ASTM C753-99
(Specification)Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
SCOPE
1.1 This specification covers nuclear-grade, sinterable uranium dioxide powder. It applies to uranium dioxide powder containing uranium of any 235 U concentration for use in nuclear reactors.
1.2 This specification recognizes the presence of reprocessed uranium in the fuel cycle and consequently defines isotopic limits for commercial grade UO 2 . Such commercial grade UO 2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unreprocessed uranium. UO 2 falling outside these limits cannot necessarily be regarded as equivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design.
1.3 This specification does not include provisions for preventing criticality accidents or requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all international, national, or federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material.
1.4 Special tests and procedures are given in Annex A1.
1.5 This specification refers expressly to UO 2 powder before the addition of any die lubricant, binder, or pore former. If powder is sold with such additions, sampling procedures or allowable impurity contents, or both, may need to be modified by agreement between the buyer and the seller.
1.6 The following safety hazards caveat pertains to the test methods portion in the annexes of this specification: This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.
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Designation: C 753 – 99
Standard Specification for
Nuclear-Grade, Sinterable Uranium Dioxide Powder
This standard is issued under the fixed designation C 753; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (e) indicates an editorial change since the last revision or reapproval.
INTRODUCTION
This specification is intended to provide the nuclear industry with a general specification for
sinterable uranium dioxide powder. It recognizes the diversity of manufacturing methods by which
uranium dioxide powders are produced and the many special requirements for chemical and physical
characterization which may be imposed by the end use of the powder in a specific reactor system. It
is, therefore, anticipated that the buyer may supplement this specification with additional requirements
for specific applications.
1. Scope standard does not purport to address all of the safety concerns,
if any, associated with its use. It is the responsibility of the user
1.1 This specification covers nuclear-grade, sinterable ura-
of this standard to establish appropriate safety and health
nium dioxide powder. It applies to uranium dioxide powder
practices and determine the applicability of regulatory limita-
containing uranium of any U concentration for use in
tions prior to use.
nuclear reactors.
1.2 This specification recognizes the presence of repro-
2. Referenced Documents
cessed uranium in the fuel cycle and consequently defines
2.1 ASTM Standards:
isotopic limits for commercial grade UO . Such commercial
B 329 Test Method for Apparent Density of Powders of
grade UO is defined so that, regarding fuel design and
Refractory Metals and Compounds by the Scott Volume-
manufacture, the product is essentially equivalent to that made
ter
from unreprocessed uranium. UO falling outside these limits
C 696 Test Methods for Chemical, Mass Spectrometric, and
cannot necessarily be regarded as equivalent and may thus
Spectrochemical Analysis of Nuclear-Grade Uranium Di-
need special provisions at the fuel fabrication plant or in the
oxide Powders and Pellets
fuel design.
C 859 Terminology Relating to Nuclear Materials
1.3 This specification does not include provisions for pre-
C 996 Specification for Uranium Hexafluoride Enriched to
venting criticality accidents or requirements for health and
Less than 5 % U
safety. Observance of this specification does not relieve the
C 1233 Practice for Determining Equivalent Boron Con-
user of the obligation to be aware of and conform to all
tents of Nuclear Materials
international, national, or federal, state, and local regulations
E 11 Specification for Wire-Cloth Sieves for Testing Pur-
pertaining to possessing, shipping, processing, or using source
poses
or special nuclear material.
E 105 Practice for Probability Sampling of Materials
1.4 Special tests and procedures are given in Annex A1.
2.2 ANSI Standard:
1.5 This specification refers expressly to UO powder be-
ANSI/ASME NQA-1 Quality Assurance Program Require-
fore the addition of any die lubricant, binder, or pore former. If
ments for Nuclear Facilities
powder is sold with such additions, sampling procedures or
2.3 Federal Regulation:
allowable impurity contents, or both, may need to be modified
Code of Federal Regulations, Title 10, Chapter 1, Nuclear
by agreement between the buyer and the seller.
Regulatory Commission, Applicable Parts
1.6 The following safety hazards caveat pertains to the test
methods portion in the annexes of this specification: This
Annual Book of ASTM Standards, Vol 02.05.
Annual Book of ASTM Standards, Vol 12.01.
1 4
This specification is under the jurisdiction of ASTM Committee C-26 on Annual Book of ASTM Standards, Vol 14.02.
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel Available from American National Standards Institute, 11 W. 42nd St., 13th
and Fertile Material Specifications. Floor, New York, NY 10036.
