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GB 15146.3-2008: Nuclear criticality safety for fissile materials outside reactors -- Part 3: Requirements for nuclear criticality safety in the storage of fissile materials
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Nuclear criticality safety for fissile materials outside reactors -- Part 3: Requirements for nuclear criticality safety in the storage of fissile materials
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Nuclear criticality safety for fissile materials outside reactor-Requirements for nuclear criticality safety in the storage of fissile material
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Basic data | Standard ID | GB 15146.3-2008 (GB15146.3-2008) | | Description (Translated English) | Nuclear criticality safety for fissile materials outside reactors -- Part 3: Requirements for nuclear criticality safety in the storage of fissile materials | | Sector / Industry | National Standard | | Classification of Chinese Standard | F09 | | Classification of International Standard | 27.120.30 | | Word Count Estimation | 17,195 | | Date of Issue | 2008-09-19 | | Date of Implementation | 2009-08-01 | | Older Standard (superseded by this standard) | GB 15146.3-1994 | | Quoted Standard | GB 15146.1; GB 15146.2; GB 15146.9 | | Regulation (derived from) | Announcement of Newly Approved National Standards No. 16 of 2008 (No. 129 overall) | | Issuing agency(ies) | General Administration of Quality Supervision, Inspection and Quarantine of the People's Republic of China, Standardization Administration of the People's Republic of China | | Summary | This Chinese standard provides storage of fissile material for nuclear criticality safety in the basic requirements and limits. This standard applies to the storage of fissile material. | GB 15146.3-2008: Nuclear criticality safety for fissile materials outside reactors -- Part 3: Requirements for nuclear criticality safety in the storage of fissile materials
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Nuclear criticality safety for fissile materials outside reactors.Part 3. Requirements for nuclear criticality safety in the storage of fissile materials
ICS 27.120.30
F09
National Standards of People's Republic of China
Replacing GB 15146.3-1994
Nuclear criticality safety for fissile materials outside reactors
Part 3. fissile material storage
Nuclear criticality safety requirements
Posted 2008-09-19
2009-08-01 implementation
Administration of Quality Supervision, Inspection and Quarantine of People's Republic of China
Standardization Administration of China released
Foreword
All technical content in this section is mandatory.
GB 15146 "Nuclear criticality safety for fissile materials outside reactor" has so far released the following 11 sections.
--- GB 15146.1 easily outside reactors Nuclear criticality safety - Part 1 of fissile material. Nuclear Criticality Safety Administration regulations (on behalf of the
For GB 15146.1-1994)
--- GB 15146.2 outside reactors Nuclear criticality safety - Part 2 of fissile material. fissile material, processing and operations processing
The basic technical rules and subcritical limits (instead of GB 15146.2-1994)
--- GB 15146.3 outside reactors Nuclear criticality safety for fissile materials - Part 3. The nuclear criticality safety for fissile material storage
Requirements (instead of GB 15146.3-1994)
--- GB 15146.4 fissile materials outside reactor - Nuclear criticality safety-containing aqueous solutions of fissile material for steel pipe intersections
Nuclear criticality safety criteria
--- GB 15146.5 plutonium outside reactor nuclear criticality safety for fissile materials - Nuclear criticality control criteria and a mixture of natural uranium
Subcritical limits
--- GB/T 15146.6 fissile materials outside reactor - Nuclear criticality safety borosilicate glass Raschig rings and its application criteria
--- GB 15146.7 easily outside reactors Nuclear criticality safety subcritical neutron multiplication of fissile material for measurements in situ
--- GB 15146.8 fissile materials outside reactor - Nuclear criticality safety - Part 8. heap outside the handling, storage and transportation of LWR fuel
Nuclear criticality safety criteria for feed unit (instead of GB 15146.8-1994)
--- GB Performance and seized 15146.9 fissile materials outside reactor - Nuclear criticality safety for nuclear criticality detection and alarm systems
Inspection requirements
--- GB 15146.10 Safety requirements outside reactor nuclear criticality safety for fissile material fixed neutron absorber
--- GB/T 15146.11 outside reactor Nuclear criticality safety for fissile materials based on nuclear criticality safety limits and controls moderator
This section GB of Section 315 146. This Part replaces GB/T 15146.3-1994 "fissile materials outside the reactor core Pro
Border security storage of fissile material for nuclear criticality safety requirements. "
Compared with GB 15146.3-1994 part of the main changes are as follows.
--- Increasing the foreword;
--- The critical limit with some modifications or deletions;
--- For the auxiliary "shall" be changed to "shall", "should" or "may."
