GB/T 4960.2-2023Glossary for nuclear science and technology—Part 2: Fission reactor (English PDF)

Foreword

This document complies with the provisions of GB/T 1.1-2020 "Standardization Work Guidelines Part 1: Structure and Drafting Rules of Standardization Documents" Drafting.

This document is Part 2 of GB/T 4960 "Nuclear Science and Technology Terminology". GB/T 4960 has released the following parts.

---Part 1. Nuclear physics and nuclear chemistry (GB/T 4960.1-2010);

---Part 3. Nuclear fuel and nuclear fuel cycle (GB/T 4960.3-2010);

---Radionuclides (GB/T 4960.4-1996);

---Radiation protection and radiation source safety (GB/T 4960.5-1996);

---Part 6. Nuclear instrumentation (GB/T 4960.6-2008);

---Part 7. Nuclear material control and nuclear safeguards (GB/T 4960.7-2010);

---Part 8. Radioactive waste management (GB/T 4960.8-2008);

---Part 9. Magnetic confinement nuclear fusion (GB/T 4960.9-2013).

This document replaces GB/T 4960.2-1996 "Nuclear Science and Technology Terminology Fission Reactor". Compared with GB/T 4960.2-1996, except In addition to structural adjustments and editorial changes, the main technical changes are as follows:

---Added ultra-high temperature gas-cooled reactors (see 3.26), small modular [reactor] reactors (see 3.27), graphite [moderated] reactors (see 3.28), super-critical Boundary water [cold] reactor (see 3.29), sodium-cooled fast reactor (see 3.30), molten salt reactor (see 3.31), fuel rod (see 4.10), control rod assembly (see 4.16), [core] coaming plate (see 4.30), core flow distribution device (see 4.32), large grid header (see 4.58), small grid header (see 4.59), isothermal temperature coefficient (see 5.22), neutron angular density (see 5.48), neutron angular fluence rate (see 5.50), characteristic line method (see 5.51), discrete ordinate method (see 5.52), spherical harmonic function method (see 5.53), collision probability method (see 5.54), penetration probability method (see 5.55), node method (see 5.56), coarse mesh finite difference method (see 5.57), flux diagram (see 5.58), refueling plan (see 5.59), chemistry Compensation control (see 5.104), balanced xenon (see 5.107), maximum xenon (see 5.108), balanced samarium (see 5.109), maximum samarium (see 5.110), axial power deviation (see 5.111), axial power deviation (see 5.112), boron differential value (see 5.113), fission products (see 5.115), [fission product] yield (see 5.116), actinides (see 5.117), minor actinides (see 5.118), transuranic elements (see 5.119), prompt neutron lifetime (see 5.121), benchmark experiment (see 5.124), number of atomic dislocations (see 5.125), nuclear enthalpy rise Passage factor (see 6.29), protection system (see 7.1.16), core melt retention system (see 7.1.56), core trap (see 7.1.57), emergency boron injection system (see 7.1.58), reactor cavity water injection cooling system (see 7.1.59), passive containment heat extraction system (see 7.1.60), reactor boron and water supply system (see 7.1.61), steam generator blowdown system (see 7.1.62), reactor Pressure vessel high-level exhaust system (see 7.1.63), secondary side passive waste heat removal system (see 7.1.64), containment filter exhaust System (see 7.1.65), inclined elevator (see 7.2.6), sodium purification (see 7.2.7), pressure pipe (see 7.3.1), discharge pipe (see 7.3.2), cobalt Absorption rods (see 7.3.3), moderator systems (see 7.3.4), deuteration (see 7.3.5), deuterium removal (see 7.3.6), reactor headers (see 7.3.6)

7.3.7), heat transfer branch pipe (see 7.3.8), liquid injection shutdown system (see 7.3.9), liquid area control system (see 7.3.10), Annular gas system (see 7.3.11), heavy water vapor recovery system (see 7.3.12), damaged fuel positioning system (see 7.3.13), ventilation Type low pressure containment (see 7.4.1), fuel loading and unloading system (see 7.4.2), new fuel supply system (see 7.4.3), spent fuel storage storage system (see 7.4.4), helium purification system (see 7.4.5), helium auxiliary system (see 7.4.6), primary loop pressure relief system (see 7.4.7), steam generator accident exhaust system (see 7.4.8), hot gas duct (see 7.4.9), reactor compartment (see 7.4.10), reaction chamber Reactor cabin cooling system (see 7.4.11), main helium [circulation] fan (see 7.4.12), negative pressure ventilation system (see 7.4.13), load follow-up trace (see 8.38), water intrusion accident (high-temperature gas-cooled reactor) (see 9.28), air inlet accident (high-temperature gas-cooled reactor) (see 9.29), decompression accident (high-temperature gas-cooled reactor)

