NB/T 20099-2012Analysis requirements for loss-of-coolant accident of pressurized water reactor nuclear power plants (English PDF)
压水堆核电厂反应堆冷却剂丧失事故分析要求
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Issued by
NEA
Level / Type
Industry · Recommended
Issue date
January 6, 2012
Implementation date
April 6, 2012
Scope
NB/T 20099-2012 is the English-translated version of 压水堆核电厂反应堆冷却剂丧失事故分析要求.
NB/T 20099-2012 is the Chinese standard "Analysis requirements for loss-of-coolant accident of pressurized water reactor nuclear power plants".
Its scope clause reads: This standard specifies the criteria, analysis methods and evaluation contents to be followed in the analysis of loss-of-coolant accident for the performance evaluation of emergency reactor core cooling system of pressurized water reactor nuclear power plants.
It is applicable to the analysis of loss-of-coolant accident of pressurized water reactor nuclear power plants to evaluate the performance of emergency reactor core cooling system. Its clauses include terms and definitions; restriction criteria.
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Document preview — NB/T 20099-2012
National Standard of the People's Republic of China
- ICS
- 27.120.20
Issued by: National Energy Administration of the People's Republic of China
Contents
- Foreword i
- 1 Scope
- 2 Normative references
- 3 Terms and definitions
- 4 Restriction criteria
- 5 Analysis methods
1 Scope
This standard specifies the criteria, analysis methods and evaluation contents to be followed in the analysis of loss-of-coolant accident for the performance evaluation of emergency reactor core cooling system of pressurized water reactor nuclear power plants.
It is applicable to the analysis of loss-of-coolant accident of pressurized water reactor nuclear power plants to evaluate the performance of emergency reactor core cooling system.
2 Normative references
The following referenced documents are indispensable for the application of this document. For dated references, only the edition cited applies. For undated references, the latest edition (including any amendments) applies.
NB/T 20103 Accident analysis and safety criteria for pressurized water reactor nuclear power pant
3 Terms and definitions
For the purposes of this document, the following terms and definitions apply.
3.1 loss-of-coolant accident (LOCA)
assumed accident of pipe failure at the pressure boundary of the reactor coolant system, ranging from the break that causes the loss-of-coolant rate exceeding the compensation capacity of the chemical and volume control system to the break that causes double-ended shear fracture of the largest pipe of the reactor coolant system
3.2 LOCA conservative evaluation code
a procedure for simulating the LOCA phenomenon and process by using a conservative model
3.3 LOCA best-estimate code
a procedure for simulating the LOCA phenomenon and process by using a realistic model
4 Restriction criteria
For the uranium dioxide fuel pellet, its cladding is made of zirconium alloy. If the assumed LOCA occurs in the pressurized water reactor nuclear power plant using cylindrical fuel rods, the acceptance criteria are as follows according to NB/T 20103:
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This preview omits tables, figures, formulas and parts of the technical clauses. The complete document — 15 pages — is available in the English PDF.
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NB/T 20103-2012 — Accident Analysis and Safety Criteria for Pressurized Water Reactor Nuclear Power Plant
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