GB15146.2-2008
Nuclear criticality safety for fissile materials outside reactors - Part 2: Basic technical practices and subcritical limits for handling, processing and operations with fissile materials
反应堆外易裂变材料的核临界安全 第2部分：易裂变材料操作、加工、处理的基本技术规则与次临界限值
GB 15146.2-2008 is a current mandatory Chinese national standard for Nuclear criticality safety for fissile materials outside reactors - Part 2: Basic technical practices and subcritical limits for handling, processing and operations with fissile materials. It appears in the Construction compliance cluster with a product safety focus and has an implementation date of Aug 1, 2009.
Applicability depends on product scope, certification route, competent authority notices and transition rules. Requst for the translation or verify source before using this record in a compliance decision.
Compliance overview
Scope and applicability
This standard applies to the handling, processing, and operations of fissile materials outside reactors. It establishes basic technical rules and subcritical limits for simple geometric shapes, specifically targeting nuclear fuel cycle facilities and related engineering operations. This standard is not applicable to the assembly of fissile materials under controlled conditions, such as critical experiments.
Technical requirements
This standard is mandatory and specifies fundamental technical rules for maintaining nuclear criticality safety. It requires controlling one or more system parameters (such as mass, geometry, concentration, or moderation) within subcritical limits while maintaining adequate safety margins for process uncertainties. Engineers must apply the double contingency principle, ensuring that at least two independent, unlikely changes in process conditions must occur simultaneously to cause a criticality accident. The standard also details single-parameter limits for homogeneous aqueous solutions, metal units, and oxides of 233U, 235U, and 239Pu, as well as multi-parameter controls for low-enriched uranium and plutonium mixtures.
Testing methods
The standard emphasizes the validation of calculation methods used to evaluate criticality safety. It requires determining the bias and uncertainty of computational methods by comparing them against experimental critical data. Validation solely by comparing results from different calculation methods is explicitly not acceptable. The evaluation also requires verifying computer programs and ensuring that nuclear characteristic parameters, such as cross-section data, are consistent with experimental measurements.
FAQs
What operations and materials are regulated under GB 15146.2-2008?
The standard applies to the handling, processing, and operations of fissile materials outside reactors. It is explicitly not applicable to the assembly of fissile materials under controlled conditions, such as critical experiments.
Are there any significant updates from the previous GB 15146.2-1994 version?
The 2008 version added 233U subcritical limits, changed the terminology from 'validation of calculation methods' to 'confirmation of calculation methods' (adding general requirements), and modified auxiliary verbs from 'must' to 'should' or 'may' to align with updated administrative practices.
How does GB 15146.2-2008 handle the validation of calculation methods when experimental data is unavailable?
The standard requires that calculation methods be validated against experimental critical data to determine bias and its uncertainty. Validation solely by comparing results from different calculation methods is explicitly not acceptable.
The summary above provides a high-level overview of GB 15146.2-2008. To ensure complete compliance for your nuclear facilities and operations entering the Chinese market, a precise and professional translation of the full technical specifications is essential. Purchase our high-quality English translation of GB 15146.2-2008 today to access all detailed parameter tables, calculation validation procedures, and subcritical limit data.
Applicability hints
- Type
- Safety
- CCS
- F09
- ICS
- 27.120.30
- Competent department
- State Administration of Science, Technology and Industry for National Defense
- Technical committee
- State Administration of Science, Technology and Industry for National Defense
Relationships
Replaces:GB 15146.2-1994