Temperature gas-cooled reactor) (see 9.30), loss of forced cooling accident (high-temperature gas-cooled reactor) (see 9.31), sodium fire (see 9.32), sodium-water reaction (see 9.33), items important to safety (see 9.38) and other terms and definitions;

---Deleted the multi-group model (see 3.80 of the 1996 edition), group separation section (see 3.82 of the 1996 edition), and linear extrapolation distance (see 3.85 of the 1996 edition), extrapolation boundary (see 3.86 of the 1996 edition), burnout heat flux density (see 3.165 of the 1996 edition), three Zone circulation (see 5.22 of the 1996 edition), expected operational events (see 6.10 of the 1996 edition), design basis accidents (see 1996 edition of 6.14 of the 1996 edition), injection stage (pressurized water reactor) (see 6.20 of the 1996 edition), injection stage (pressurized water reactor) (see 1996 edition of 6.21), refilling stage (pressurized water reactor) (see 6.22 of the 1996 edition), spray stage (pressurized water reactor) (see 6.23 of the 1996 edition), Re-flooding stage (pressurized water reactor) (see 6.24 of the 1996 edition), recirculation stage (pressurized water reactor) (see 6.25 of the 1996 edition), various safety (see 6.40 of the 1996 edition), safety functions (see 6.41 of the 1996 edition), safety combination (see 6.42 of the 1996 edition), technology Technical specifications (see 6.45 of the 1996 edition), non-conformities (see 6.46 of the 1996 edition), and audits (see 6.47 of the 1996 edition) terms and definitions.

This document is proposed and coordinated by the National Nuclear Energy Standardization Technical Committee (SAC/TC58).

Introduction

Terminology is the basis for standardization in a field. In order to standardize and unify a large number of terminology in the field of nuclear science and technology and improve communication To ensure accuracy and efficiency, our country has formulated and released GB/T 4960 "Nuclear Science and Technology Terminology", which is planned to consist of 9 parts.

---Part 1. Nuclear physics and nuclear chemistry. The purpose is to define terms and definitions in nuclear physics and nuclear chemistry.

---Part 2. Fission Reactor. The purpose is to define the terminology and safety aspects of nuclear fission reactor design, commissioning and operation. definition.

---Part 3. Nuclear fuel and nuclear fuel cycle. The purpose is to define uranium mining, uranium conversion, fuel element design and manufacturing, etc. Terms and Definitions.

---Radionuclides. The purpose is to define the terms and definitions of radionuclides and their applications in agriculture, industry, medicine, etc.

---Radiation protection and radiation source safety. The purpose is to define terms and definitions in radiation protection, radiation source safety, etc.

---Part 6. Nuclear instrumentation. The purpose is to define terms and definitions for various types of instrumentation used in the nuclear industry.

---Part 7. Nuclear material control and nuclear safeguards. The purpose is to define terms and definitions in areas such as nuclear material control.

---Part 8. Radioactive waste management. The purpose is to define the terminology and definition.

---Part 9. Magnetic confinement nuclear fusion. The purpose is to define terms and definitions in the field of magnetic confinement fusion.

This document has played an important role in the design, commissioning and operation of fission reactors and nuclear safety. However, with the development of my country's nuclear energy field in recent years, Technological progress continues to occur, and more and more new reactor types have been applied and good practical experience has been achieved. In order to solidify these good practices, This document has been specially revised to include a large number of terms for non-light water reactor types such as fast reactors, heavy water reactors, and high temperature gas-cooled reactors. In addition, in order to further consolidate the subject Basics, and also adds a small number of more basic terms. The revision of this document aims to promote all-round further development in the field of fission reactors. Terminology of Nuclear Science and Technology Part 2. Fission Reactor

1 Scope

This document defines the fission reactor type, reactor body, reactor physics, reactor thermal engineering, reactor process systems and components, adjustment Terms and definitions in the fields of testing and operation, nuclear safety, etc.

This document is applicable to the preparation and translation of standards and technical documents in the field of fission reactors, as well as the specification of terminology for domestic and international technical exchanges. Expression.

2 Normative reference documents

This document has no normative references.

3 Reactor Type