Appendix A of this section is an informative annex.
This part of the National Standardization Technical Committee proposed nuclear energy.
This part of the National Standardization Technical Committee centralized nuclear energy.
This section drafted by. China Institute of Atomic Energy, China National Nuclear Corporation.
The main drafters of this section. Liu Zhenhua, Li Yucheng, Shen Lei students.
This section was first released in 1994.
Nuclear criticality safety for fissile materials outside reactors
Part 3. fissile material storage
Nuclear criticality safety requirements
1 Scope
This section provides basic storage of fissile material for nuclear criticality safety requirements and limits.
This section applies to storage of fissile material.
2 Normative references
The following documents contain provisions which, through reference in this text, constitute provisions of this part. For dated references, subsequent
Amendments (not including errata content) or revisions do not apply to this section, however, encourage the parties to this part of the research agreement
Whether the latest versions of these documents. For undated reference documents, the latest versions apply to this section.
GB 15146.1 fissile materials outside reactor - Nuclear criticality safety - Part 1. Nuclear Criticality Safety Administration regulations
GB 15146.2 outside reactors Nuclear criticality safety for fissile materials - Part 2. The operation of fissile material, processing, handling basic
Technical Regulations and subcritical limits
Performance and testing GB 15146.9 fissile materials outside reactor - Nuclear criticality safety for nuclear criticality detection and alarm systems
Claim
3 Terms and Definitions
The following terms and definitions apply to this part of GB 15146.
3.1
Be treated as a whole collection of fissile material, the material may be, a collection of material of any shape can also be separated by a number of
The small components.
3.2
The storage unit is placed therein, and the volume of space having a defined boundary.
3.3
Rules set by the storage unit has a number of storage element composed of a gate arrangement.
3.4
Calculation methods recognized in accordance with the provisions of GB 15146.2.
4 Management requirements and technical rules
4.1 Management Requirements
4.1.1 Storage in the operation of all fissile material shall comply with the relevant requirements of GB 15146.1 and GB 15146.2 of.
4.1.2 should be approved storage control methods and operating rules written to written procedures; involved in the transfer and storage of fissile material for staff
You should be familiar with these procedures; storage limit should be a variety of fissile material posted.
4.1.3 Nuclear criticality safety management personnel should carry out the necessary checks to confirm the procedures established by implementation.
4.1.4 personnel access storage areas should be strictly controlled.
4.2 Technical Regulations
4.2.1 In addition to easy storage of fissile material shall meet the requirements of GB 15146.2 outside should also comply with section 4.2.2 - 4.2.12 of
Claim.
4.2.2 should be determined to calculate the experimental data, results or methods of calculating been confirmed as the basis when the fissile material storage limit.
4.2.3 storage facility and warehouse located Shidu Yi be designed, constructed and maintained in accordance with good engineering practice.
4.2.4 Design of warehouse facilities should be excluded unreasonable storage layout and structure to minimize dependence on administration.
Storage 4.2.5 fissile material, it should be under such fire, flooding, earthquakes and other natural disasters conditions, are able to avoid temporary
Border incidents.
4.2.6 fissile material storage unit should be packaged within a container, the container should be of watertight. Certainly not only container
Were flooded, or even water into the container will not be reached critical, confined conditions can be relaxed.
4.2.7 can be used birdcage fixtures, metal cans and lids physical barrier structure on the shelf used to keep the storage unit
The space between the spacing. Shelves must be strong and non-combustible.
4.2.8 In the storage site should strive to do without the presence of flammable materials. If the storage site will inevitably have a relatively large amount of flammable materials exist,
For example, flammable metal cutting debris, it should be equipped with fire-fighting system.
4.2.9 equipped with a sprinkler system fissile material storage site should be used to make containers for fissile materials in the design to prevent hydrocephalus
Measures.
4.2.10 equipped with a sprinkler system fissile material storage site, should the possibility of water under conditions of nuclear criticality accident made
Evaluation.
4.2.11 to be resettled in nuclear criticality accident alarm system storage site, set the alarm system shall comply with the provisions of GB 15146.9,
Particular attention should determine the appropriate detector alarm system installed.
4.2.12 should be an important part of a good warehouse management as nuclear criticality safety practical work.
