NB/T 20600-2021Design and fabrication specification for fuel assembly and associated core components in HPR1000 nuclear power plants (English PDF)

Foreword

This document was issued on 7 January 2021 by the National Energy Administration of the PRC and takes effect on 1 July 2021.

It is a NB/T standard: recommended rather than compulsory, but it is the text a Chinese reviewer applies when assessing a submission.

It is classified under ICS 27.120.10, Chinese classification F 49.

This document was drafted in accordance with the rules given in GB/T 1.1-2020, Directives for standardization - Part 1: Rules for the structure and drafting of standardizing documents.

This document was proposed by the Nuclear Power Standardization Technical Committee of the Energy Industry.

This document is under the jurisdiction of the Nuclear Industry Standardization Research Institute.

The drafting organizations of this document are: Nuclear Power Institute of China; CNNC Jianzhong Nuclear Fuel Element Co., Ltd.; China Nuclear Power Technology Research Institute Co., Ltd.; CGN Uranium Resources Development Co., Ltd.

The main drafters of this document are: Ru Jun, Zhang Lin, Yang Huanming, Lyu Liangliang, Dai Jianxiong, Li Yun, Li Jinkui, Li Hua, Zhang Kun, Liu Zihua, Jiang Yourong, Cao Hui, Pu Zengping, Gao Shixin, Xia Jianwen, Xing Shuo, Zhong Duojun, Lei Tao, Chen Yao, Chen Ping, Pan Jiaye, Li Yuanming, Fu Xiangang, Yang Xiaodong, Cao Rui, Qin Guopeng, Liu Zhenhai, Lan Hong, He Liang, Chen Yu, Chen Jie, Li Jiehua, Liu Shichao, Liu Pengliang, Chen Changyou, Qin Mian, Liao Changshu, Ou Jiangwu, Wang Huisheng, Nie Lihong.

1 Scope

NB/T 20600-2021 is the design and fabrication specification for the fuel assemblies and the associated core components of the HPR1000 - Hualong One - the Chinese pressurised water reactor design now built at home and exported. The fuel assembly is the component that has to hold uranium dioxide pellets in a fixed geometry for several years inside a reactor core, under irradiation, high temperature, coolant flow that induces vibration, and the mechanical loads of handling and of postulated accidents. The specification sets the general requirements the assembly must satisfy - the design basis, the service conditions and the criteria against which each is judged. It then covers the assembly itself and each of its parts: the fuel rods with their cladding, pellets, springs and end plugs, the skeleton formed by guide thimbles and instrumentation tube, the spacer grids that hold the rods and mix the coolant, and the top and bottom nozzles. The associated core components follow - control rod assemblies, burnable absorber and source assemblies, and the plugging devices - each with its own requirements. For every component the specification gives the materials and their condition, the dimensional and tolerance requirements, the design analyses that must be performed, and the fabrication, welding and inspection required, together with the cleanliness, handling and documentation appropriate to nuclear fuel. Note that the standard defines no terms of its own: it states explicitly that none require definition.

This document specifies the design and fabrication requirements for the fuel assemblies and the associated core components of HPR1000 (Hualong One) nuclear power plants.

This document applies to the design and fabrication of the fuel assemblies and the associated core components of HPR1000 nuclear power plants. It may also be used for reference in the design and fabrication of the fuel assemblies and the associated core components of other pressurized water reactor nuclear power plants.

A description of the fuel assemblies and the associated core components of HPR1000 nuclear power plants is given in Annex A.

2 Normative references

The contents of the following documents constitute indispensable provisions of this document through the normative references made to them in the text. For dated references, only the edition corresponding to that date applies to this document; for undated references, the latest edition (including all amendments) applies to this document.

GB/T 223 (all parts), Methods for chemical analysis of iron, steel and alloy.

GB/T 228.1, Metallic materials - Tensile testing - Part 1: Method of test at room temperature.

GB/T 228.2, Metallic materials - Tensile testing - Part 2: Method of test at elevated temperature.

GB/T 229, Metallic materials - Charpy pendulum impact test method.

GB/T 230.1, Metallic materials - Rockwell hardness test - Part 1: Test method.

GB/T 231.1, Metallic materials - Brinell hardness test - Part 1: Test method.

GB/T 232, Metallic materials - Bend test method.

GB/T 238, Metallic materials - Wire - Reverse bend test method.

GB/T 239.1, Metallic materials - Wire - Part 1: Single twist test method.

GB/T 239.2, Metallic materials - Wire - Part 2: Double twist test method.

GB/T 2976, Metallic materials - Wire - Wrapping test method.

GB/T 4162-2008, Ultrasonic testing method for wrought and rolled steel bars.

GB/T 4334, Corrosion of metals and alloys - Test methods for intergranular corrosion of stainless steels.

GB/T 4340.1, Metallic materials - Vickers hardness test - Part 1: Test method.

GB/T 4740, Test method for compressive strength of ceramic materials.

GB/T 5163, Sintered metal materials (excluding hardmetals) - Permeable sintered metal materials - Determination of density, oil content and open porosity.

GB/T 6394, Determination of estimating the average grain size of metal.

