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GB/T 10265-2026Specification for nuclear grade sinterable uranium dioxide powder (English PDF)

核级可烧结二氧化铀粉末技术条件

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Issued by

SAMR; SAC

Level / Type

National · Recommended

Issue date

July 30, 2026

Implementation date

February 1, 2027

Scope

GB/T 10265-2026 is the English-translated version of 核级可烧结二氧化铀粉末技术条件.

GB/T 10265-2026 is the Chinese standard "Specification for nuclear grade sinterable uranium dioxide powder". Its scope clause reads: This document specifies the technical requirements, batch requirements, sampling, and inspection procedures for nuclear-grade sinterable uranium dioxide powder (hereinafter referred to as "uranium dioxide powder").

The document describes the receipt, certification documents, packaging, marking, transportation, and storage, and the corresponding test methods. This document applies to the manufacture, inspection, acceptance, packaging, and transportation of any 235U enriched uranium dioxide powder for pressurized water reactor pellets.

For other types of core blocks, the powder used should be followed accordingly. Its clauses include terms and definitions; technical requirements.

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Document preview — GB/T 10265-2026

National Standard of the People's Republic of China

ICS: 27.120.30
Classification: F 46
Replacing: GB/T 10265-2008

Issued by: State Administration for Market Regulation; Standardization Administration of the PRC

Preface
1.Scope
2 Normative References
3.Terms and Definitions
4.Technical Requirements
5.Powder batch requirements
6.Sampling
7.Test Methods
8.Acceptance
10 Packaging, labeling, transportation, and storage
Appendix A (Informative) Equivalent Boron Factor
Appendix B (Informative) Sinterability Test

1 Scope

This document specifies the technical requirements, batch requirements, sampling, and inspection procedures for nuclear-grade sinterable uranium dioxide powder (hereinafter referred to as "uranium dioxide powder").

The document describes the receipt, certification documents, packaging, marking, transportation, and storage, and the corresponding test methods.

This document applies to the manufacture, inspection, acceptance, packaging, and transportation of any 235U enriched uranium dioxide powder for pressurized water reactor pellets.

For other types of core blocks, the powder used should be followed accordingly.

2 Normative references

The contents of the following documents, through normative references within the text, constitute essential provisions of this document. Dated citations are not included.

For references to documents, only the version corresponding to that date applies to this document; for undated references, the latest version (including all amendments) applies.

This document.

GB/T 4960.3 Nuclear Science and Technology Terminology Part 3.Nuclear Fuel and Nuclear Fuel Cycle

GB 11806 Safe Transport Procedures for Radioactive Materials

GB/T 11843 Determination of Nitrogen in Uranium Dioxide Powder and Pellet - Spectrophotometric Method

GB/T 11844 Determination of Fluorine and Chlorine in Uranium Dioxide Powder and Chips - High-Temperature Hydrolysis-Ion Selective Electrode Method

GB/T 11847 Determination of Specific Surface Area of Uranium Dioxide Powder by BET Volumetric Method

GB/T 13372 Determination of Impurity Elements in Uranium Dioxide Powder and Bulk by Inductively Coupled Plasma Atomic Emission Spectrometry

GB/T 13696 Technical conditions for enriched uranium hexafluoride with an abundance of less than 5% (235U)

GB/T 13697 Determination of Carbon in Uranium Dioxide Powder and Pellets - High Frequency Induction Furnace Combustion-Infrared Detection Method

GB 18871 Basic Standards for Ionizing Radiation Protection and Radiation Source Safety

EJ/T 564 Requirements for Packaging, Transportation, Loading and Unloading, Receiving, Storage and Maintenance of Items for Nuclear Power Plants

EJ/T 898 Determination of Loose and Tap Density of Uranium Dioxide Powder

EJ/T 973 Determination of Uranium Isotope Abundance in Uranium Dioxide Powder and Pellet - Thermoionization Mass Spectrometry

3 Terms and Definitions

The terms and definitions defined in GB/T 4960.3 apply to this document.

4 Technical Requirements

4.1 Chemical Requirements

4.1.1 Uranium content

The minimum uranium content is 87.0% (mass fraction, dry basis).

4.1.2 Oxygen-to-uranium ratio (O/U)

The oxygen-to-uranium ratio (O/U) of uranium dioxide powder should be controlled between 2.02 and 2.18.

......
This preview omits tables, figures, formulas and parts of the technical clauses. The complete document — 15 pages — is available in the English PDF.

Referenced standards

Cited by

GB/T 10266-2008Specification for sintered uranium dioxide pellets

Editions of GB/T 10265

Edition	Title	Revision	Status
GB/T 10265-2026	Specification for nuclear grade sinterable uranium dioxide powder	current edition	Current
GB/T 10265-2008	Specification for nuclear grade sinterable uranium dioxide powder	previous edition	In force until 1 February 2027

This page sells the current edition, GB/T 10265-2026. Earlier editions are listed for reference only.

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