5 storage limits and conditions of use
5.1 one of the following conditions, in principle, the need to restrict the conditions for storage of fissile material.
a) the mass fraction of 235U enrichment of uranium is not more than 1.0% water solution or a homogeneous mixture;
b) enrichment of 235U mass fraction of not more than 5.0%, and the ratio of the number of hydrogen atoms nuclides the number of atoms of fissile material is less than or equal to
0.5 bulk solid compounds of uranium metal or uranium. These materials do not have bulk requirements concave, not by means of small bars, small group
to make. When no hydrogen-containing medium in the container, and the container watertight, you can cancel this restriction;
c) 235U concentration of not more than 11.7g/L, or Pu concentration is not more than a uniform aqueous solution of 7.2g/L, and can not guarantee during storage
Accident concentration and precipitation of material occurs;
d) vessel was charged with metal-like 233U, 235U, 238U, 239Pu or 241Pu radionuclides single unit, or by a combination of any of these nuclides
Units, and units containing fissile material is not more than 0.015kg, containers larger than the minimum size of 10cm;
e) (U + Pu) Plutonium content of not more than 0.13% of an aqueous solution or a homogeneous mixture of plutonium and natural uranium or depleted uranium.
5.2 pairs of several common fissile material storage unit cell limits in Table 1 values may be used. The limits in Table 1 class Ⅰ unit
It refers to the unit by the wrapper when no hydrogen material (such as steel, aluminum, etc.) manufacturing, and the wall thickness does not exceed the limit when 1.27cm; Ⅱ class unit
Limit means limits wrapper hydrogen-containing material or wall thickness of steel, aluminum and other materials than 1.27cm when made.
5.3 Table 1 lists the limits applicable to uranium (or plutonium) isotopes of various compositions. But other than 238U isotope of uranium should be considered
235U; various plutonium isotopes 240Pu outside shall be regarded as 239Pu.
5.4 Table 1 class Ⅰ unit, its shape is generally limited (but the geometry of the sheet or the like to do special consideration). For metals, the compounds
Or a mixture of units in addition to a thin plastic wrap material (per kilogram of fissile materials should not exceed 10g polyethylene) and the sealing gasket, in general,
Not have other hydrogen-containing substance, if so, to deal with critical safety reviews. Table 1 Ⅱ-based unit, which allows the external unit there except
Any number of hydrogen-containing substance D2O, except beryllium and graphite.
1 limits listed in Table 5.5 should not be used in isolation unit is suitable for a variety of amplification factor relaxed.
5.6 package container units easily fissile material should be at the center of the gate element, gate element deviation in the center of the grid cell size not greater than 10%.
5.7 Table 1 lists the units are arranged in a linear or planar array isolated, when more than 40cm away from the center of the cell and the surface of the unit from the container
From greater than 30cm, the number of units ordered may not be limited.
Table 1 unit limit for storage of fissile material used
Unit type was type material
Limit
Limit type units 235U and 239Pu unit limit unit limits
Ⅰ class unit
Metal, or a mixture of compounds (H/Xa≤0.5) mass limit, kg 18.5 4.5b
Metal, or a mixture of compounds (0.5 < H/X≤2.0) mass limit, kg 16.0 4.5
Or a mixture of hydrogen-containing compound (2 < H/X≤20) mass limit, kg 3.6 2.4
A solution or a mixture of hydrogen (H/X > 20) the volume limit, L 3.6 2.4
Ⅱ class unit
Metal, or a mixture of compounds (H/X≤2) mass limit, kg 9.5 3.4c
Or a mixture of hydrogen-containing compound (2 < H/X≤20) mass limit, kg 2.0 1.3
A solution or a mixture of hydrogen (20≤H/X < 800) volume limit, L 2.0 1.3
A solution or a mixture of hydrogen (H/X≥800) volume limit, L 4.0 3.0
aH/X represents the material itself, H/235U or H/239Pu atomic ratio.
b This is the density of plutonium metal 19.6g/cm3 limits, the density limits of plutonium alloy 15.8g/cm3 was 6.0kg.
c This is the density of plutonium metal 19.6g/cm3 limits, the density limits of plutonium alloy 15.8g/cm3 was 4.5kg.
5.8 Table 1 lists class Ⅰ unit arranged in a cubic array storage, the maximum number of units allowed in relation to the volume of the gate element shown in Figure 1. Figure 1
The lower curve is for the case against the thickness of the reflector (concrete, steel, wood, clay built into the thick-walled depot) in addition to the array. Curve fit
Only slightly for the outer reflector array of circumstances.
NOTE. Slight reflection reflector means smaller reflector. Only arrays on both sides (floor and a wall) or side (the array on the big room) close to the thick
When the reflector, the reflector can be regarded as only slightly reflective.
The Class Ⅱ listed in Table 1 are arranged in a cubic array storage unit, the outside unit's internal cubic array best water moderator, cubic external array
Reflections of water, the maximum number of units allowed in relation to the volume of the gate element shown in Figure 2.
