CN215183121U - Hydrogen-containing waste gas treatment device for nuclear power station - Google Patents
Hydrogen-containing waste gas treatment device for nuclear power station Download PDFInfo
- Publication number
- CN215183121U CN215183121U CN202022731965.1U CN202022731965U CN215183121U CN 215183121 U CN215183121 U CN 215183121U CN 202022731965 U CN202022731965 U CN 202022731965U CN 215183121 U CN215183121 U CN 215183121U
- Authority
- CN
- China
- Prior art keywords
- space
- nuclear power
- bed
- hydrogen
- power plant
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Images
Landscapes
- Treating Waste Gases (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
- Carbon And Carbon Compounds (AREA)
Abstract
The utility model belongs to the technical field of the nuclear power station exhaust gas system handles, especially relate to a hydrogen-containing exhaust treatment device of nuclear power station. The hydrogen-containing waste gas treatment device for the nuclear power station comprises an active carbon retention bed and a cylinder body with a containing space for containing the active carbon retention bed; the activated carbon retention bed comprises a partition plate, a first layered carbon bed and a second layered carbon bed which are connected to two opposite sides of the partition plate; the accommodation space is divided into a first space and a second space by the partition board, the first layered carbon bed is positioned in the first space and used for installing activated carbon particles in the first space, and the second layered carbon bed is positioned in the second space and used for installing activated carbon particles in the second space. The utility model discloses in, need not to set up the high-pressure holding vessel, reduced the time of nuclear power station waste gas in the storage effectively, avoided the nuclear power station gas to take place the problem of leaking for long-time high-pressure storage, improved the security that radioactive gas discharged; meanwhile, the treatment efficiency of the waste gas of the nuclear power station is improved.
Description
Technical Field
The utility model belongs to the technical field of nuclear power station exhaust-gas treatment system, especially, relate to a hydrogen-containing exhaust-gas treatment device of nuclear power station.
Background
During normal operation and expected operation of a nuclear power plant, hydrogen-containing waste gas with radioactivity is inevitably generated. The hydrogen-containing waste gas mainly comprises hydrogen produced by nuclear fission reaction, radioactive inert gases such as krypton and xenon. In order to meet the national requirements for the emission of exhaust gas from nuclear power plants, the radioactive hydrogen-containing exhaust gas cannot be directly discharged into the air, so as to avoid destroying the natural ecosystem.
In the prior art, a method for treating hydrogen-containing waste gas of a nuclear power plant generally includes collecting radioactive hydrogen-containing waste gas discharged by an upstream nuclear auxiliary system, storing the radioactive hydrogen-containing waste gas in a decay tank after pressurization treatment, and discharging the radioactive hydrogen-containing waste gas to the environment after decay for a period of time. However, the method for storing and discharging the waste gas in the decay tank has high requirement on the pressure of the decay tank, long storage time and potential risk of leakage of the hydrogen-containing waste gas to the environment; and operations such as air inlet, switching, closing, air exhaust and the like are required to be performed on the decay tank manually, and the operation and maintenance work is complex and high in cost.
SUMMERY OF THE UTILITY MODEL
The utility model provides a hydrogen-containing exhaust treatment device of nuclear power station to handling potential risk scheduling problem of revealing of hydrogen-containing waste gas through nuclear power station decay jar among the prior art.
In view of the above technical problems, an embodiment of the present invention provides a hydrogen-containing waste gas treatment device for a nuclear power plant, which includes an activated carbon retention bed and a cylinder having an accommodating space for accommodating the activated carbon retention bed; the activated carbon retention bed comprises a partition plate, a first layered carbon bed and a second layered carbon bed which are connected to two opposite sides of the partition plate; the partition plate divides the accommodating space into a first space and a second space, the first layered carbon bed is positioned in the first space and used for installing activated carbon particles in the first space, and the second layered carbon bed is positioned in the second space and used for installing activated carbon particles in the second space;
the first layered carbon bed is provided with an air inlet pipe communicated with the first space, and the second layered carbon bed is provided with an air outlet pipe communicated with the second space; and a communicating pipe for communicating the first space and the second space is also arranged between the first layered carbon bed and the second layered carbon bed.
Optionally, the first layered carbon bed comprises at least two first semicircular bearing plates arranged at intervals along the axial direction of the cylinder, and the second layered carbon bed comprises at least two second semicircular bearing plates arranged at intervals along the axial direction of the cylinder; and the activated carbon particles are arranged on each first semicircular bearing plate and each second semicircular bearing plate.
Optionally, the first layered carbon bed and the second layered carbon bed are symmetrically disposed.
Optionally, the hydrogen-containing waste gas treatment device of the nuclear power plant further comprises a first flange and a second flange which are arranged at two opposite ends of the cylinder body.
Optionally, the hydrogen-containing waste gas treatment device of the nuclear power plant further comprises a conical cylinder installed between the cylinder body and the second flange, and the cross-sectional area of the conical cylinder, which is perpendicular to the axis of the cylinder body, gradually increases from the second flange towards the direction of the cylinder body.
Optionally, the hydrogen-containing waste gas treatment device of the nuclear power plant further comprises a flow guide pipe, and the air inlet pipe is connected with the first space through the flow guide pipe.
Optionally, the diameter of the activated carbon particles ranges from 3 mm to 5 mm.
Optionally, the hydrogen-containing waste gas treatment device of the nuclear power plant further comprises a plurality of support legs which are arranged on the outer wall of the cylinder body and used for supporting the cylinder body.
