ASTM C753-16a (2021) PDF

Full title and description

St ASTM C753-16a (2021) — Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder. This specification defines chemical and physical acceptance requirements, sampling, and test methods for sinterable uranium dioxide (UO2) powder intended for fabrication of nuclear fuel pellets. It applies to UO2 powders of any 235U concentration and addresses composition, impurities, moisture, isotopic limits for commercial-grade material, particle characteristics, bulk density and sinterability; it does not include criticality- or health-and-safety provisions.

Abstract

This standard covers nuclear‑grade, sinterable uranium dioxide (UO2) powder used as feedstock for manufacturing reactor fuel pellets. It specifies required chemical properties (uranium assay, oxygen‑to‑uranium ratio, individual and total impurity limits, moisture, isotopic/equivalent boron content) and physical properties (particle size distribution, bulk density, sinterability), and describes sampling and analytical test methods for acceptance. The document recognizes reprocessed uranium and defines isotopic limits for commercial‑grade UO2 so that products are comparable for fuel design and fabrication.

General information

• Status: Active (reapproved).
• Publication date: Current edition approved October 1, 2021; last updated October 22, 2021 (designation C753-16a (2021)).
• Publisher: ASTM International (American Society for Testing and Materials).
• ICS / categories: 27.120.30 — Fissile materials and nuclear fuel technology.
• Edition / version: C753-16a (2021) — reapproval of the 2016 revision.
• Number of pages: 5.

Scope

The specification applies to calcined UO2 powder prior to addition of any die lubricant, binder, or pore former and covers powders containing uranium with any 235U enrichment used to produce reactor fuel pellets. It establishes allowable chemical and physical limits, sampling procedures, and references analytical test methods. The standard does not address criticality control, shipping, handling, or occupational safety requirements, and users must comply with applicable regulatory and safety rules.

Key topics and requirements

• Uranium content and assay reporting (agreement on basis between buyer and seller).
• Oxygen-to-uranium (O/U) ratio specification and accepted test methods.
• Individual impurity element limits and total non-volatile oxide impurity ceilings.
• Moisture content limits (typically ≤ 0.50 wt% unless otherwise agreed).
• Isotopic content guidance and defined limits for commercial‑grade (including treatment of reprocessed uranium).
• Equivalent boron content determination and reporting where applicable.
• Physical requirements: particle size distribution, apparent/bulk density, and sinterability performance for pellet fabrication.
• Sampling requirements and referenced analytical/test methods (chemical analyses, particle sizing, density, sintering tests).
• Notes on buyer–seller agreement for powders supplied as press feed or containing additives (lubricants, binders, pore formers).

Typical use and users

Used by nuclear fuel manufacturers, powder suppliers, quality assurance and analytical laboratories, procurement and specification engineers in the nuclear fuel cycle, and regulators or inspectors assessing feedstock conformity for pellet fabrication. Also referenced by research groups and contract fabricators working with UO2 powder for light water reactor fuel production.

Related standards

Commonly referenced standards and documents include ASTM C696 (chemical analysis methods for UO2), C859 (terminology relating to nuclear materials), C996 (specification for uranium hexafluoride enriched to less than 5% 235U), C1233 (practice for determining equivalent boron contents), E11 (test sieves), E105 (probability sampling), ASME NQA‑1 (quality assurance for nuclear facility applications), and companion fuel/pellet specifications such as ASTM C776.

Keywords

nuclear-grade; uranium dioxide; UO2; sinterable powder; fuel pellets; isotopic limits; impurities; oxygen-to-uranium ratio; sinterability; bulk density; particle size; equivalent boron; sampling; ASTM C753.

FAQ

Q: What is this standard?

A: ASTM C753-16a (2021) is the ASTM International standard specification that defines chemical and physical acceptance criteria, sampling, and test methods for nuclear‑grade, sinterable uranium dioxide powder used to make reactor fuel pellets.

Q: What does it cover?

A: It covers uranium assay, O/U ratio, individual and total impurity limits, moisture, isotopic and equivalent boron content, particle size, bulk density and sinterability requirements, plus sampling and analytical test method references. It does not cover safety, criticality control, or regulatory handling requirements.

Q: Who typically uses it?

A: Fuel fabricators, UO2 powder manufacturers and suppliers, QA/analytical labs, procurement/specification engineers, and regulatory or inspection bodies involved in nuclear fuel production and acceptance testing.

Q: Is it current or superseded?

A: The document is the reapproved 2016 revision designated C753-16a and the current edition was approved October 1, 2021 with an update recorded October 22, 2021. Users should verify with ASTM International for any subsequent revisions or amendments after that date.

Q: Is it part of a series?

A: It belongs to the body of ASTM standards maintained by Committee C26 (Nuclear Fuel Cycle) and Subcommittee C26.02 (Fuel and Fertile Material Specifications). It is commonly used alongside related ASTM specifications and test methods for uranium compounds and fuel pellets.

Q: What are the key keywords?

A: nuclear-grade, uranium dioxide, UO2, sinterable powder, fuel pellets, impurities, O/U ratio, isotopic content, sinterability, bulk density, ASTM C753.