5.9 If the number of units of fissile material is less than the limits listed in Table 1, by maintaining the largest array unit determines the total amount of fissile material and the gate
Cell size under the same conditions, the total number of array elements can be increased.
5.10 yuan at the gate from the center and the number of units has allowed the conditions established by the unit may limit a mixed array of different units, but this
When all types of units must be centrally located, respectively.
5.11 can remove some cells from the array or array to increase the total volume of approach channel is formed within the array, in the channel to allow workers
Staff or through travel and transport allow, but not in which to place the storage unit.
5.12 storage array to meet one of the following conditions may be considered isolated from each other.
a) If the surfaces of two planar array or cube array to the surface is greater than the distance between two of the following values, whichever is greater. the maximum size of each array
Inch; 4m above.
b) there is concrete or 50cm above the water layer between the two arrays.
5.13 limits in Table 1 are listed for several common fissile material storage units making. For some cases, the provision of a single storage
Yuan limits may be too restrictive or not suited to this point, according to experimental data and (or) calculated result of the calculation method is confirmed in detail
Safety analysis, provide new limits. Examples of these storage units.
a) There are a number of more than slow and reflective capacity of water and concrete materials (such as heavy water, graphite, beryllium, etc.) incorporation of fissile material
unit;
b) appear stronger than concrete or water reflection material around at the array;
c) loading unit exceeds tabulated limit value;
d) Fissile material means temporarily stored in the operating area or operating a small chamber when the container is not closed;
e) other is not specified circumstances.
5.14 reference section in Appendix A for determining high-enriched fissile material storage limit.
Note 1. The lower curve applies to the situation close to the outer array has a thick reflector;
Note 2. The curve applies to the outer array has a slight case of the reflector;
Note 3. The minimum surface spacing between the units 20cm;
Note 4. The number of smaller units with a maximum unit can be seen as a maximum equivalent unit.
Figure 1 cubic array allows the maximum number of cells Figure
Figure 2 cubic array of internal best water moderator, water reflection external circumstances cube array
The maximum allowable number of cells Figure
Appendix A
(Informative)
Storage limits and conditions of use of highly enriched fissile material
A. Appendix 1 shows the mass fraction of uranium enrichment 235U not less than 30%, 233U and plutonium metals and oxides reservoir
Deposit limits, given its quality limits and spatial separation limits.
These fissile material different in different mass fractions single enrichment, different H/U (Pu) ratio, different grid sizes and storage arrays
Limit the number of quality Yuan (expressed in kg), as shown in Table A. 1 ~ A. 11 listed.
A. Limits given in Annex 2 for the main arrays ideal given. In practice, there are certain differences between the ideal and the actual array of arrays.
However, the limits given in this annex may provide a starting point for establishing the actual safe storage array.
A. Quality limits given in Appendix 3 unit is obtained under the following conditions.
a) calculated by the calculation method after confirmation.
b) according to the array neutron multiplication factor of less than 0.95 calculated conditions.
c) to around 20cm thick with water reflection layer critical computing data cube array as the basis.
d) calculations are for units placed in the center square of the grid, for the case of a sphere of fissile material carried.
A. 4 This appendix gives 235U highly enriched uranium limits, and 233U mass fraction should be less than 1%, it should be outside 238U
The uranium isotopes are considered 235U; when using 233U limits, should be the other isotope of uranium 233U is also considered; if the 240Pu
Concentration greater than the concentration of 241Pu and calculate H/Pu atomic ratio and when the quality or concentration as 239Pu to 241Pu, 239Pu limits are available
Apply a mixture of various plutonium isotopes.
A. 5 For oxide fissile material, its storage limit is based on the calculated dioxide derived. These limits also apply to their
He oxides, and fluorides, chlorides, nitrates or other salts of these compounds as long as the hydrogen content does not exceed the value given in the table, easily
Density of fissile material does not exceed dioxide characteristic value.
A. Several mass limits listed in the table unit of Figure 6 is greater than the critical mass of water reflective sphere. In Table A. 1 ~ A. 11, where the quality limit
Values greater than 90% water by mass critical reflection sphere values are added to the label. For these marked increase over the unit, should take appropriate control measures
Applied to ensure that the sub-critical, for example, geometric control, and should meet the A. 8.9 requirements.
A. 7 Application of tabular data should be cautious. These data only provides a gate element volume (size) and quality limits gate element, must be used
Use can effectively ensure criticality safety measures. Taking into account the operation of some practical factors should be smaller limits.