Current edition approved June 10, 1999. Published September 1999. Originally Available from Standardization Documents, Order Desk, Building 4 Section D,
published as C 753 – 73. Last previous edition C 753 – 94. 700 Robbins Ave., Philadelphia, PA 19111–5094, Attn: NPODS.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
C 753
3. Terminology specified in C 996 for Commercial grade UF may be agreed
between the buyer and the seller since it is not a safety
3.1 Definitions—Definitions of terms are as given in Termi-
concern.
nology C 859.
4.5.2 For UO powder, not having an assay in the range set
forth in 4.5.1, the isotopic requirements shall be as agreed upon
4. Chemical Requirements
between the buyer and the seller.
4.1 Uranium Content— The uranium content shall be de-
4.6 Equivalent Boron Content—For thermal reactor use, the
termined on a basis to be agreed upon between the buyer and
total equivalent boron content (EBC) shall not exceed 4.0 μg/g
seller.
on a uranium weight basis. For purpose of EBC calculation B,
4.2 Oxygen-to-Uranium Ratio (O/U)—The O/U ratio may
Gd, Eu, Dy, Sm, and Cd shall be included in addition to
be specified as agreed upon between the buyer and seller. The
elements listed in Table 1. The method of performing the
determination of the O/U ratio shall be in accordance with Test
calculation shall be as indicated in Practice C 1233. For fast
Methods C 696 or demonstrated equivalent.
reactor use, the above limitation on EBC does not apply.
4.3 Impurity Content— The impurity content shall not
exceed the individual element limit specified in Table 1 on a
5. Physical Requirements
uranium weight basis. The summation of the contribution of
5.1 Particle Size— Based on visual observation, all of a
each of the impurity elements listed in Table 1 shall not exceed
representative sample of the UO shall pass through a 425-μm
1500 μg/g. If an element analysis is reported as “less than” a
(No. 40) standard sieve conforming to Specification E 11.
given concentration, this “less than” value shall be used in the
Particle size distribution and method of determination shall be
determination of total impurities. If an element analysis is
as agreed upon between the buyer and seller. Alternatively, as
reported as “less than” a given concentration, this “less than”
agreed upon between the buyer and the seller, the fraction not
value shall be used in the determination of total impurities.
passing through a 425-μm (No. 40) standard sieve shall be
4.4 Moisture Content— The moisture content shall not
reported to the buyer.
exceed 0.40 g/100 g uranium dioxide (UO ).
2 5.2 Bulk Density— The bulk density of UO powder will
4.5 Isotopic Content:
depend on the processing method. Unless otherwise agreed
4.5.1 For UO powder with an isotopic content of U upon between the buyer and seller, the bulk density shall be a
minimum of 625 kg/m as determined by Test Method B 329,
between that of natural uranium and 5 %, the isotopic limits of
Specification C 996 shall apply, unless otherwise agreed upon or an agreed upon alternative.
5.3 Sinterability— Test pellets shall be produced and mea-
between the buyer and the seller. If the U content is greater
than enriched commercial grade UF requirements, the isotopic sured in accordance with a sintering performance test agreed
upon between the buyer and seller. A sinterability performance
analysis requirements of Specification C 996 shall apply. The
specific isotopic measurements required by Specification test described in Annex A1 is presented as a guide.
C 996 may be waived, provided that the seller can demonstrate
compliance with Specification C 996, for instance, through the 6. Lot Requirements
seller’s quality assurance records. U content greater then one
6.1 A lot is defined as a quantity of UO powder that is
uniform in isotopic, chemical, physical, and sinterability char-
acteristics.
TABLE 1 Impurity Elements and Maximum Concentration Limits
6.2 The identity of a lot shall be retained throughout.
Maximum Concentration 6.3 A powder lot shall form the basis for defining sampling
Element
Limit of Uranium, μg/gU
plans used to establish conformance to this specification.
Aluminum 250
6.4 Sampling plans and procedures shall be mutually agreed
Carbon 100
upon by the buyer and the seller. A suggested sampling
Calcium + magnesium 200
procedure is given in Annex A2.
Chlorine 100
Chromium 200
Cobalt 100
7. Test Methods
Copper 250
Fluorine 100
7.1 The seller shall test the sample obtained per Annex A2
Iron 250
to ensure conformance of the powder to the requirements of
Lead 250
Sections 4 and 5.
Manganese 250
Molybdenum 250
7.1.1 All chemical analyses shall be performed on portions
Nickel 200
of the representative sample prepared in accordance with
Nitrogen 200
Annex A2. Analytical chemistry methods used shall be in
Phosphorus 250
Silicon 300
accordance with Test Methods C 696 or demon
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