GB/T 10266-2008 English PDF (GB/T10266-2008)

GB/T 10266-2008: Specification for sintered uranium dioxide pellets
Delivery: 9 seconds. Download (& Email) true-PDF + Invoice.
Get Quotation: Click GB/T 10266-2008 (Self-service in 1-minute)
Historical versions (Master-website): GB/T 10266-2008
Preview True-PDF (Reload/Scroll-down if blank)

GB/T 10266-2008
GB
NATIONAL STANDARD OF THE
PEOPLE’S REPUBLIC OF CHINA
ICS 27.120.30
F 46
Replacing GB/T 10266-1998
Specification for sintered uranium dioxide pellets
ISSUED ON: JUNE 19, 2008
IMPLEMENTED ON: APRIL 01, 2009
Issued by: General Administration of Quality Supervision, Inspection and
Quarantine of PRC;
Standardization Administration of PRC.
Table of Contents
Foreword ... 3 
1 Scope ... 5 
2 Normative references ... 5 
3 Technical requirements ... 5 
4 Requirements of pellets batch ... 9 
5 Sampling ... 10 
6 Test and inspection ... 10 
7 Quality certification documents ... 11 
8 Packaging and transportation ... 11 
Appendix A (Informative) Comparison of clause number between this standard
and ASTM C 776:2006 ... 13 
Appendix B (Informative) The technical differences between this standard and
ASTM C 776:2006 and their reasons ... 14 
Appendix C (Informative) Load capacity test of pellets ... 15 
Specification for sintered uranium dioxide pellets
1 Scope
This standard specifies the technical requirements, pellet batches, sampling,
testing and inspection, packaging and transportation requirements for sintered
uranium dioxide pellets (hereinafter referred to as "pellets").
This standard is applicable to pellets with various 235U enrichments for nuclear
reactors.
This standard does not include the relevant content of the prevention of
criticality accidents and the requirements for safety and health. The use of this
standard shall also comply with relevant national regulations on nuclear
material control, transportation, handling, use.
2 Normative references
The provisions in following documents become the provisions of this Standard
through reference in this Standard. For the dated references, the subsequent
amendments (excluding corrections) or revisions do not apply to this Standard;
however, parties who reach an agreement based on this Standard are
encouraged to study if the latest versions of these documents are applicable.
For undated references, the latest edition of the referenced document applies.
GB/T 10265 Specification for nuclear grade sinterable uranium dioxide
powder (GB/T 10265-2008, ASTM C753:2004, MOD)
GB 11806 Regulations for the safe transport of radioactive material (GB
11806-2004, IAEA Safety Standards Serries No. TS-R-1, 2003, IDT)
GB/T 13696 Specification for uranium hexafluoride enriched to less than 5%
235U
EJ/T 689 Testing method for the thermal-stability of sintered UO2 pellets
3 Technical requirements
3.1 Chemical requirements
All chemical analysis samples shall be representative AND meet the
requirements of Chapter 5. All chemical analysis methods shall adopt national
standards or industry standards, OR the methods agreed upon by both parties.
the buyer, such as the load-bearing capacity test. Refer to Appendix C for the
load-bearing capacity test method.
3.3.4.1 Surface cracks
a) Axial crack length (including cracks extending to the end of the pellet):
Less than one-half of the height;
b) Circumferential crack length: Less than one-third of the circumference.
3.3.4.2 Block loss
a) Cylindrical surface block loss
1) Cylindrical surface block loss: Less than 5% of the surface area of the
cylindrical surface of the pellet;
2) Maximum linear size: The maximum linear size shall be able to ensure
that, the fuel performance remains stable during use; its limit shall be
negotiated by the supplier and the demander.
b) Block loss at the end of pellet: less than 1/3 of the area of the end of the
pellet (can be detected by 1/3 of the circumference of the pellet end
defect).
3.3.5 Appearance quality of pellets
The surface of the finished pellets shall be free of visible slag and foreign matter,
such as oil stains and grinding media.
3.4 Marking
A mark or code shall be used to identify the 235U enrichment of the pellets.
