Commission of Science, Technology and Industry for National Defense
Issued on:
2006-12-15
Implemented on:
2007-5-1
Status:
valid
Language:
English
File Format:
PDF
Word Count:
3000 words
Price(USD):
60.0
Delivery:
via email in 1 business day
1 Scope
This standard specifies the safety criteria for decommissioning design of spent fuel reprocessing plant.
This standard is applicable to the decommissioning design of normally closed spent fuel reprocessing plants; the decommissioning design of reprocessing plants closed abnormally and facilities for processing radioactive waste may also refers to this standard.
2 Normative References
The following documents contain provisions which, through reference in this standard, constitute provisions of this standard. For dated reference, subsequent amendments to (excluding any corrigendum), or revisions of, any of these publications do not apply. However, parties to agreements based on this standard are encouraged to investigate the possibility of applying the most recent editions of the standards indicated below. For undated references, the latest edition of the document referred to applies.
GB/T 4960.3 Glossary of Nuclear Science and Technology - Nuclear Fuel and Nuclear Fuel Cycle
GB/T 4960.5 Glossary of Terms: Nuclear Science and Technology - Radiation Protection and Safety of Radiation Sources
GB/T 4960.8 Glossary of Term: Nuclear Science and Technology - Radioactive Waste Management
GB 9133 Classification of Radioactive Waste
GB 11806 Regulations for the Safe Transport of Radioactive Material
GB 14500 Regulations for Radioactive Waste Management
GB 18871-2002 Basic Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources
GB/T 19597 Safety Requirements for Decommissioning of Nuclear Facilities
EJ 1186 Characterization of Radioactive Waste Forms and Packages
EJ/T 1203 Requirements of Radiation Program for Decommissioning Operations of Nuclear Facilities
3 Terminologies and Definitions
Foreword i
1 Scope
2 Normative References
3 Terminologies and Definitions
4 General Safety Requirements of Decommissioning Design
5 Radioactive Characteristic Investigation
6 Clear-up of Radioactive Materials
7 Decontamination
8 Dismantlement of Systems and Equipment
9 Demolition of Buildings (Structures)
10 Environment Management for Plant Area within Decommissioning Range
11 Safety Management of Decommissioning Waste
12 Accident Emergency
13 Quality Assurance
Safety Criteria for Decommissioning Design of Spent Fuel Reprocessing Plant
Chinese Classification
Professional Classification
EJ
ICS Classification
Issued by
Commission of Science, Technology and Industry for National Defense
Issued on
2006-12-15
Implemented on
2007-5-1
Status
valid
Superseded by
Superseded on
Abolished on
Superseding
Language
English
File Format
PDF
Word Count
3000 words
Price(USD)
60.0
Keywords
EJ/T 1201-2006, EJ 1201-2006, EJT 1201-2006, EJ/T1201-2006, EJ/T 1201, EJ/T1201, EJ1201-2006, EJ 1201, EJ1201, EJT1201-2006, EJT 1201, EJT1201
Introduction of EJ/T 1201-2006
1 Scope
This standard specifies the safety criteria for decommissioning design of spent fuel reprocessing plant.
This standard is applicable to the decommissioning design of normally closed spent fuel reprocessing plants; the decommissioning design of reprocessing plants closed abnormally and facilities for processing radioactive waste may also refers to this standard.
2 Normative References
The following documents contain provisions which, through reference in this standard, constitute provisions of this standard. For dated reference, subsequent amendments to (excluding any corrigendum), or revisions of, any of these publications do not apply. However, parties to agreements based on this standard are encouraged to investigate the possibility of applying the most recent editions of the standards indicated below. For undated references, the latest edition of the document referred to applies.
GB/T 4960.3 Glossary of Nuclear Science and Technology - Nuclear Fuel and Nuclear Fuel Cycle
GB/T 4960.5 Glossary of Terms: Nuclear Science and Technology - Radiation Protection and Safety of Radiation Sources
GB/T 4960.8 Glossary of Term: Nuclear Science and Technology - Radioactive Waste Management
GB 9133 Classification of Radioactive Waste
GB 11806 Regulations for the Safe Transport of Radioactive Material
GB 14500 Regulations for Radioactive Waste Management
GB 18871-2002 Basic Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources
GB/T 19597 Safety Requirements for Decommissioning of Nuclear Facilities
EJ 1186 Characterization of Radioactive Waste Forms and Packages
EJ/T 1203 Requirements of Radiation Program for Decommissioning Operations of Nuclear Facilities
3 Terminologies and Definitions
Contents of EJ/T 1201-2006
Foreword i
1 Scope
2 Normative References
3 Terminologies and Definitions
4 General Safety Requirements of Decommissioning Design
5 Radioactive Characteristic Investigation
6 Clear-up of Radioactive Materials
7 Decontamination
8 Dismantlement of Systems and Equipment
9 Demolition of Buildings (Structures)
10 Environment Management for Plant Area within Decommissioning Range
11 Safety Management of Decommissioning Waste
12 Accident Emergency
13 Quality Assurance