A. 8 Use Table A. 1 ~ A. The mass limits listed in 11, the following should be considered. Where these cases, should be
Table A. 1 ~ A. 11 as a starting point, consider new quality limits and (or) to consider new quality limit conditions of use.
A. 8.1 moderation. hydrogen atom ratio of fissile material is determined by the fissile material itself, not including the adjacent hydrogen-containing material. Table Regulation
Given the quality of the limits contained in the safety margin, sufficient to compensate for situations such as the kind of slowing down with a thin plastic wrap unit time. This situation is more than
As a significant moderator effect, the calculation method is appropriate after confirmed estimates.
A. Location 8.2 units in the gate elements. each unit should be located in the center of the gate element, gate element deviate from the center of the grid cell size must not exceed the
10%. If the cell mass limit down to 60% of the listed value, the unit in the horizontal position of the gate element can be unrestricted. If after reduction
Quality is still more than 20 percent of the ball bare critical mass, the cell surface minimum distance should not be less than 15.2cm.
A. 8.3 Other reflective materials. mass limits listed in the table also apply to the case of the reflective layer is thinner than the concrete of 12.7cm (Coagulation
Soil surface density ρ = 290kg/m
2). When the thickness of the concrete when the reflective layer is 20.3cm, mass limits should be reduced to 75% of the listed value.
When the thickness of the concrete additional reflective layer, the quality limit should be reduced to 60% of the values listed. Other equivalent thick masonry materials
Degree can be determined by its surface density.
A. 8.4 pairs of the batch. a gate of some element, in some geometric conditions, when the quality of the unit is doubled, the array will be supercritical. But for
Most chunks practical significance of storage units, which belong to the geometry of the relatively small reaction that category. If you can prove bis
Batch gate element in each side gate element is k eff value water reflection not more than 0.93, the table A. 1 ~ A. 11 in the array of such one pair of batch
Gate yuan, the entire array is not supercritical. Or it can prove that, when double batch gate element is reflected in the respective surface of the water when the gate element is subcritical
, The table A. 1 ~ A. 11 array even if there are several (not more than 8) double batch gate yuan, the entire array will not supercritical.
Making fissile material storage safety analysis or the development of procedures, it should consider the problem of double batch of material. If it does occur
Double batch feeding, it should be confirmed that even when a double batch feeding occurs when the gate element in the array is not supercritical. Such as strengthening administrative restrictions
Capacity of the container, properly designed storage units, etc., are beneficial to prevent double batch.
A. 8.5 adjacent storage compartments. for two adjacent storage cells, when the thickness of the concrete thickness of the spacer in and around the concrete wall are equal
, Its mass should be reduced to 55% of the limit values listed in the table. The reduction factor is sufficient to include a concrete reflection effect.
Conditions of use listed value is for a single storage array requirements. When the spacing between the two storage compartments storage arrays with greater than these
The minimum surface dimensions of the surface, you can put two arrays as isolated arrays.
Between the two sub-arrays, when these sub-arrays separated by more than the opposing surfaces of the minimum surface dimensions, these can be seen as an array of seeds
Isolated with an array of reflective layer.
A. Reduction factor 8.6. 8.2 to 8.5 in the required reduction factors can be multiplied. If the result is too conservative, should be used for the system under study
After re-calculation method validation be calculated. For the calculation method to determine the k eff, in order to ensure that no more than the recommended value of k eff 0.95, which should be considered
Accuracy and bias. In the reduction factor for influential factors, the increase in cell size than the gate reduce the mass limit on the reduction factor of more
It is obvious.
A. 8.7 channel. from table A. 1 ~ A. Array 11 removed some of the cells or increase the total volume of the array, so the array aside
Space, form channels. Thereby forming a safety margin sufficient to allow safe access storage areas thus constructed.
A. 8.8 containers and storage rack material. the limits listed in the table have been considered close to the thickness of less than 1.27cm iron effect of the container.
When the thickness is greater than this value, or the use of other materials of iron, its effects will be studied experimentally or calculated using the methods of confirmation.
A. 8.9 times critical of the unit. All material is stored for each unit under flooded conditions should be in a subcritical state.
A. 8.10 spacing unit. storage site of possible flooding, the distance between the surface of the unit should be greater than 15.2cm.
A. 8.11 unit Shape. quality limits apply to any given shape unit.
A. 9 Table A. 1 ~ A. Quality listed 11 limits in other areas of application. the value listed in the table may not be directly used for all real
Inter existing systems. Meet the A. When the provisions set forth in 8, mass limits listed in the table can be extended to the following conditions.
A. 9.1 yuan...
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