3.5 Irradiation stability
In order to evaluate the radiation stability of pellets, EJ/T 689 shall be used for
thermal stability test.
4 Requirements of pellets batch
4.1 Pellets, which are made from the same batch of uranium dioxide powder,
meet the requirements of GB/T 10265, use the same group of process
parameters, are defined as a pellet batch.
4.2 The identification of a pellet batch shall be retained, throughout the
production process. In the whole process, it shall ensure the identity of batch
materials; it is not allowed for mixing of materials.
5 Sampling
5.1 Sampling, weighing, sample processing must be carried out, under
conditions that ensure that the sample is representative of the batch. The
sampling plan, which meets the acceptance criteria, shall be negotiated by both
the supplier and the buyer.
5.2 The purchaser has the right to select a representative sample from each
pellet batch, AND determine its chemical, nuclear or physical properties.
5.3 The batch of samples shall have a sufficient number of pellets, so that it can
carry out the quality inspection and arbitration test if necessary, at the supplier's
factory, as well as the acceptance test, at the buyer's factory, when necessary.
5.4 When necessary, the batch of samples for acceptance test at the buyer's
factory shall be put into a separate container; the batch number shall be clearly
marked; it can be shipped before or with the batch of pellets. The arbitration
samples shall be clearly marked AND kept in the supplier’s factory, until the
buyer formally accepts the batch of pellets.
6 Test and inspection
6.1 The supplier shall test samples, in accordance with the requirements
described in Chapter 5, to ensure that the pellets meet the requirements of
Chapter 3. All tests shall be carried out on the basis of technology, which is
agreed upon by the supplier and the buyer.
6.2 Within the time period, which is agreed upon between the supplier and the
buyer, the supplier shall save all results AND provide all results when required,
to prove that the pellets meet the requirements described in Chapter 3.
6.3 The buyer can use the samples, which are provided by the supplier, OR
samples, which are taken from the buyer's factory, for acceptance tests.
Acceptance shall be based on a batch of pellets; it shall depend on the material
properties, which meet the requirements of Chapter 3 OR the requirements
after amended according to the contract documents.
6.4 If there is a dispute over the analysis results, a third party, which is agreed
upon by the supplier and the buyer, shall be determined as the arbitrator.
GB/T 10266-2008
GB
NATIONAL STANDARD OF THE
PEOPLE’S REPUBLIC OF CHINA
ICS 27.120.30
F 46
Replacing GB/T 10266-1998
Specification for sintered uranium dioxide pellets
ISSUED ON: JUNE 19, 2008
IMPLEMENTED ON: APRIL 01, 2009
Issued by: General Administration of Quality Supervision, Inspection and
Quarantine of PRC;
Standardization Administration of PRC.
Table of Contents
Foreword ... 3 
1 Scope ... 5 
2 Normative references ... 5 
3 Technical requirements ... 5 
4 Requirements of pellets batch ... 9 
5 Sampling ... 10 
6 Test and inspection ... 10 
7 Quality certification documents ... 11 
8 Packaging and transportation ... 11 
Appendix A (Informative) Comparison of clause number between this standard
and ASTM C 776:2006 ... 13 
Appendix B (Informative) The technical differences between this standard and
ASTM C 776:2006 and their reasons ... 14 
Appendix C (Informative) Load capacity test of pellets ... 15 
Specification for sintered uranium dioxide pellets
1 Scope
This standard specifies the technical requirements, pellet batches, sampling,
testing and inspection, packaging and transportation requirements for sintered
uranium dioxide pellets (hereinafter referred to as "pellets").
This standard is applicable to pellets with various 235U enrichments for nuclear
reactors.
This standard does not include the relevant content of the prevention of
criticality accidents and the requirements for safety and health. The use of this
standard shall also comply with relevant national regulations on nuclear
material control, transportation, handling, use.
2 Normative references
The provisions in following documents become the provisions of this Standard
through reference in this Standard. For the dated references, the subsequent
amendments (excluding corrections) or revisions do not apply to this Standard;
however, parties who reach an agreement based on this Standard are
encouraged to study if the latest versions of these documents are applicable.
