion through barriersB01D59/00In the scheme411
B01D59/48Separation by mass spectrography using electrostatic and magnetic fieldsB01D59/00In the scheme409
G21C21/04Manufacture of fuel elements or breeder elements contained in non-active casings by vibrational compaction or tamping of fuel in the jacketG21C21/02In the scheme408
B01D59/14Construction of the barrierB01D59/00In the scheme369
C22B60/0282Solutions containing P ions, e.g. treatment of solutions resulting from the leaching of phosphate ores or recovery of uranium from wet-process phosphoric acidC22B60/02In the scheme348
G21C19/50Reprocessing of irradiated fuel of irradiated fluid fuel, e.g. regeneration of fuels while the reactor is in operationG21C19/42In the scheme338
C22B60/0221Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leachingC22B60/02In the scheme331
G21F5/04Means for controlling exposure, e.g. time, size of apertureG21F5/00In the scheme330
C01G43/063Hexafluoride (UF6)C01G43/00In the scheme319
B01D59/40Separation by electrochemical methods by electrolysisB01D59/00In the scheme297
C01G43/003Preparation involving a liquid-liquid extraction, an adsorption or an ion-exchangeC01G43/00In the scheme289
B01D59/28Separation by chemical exchangeB01D59/00In the scheme286
G21C21/16Manufacture of fuel elements or breeder elements contained in non-active casings by casting or dipping techniquesG21C21/02In the scheme283
C01G43/006Compounds containing uranium, with or without oxygen or hydrogen, and containing two or more other elementsC01G43/00In the scheme277
B01D59/42Separation by electrochemical methods by electromigration; by electrophoresisB01D59/00In the scheme245
C22B60/0286Obtaining thorium, uranium, or other actinides obtaining uranium refining, melting, remelting, working up uraniumC22B60/02In the scheme244
G21C21/08Manufacture of fuel elements or breeder elements contained in non-active casings by a slip-fit cladding process by crimping the jacket around the fuelG21C21/02In the scheme237
B01D59/10Separation by diffusionB01D59/00In the scheme235
B01D59/38Separation by electrochemical methodsB01D59/00In the scheme229
G21F5/065Containers provided with a rotatable drumG21F5/00In the scheme206
B01D59/02Separation by phase transitionB01D59/00In the scheme203
G21C21/14Manufacture of fuel elements or breeder elements contained in non-active casings by plating the fuel in a fluidG21C21/02In the scheme200
B01D59/24Separation by extracting by solvent extractionB01D59/00In the scheme195
B01D59/22Separation by extractingB01D59/00In the scheme191
C22B60/0204Obtaining thorium, uranium, or other actinides obtaining uraniumC22B60/02In the scheme191
C22B60/023Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors halogenated ion as active agentC22B60/02In the scheme185
C22B60/0243Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes by leaching using acidic solutions or liquors phosphorated ion as active agentC22B60/02In the scheme164
C01G43/08ChloridesC01G43/00In the scheme163
G21C21/12Manufacture of fuel elements or breeder elements contained in non-active casings by hydrostatic or thermo-pneumatic canning in general by pressing without lengthening, e.g. explosive coatingG21C21/02In the scheme159
G21F5/125Means to monitor or detect the leak-tightness of the closureG21F5/00In the scheme140
B01D59/08Separation by phase transition by fractional crystallisation, by precipitation, by zone freezingB01D59/00In the scheme129
C22B60/0273Extraction by titanium containing adsorbents, e.g. by hydrous titanium oxideC22B60/02In the scheme125
C22B60/0217Obtaining thorium, uranium, or other actinides obtaining uranium by wet processesC22B60/02In the scheme118
C22B60/0256Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries using biological agents, e.g. microorganisms or algaeC22B60/02In the scheme117
B01D59/16Separation by diffusion by thermal diffusionB01D59/00In the scheme84
B01D59/46Separation by mass spectrography using only electrostatic fieldsB01D59/00In the scheme72
B01D59/33Separation by chemical exchange by exchange between fluids involving dual temperature exchangeB01D59/00In the scheme57
G21C21/06Manufacture of fuel elements or breeder elements contained in non-active casings by rotatable swaging of the jacket around the fuelG21C21/02In the scheme55
G21F9/26Disposal of liquid waste by dilution in water, e.g. in ocean, in streamG21F9/00In the scheme40
B01D59/36Separation by biological methodsB01D59/00In the scheme39
C01G43/04Halides of uraniumC01G43/00In the scheme33
C22B60/0269Extraction by activated carbon containing adsorbentsC22B60/02In the scheme29
C01G43/10BromidesC01G43/00In the scheme8
B01D59/06Separation by phase transition by fractional melting; by zone meltingB01D59/00In the scheme7
C01G43/12IodidesC01G43/00In the scheme3
Match: Direct
The capability is itself a technology or a kind of physical system, and the classification names it. B01D59/00 covers separation of isotopes of any element, not only uranium. The crosswalk is a first pass that nobody has reviewed.

Other capabilities in Energy Infrastructure