GB/T 6402, Ultrasonic testing method for steel forgings.

GB/T 6579, Laboratory glassware - Thermal shock and thermal shock endurance test method.

GB/T 8651, Ultrasonic lamb wave inspection method for metal sheets and plates.

GB/T 10266, Technical specification for sintered uranium dioxide pellets.

GB/T 10561, Steel - Determination of content of non-metallic inclusions - Micrographic method using standard diagrams.

GB/T 11170, Stainless steel - Determination of multi-element contents - Spark discharge atomic emission spectrometric method (routine method).

GB/T 11809, Metallographic examination and X-ray radiographic examination of the seam welds of pressurized water reactor fuel rods.

GB/T 11813, Helium mass spectrometer leak detection of pressurized water reactor fuel rods.

GB/T 11839-2008, Determination of boron in uranium dioxide pellets - Curcumin extraction photometric method.

GB 11841, Determination of uranium in uranium dioxide powder and pellets - Ferrous sulphate reduction - Potassium dichromate oxidimetric method.

GB/T 13370-1992, Determination of lithium, sodium, potassium and caesium in uranium dioxide powder and pellets - Atomic absorption spectrophotometric method / flame emission spectrometric method.

GB/T 13372-1992, Determination of impurity elements in uranium dioxide powder and pellets - ICP-AES method.

GB/T 13698, Determination of total hydrogen in uranium dioxide pellets.

GB/T 19348.1, Non-destructive testing - Industrial radiographic film - Part 1: Classification of film systems for industrial radiography.

GB/T 19802, Non-destructive testing - Industrial radiographic illuminators - Minimum requirements.

GB/T 20123, Steel and iron - Determination of total carbon and sulfur content - Infrared absorption method after combustion in an induction furnace (routine method).

GB/T 20124, Steel and iron - Determination of nitrogen content - Thermal conductimetric method after fusion in a current of inert gas (routine method).

GB/T 25942, Nuclear grade silver-indium-cadmium alloy rod.

GB/T 26314, Designation and chemical composition of zirconium and zirconium alloys.

GB/T 28195, Test method for softening point of glass.

GB/T 28209, Methods for chemical analysis of borosilicate glass.

GB/T 2828.1, Sampling procedures for inspection by attributes - Part 1: Sampling schemes indexed by acceptance quality limit (AQL) for lot-by-lot inspection.

EJ/T 499, Design and fabrication technical conditions for primary neutron source rods of pressurized water reactor nuclear power plants.

EJ/T 542, Specification for sintered gadolinia-urania (gadolinium sesquioxide - uranium dioxide) pellets.

EJ/T 686, Method for the determination of uranium-235 enrichment of reactor fuel rods - Gamma-ray energy spectrometry.

EJ/T 687, Test method for the load-bearing capacity of sintered uranium dioxide pellets.

EJ/T 688, Inspection method for the microstructure of sintered uranium dioxide pellets.

EJ/T 689, Test method for the thermal stability of sintered uranium dioxide pellets.

EJ/T 787, Inspection methods for the outline dimensions, geometric density and appearance quality of sintered uranium dioxide pellets.

EJ/T 868, Quality assurance in the manufacture of nuclear fuel assemblies.

EJ/T 957-2007, Cleanliness and cleaning of pressurized water reactor fuel assemblies.

EJ/T 973-2016, Determination of the uranium isotopic abundance in uranium dioxide powder and pellets - Thermal ionization mass spectrometry.

EJ/T 1028, Autoclave corrosion test for zirconium and zirconium alloys.

EJ/T 1092, Method for the determination of the internal pellet gap and plenum length of pressurized water reactor fuel rods - Gamma-ray transmission method.

EJ/T 1212 (all parts), Methods for the analysis of sintered gadolinium oxide - uranium dioxide pellets.

NB/T 20003.2-2010, Non-destructive testing of mechanical equipment in the nuclear island of nuclear power plants - Part 2: Ultrasonic testing.

NB/T 20035, Classification of operating conditions of pressurized water reactor nuclear power plants.

NB/T 20057.4, Design of the reactor system of pressurized water reactor nuclear power plants - Core - Part 4: Fuel-associated core components.

NB/T 20099-2012, Requirements for the analysis of loss-of-coolant accidents in pressurized water reactor nuclear power plants.

NB/T 20101-2012, Requirements for the analysis of rod ejection accidents in pressurized water reactor nuclear power plants.

NB/T 20141, Rules for the packaging, transport, handling and storage of fresh fuel assemblies of pressurized water reactor nuclear power plants.

NB/T 20436, Water chemistry control of pressurized water reactor nuclear power plants.

NB/T 20538, Zirconium alloy tubes for fuel cladding of pressurized water reactor nuclear power plants.

NB/T 20565, Zirconium alloy bars and wires for fuel assemblies of pressurized water reactor nuclear power plants.

NB/T 20578, Zirconium alloy strip for fuel assemblies of pressurized water reactor nuclear power plants.

YS/T 423 (all parts), Methods for chemical analysis of nuclear grade boron carbide powder.

YS/T 425, Antimony-beryllium pellets.

3 Terms and definitions

No terms and definitions are needed to be defined in this document.