For undated references, the latest edition of the referenced document applies.
GB/T 10265 Specification for nuclear grade sinterable uranium dioxide
powder (GB/T 10265-2008, ASTM C753:2004, MOD)
GB 11806 Regulations for the safe transport of radioactive material (GB
11806-2004, IAEA Safety Standards Serries No. TS-R-1, 2003, IDT)
GB/T 13696 Specification for uranium hexafluoride enriched to less than 5%
235U
EJ/T 689 Testing method for the thermal-stability of sintered UO2 pellets
3 Technical requirements
3.1 Chemical requirements
All chemical analysis samples shall be representative AND meet the
requirements of Chapter 5. All chemical analysis methods shall adopt national
standards or industry standards, OR the methods agreed upon by both parties.
the buyer, such as the load-bearing capacity test. Refer to Appendix C for the
load-bearing capacity test method.
3.3.4.1 Surface cracks
a) Axial crack length (including cracks extending to the end of the pellet):
Less than one-half of the height;
b) Circumferential crack length: Less than one-third of the circumference.
3.3.4.2 Block loss
a) Cylindrical surface block loss
1) Cylindrical surface block loss: Less than 5% of the surface area of the
cylindrical surface of the pellet;
2) Maximum linear size: The maximum linear size shall be able to ensure
that, the fuel performance remains stable during use; its limit shall be
negotiated by the supplier and the demander.
b) Block loss at the end of pellet: less than 1/3 of the area of the end of the
pellet (can be detected by 1/3 of the circumference of the pellet end
defect).
3.3.5 Appearance quality of pellets
The surface of the finished pellets shall be free of visible slag and foreign matter,
such as oil stains and grinding media.
3.4 Marking
A mark or code shall be used to identify the 235U enrichment of the pellets.
3.5 Irradiation stability
In order to evaluate the radiation stability of pellets, EJ/T 689 shall be used for
thermal stability test.
4 Requirements of pellets batch
4.1 Pellets, which are made from the same batch of uranium dioxide powder,
meet the requirements of GB/T 10265, use the same group of process
parameters, are defined as a pellet batch.
4.2 The identification of a pellet batch shall be retained, throughout the
production process. In the whole process, it shall ensure the identity of batch
materials; it is not allowed for mixing of materials.
5 Sampling
5.1 Sampling, weighing, sample processing must be carried out, under
conditions that ensure that the sample is representative of the batch. The
sampling plan, which meets the acceptance criteria, shall be negotiated by both
the supplier and the buyer.
5.2 The purchaser has the right to select a representative sample from each
pellet batch, AND determine its chemical, nuclear or physical properties.
5.3 The batch of samples shall have a sufficient number of pellets, so that it can
carry out the quality inspection and arbitration test if necessary, at the supplier's
factory, as well as the acceptance test, at the buyer's factory, when necessary.
5.4 When necessary, the batch of samples for acceptance test at the buyer's
factory shall be put into a separate container; the batch number shall be clearly
marked; it can be shipped before or with the batch of pellets. The arbitration
samples shall be clearly marked AND kept in the supplier’s factory, until the
buyer formally accepts the batch of pellets.
6 Test and inspection
6.1 The supplier shall test samples, in accordance with the requirements
described in Chapter 5, to ensure that the pellets meet the requirements of
Chapter 3. All tests shall be carried out on the basis of technology, which is
agreed upon by the supplier and the buyer.
6.2 Within the time period, which is agreed upon between the supplier and the
buyer, the supplier shall save all results AND provide all results when required,
to prove that the pellets meet the requirements described in Chapter 3.
6.3 The buyer can use the samples, which are provided by the supplier, OR
samples, which are taken from the buyer's factory, for acceptance tests.
Acceptance shall be based on a batch of pellets; it shall depend on the material
properties, which meet the requirements of Chapter 3 OR the requirements
after amended according to the contract documents.
6.4 If there is a dispute over the analysis results, a third party, which is agreed
upon by the supplier and the buyer, shall be determined as the arbitrator.