Optionally, the hydrogen-containing waste gas treatment device of the nuclear power plant further comprises a lifting appliance installed on the cylinder body.
Optionally, a detector for monitoring activity of the radioactive gas is arranged on the gas outlet pipe.
In the utility model, the active carbon detention bed comprises a baffle plate, a first layered carbon bed and a second layered carbon bed which are connected with the two opposite sides of the baffle plate; the first layered carbon bed is located in the first space and used for installing activated carbon particles in the first space, and the second layered carbon bed is located in the second space and used for installing activated carbon particles in the second space. Radioactive waste gas discharged by the nuclear power station enters the first space from the gas inlet pipe, can be adsorbed by activated carbon particles on the first layered carbon bed, then enters the second space through the communicating pipe, is adsorbed by the activated carbon particles in the second layered carbon bed, and is discharged to the external environment through the gas outlet pipe; krypton and xenon in the exhaust gas need to pass through the processes of adsorption, desorption, reabsorption and reabsorption of the activated carbon particles in the first layered carbon bed and the second layered carbon bed, so that the krypton and xenon are retained in the activated carbon particles for a long time and decay, and finally, the radioactive content in the exhaust gas of the nuclear power station discharged from the gas outlet pipe meets the discharge requirement; the radioactive waste gas of the nuclear power plant of the gas treatment device is mixed gas, wherein most of the radioactive waste gas is non-radioactive gases such as nitrogen, hydrogen, carbon dioxide and the like, the activated carbon particles do not adsorb the gases, and the non-radioactive gases directly pass through the activated carbon detention bed to be discharged into the external environment, so that a high-pressure storage tank is not needed as long as krypton and xenon radioactive gases with extremely small volume are retained, thereby improving the treatment efficiency of the waste gas of the nuclear power plant, avoiding the problem of leakage of the gases of the nuclear power plant due to long-time high-pressure storage, and improving the safety of radioactive gas discharge.
Drawings
The present invention will be further explained with reference to the drawings and examples.
Fig. 1 is a cross-sectional view of a hydrogen-containing waste gas treatment device of a nuclear power plant according to an embodiment of the present invention;
fig. 2 is a plan view of a hydrogen-containing waste gas treatment device of a nuclear power plant according to an embodiment of the present invention;
fig. 3 is a plan view of an activated carbon retention bed of a hydrogen-containing waste gas treatment device of a nuclear power plant according to an embodiment of the present invention;
fig. 4 is a schematic structural diagram of an activated carbon retention bed of a hydrogen-containing waste gas treatment device of a nuclear power plant according to an embodiment of the present invention.
The reference numerals in the specification are as follows:
1. an activated carbon retention bed; 11. a partition plate; 12. a first layered carbon bed; 121. an air inlet pipe; 122. a communicating pipe; 123. a first semicircular bearing plate; 13. a second layered carbon bed; 131. an air outlet pipe; 132. a second semicircular bearing plate; 14. activated carbon particles; 2. a barrel; 21. an accommodating space; 3. a first flange; 4. a second flange; 5. a conical cylinder; 6. a flow guide pipe; 7. and (7) supporting legs.
Detailed Description
In order to make the technical problem, technical solution and advantageous effects solved by the present invention more clearly understood, the following description is given in conjunction with the accompanying drawings and embodiments to illustrate the present invention in further detail. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the invention.
It is to be understood that the terms "upper", "lower", "left", "right", "front", "rear", "middle", and the like, indicate orientations or positional relationships based on the orientations or positional relationships shown in the drawings, and are merely for convenience in describing the present invention and simplifying the description, and do not indicate or imply that the device or element referred to must have a particular orientation, be constructed in a particular orientation, and be operated, and thus, should not be construed as limiting the present invention.
As shown in fig. 1 to 4, a hydrogen-containing waste gas treatment device for a nuclear power station according to an embodiment of the present invention includes an activated carbon retention bed 1 and a cylinder 2 having a receiving space 21 for receiving the activated carbon retention bed 1; the activated carbon retention bed 1 comprises a partition plate 11, and a first layered carbon bed 12 and a second layered carbon bed 13 which are connected to two opposite sides of the partition plate 11; the partition 11 divides the accommodating space 21 into a first space (not shown) in which the first layered carbon bed 12 is located and used for installing the activated carbon granules 14 and a second space (not shown) in which the second layered carbon bed 13 is located and used for installing the activated carbon granules 14; it is understood that the number of layers of the first layered carbon bed 12 and the second layered carbon bed 13 can be set according to the actual requirement and the size of the barrel 2. Preferably, the diameter of the activated carbon particles 14 ranges from 3 mm to 5mm, such as 3.5mm, 4mm, 4.5mm, and the like; it is understood that the diameter of the activated carbon particles 13 can be set to other values according to actual requirements, such as 6mm, 7mm, etc., and the activated carbon particles 13 need to be hardened and activated to have an adsorption function (i.e., the activated carbon particles 13 mounted on the activated carbon retention bed 1 need to be hardened and activated).
An air inlet pipe 121 communicated with the first space is arranged on the first layered carbon bed 12, and an air outlet pipe 131 communicated with the second space is arranged on the second layered carbon bed 13; a communicating pipe 122 for communicating the first space and the second space is further provided between the first layered carbon bed 12 and the second layered carbon bed 13. Preferably, the gas inlet pipe 121 is connected to the upper end of the first layered carbon bed 12, the opposite ends of the communicating pipe 122 are connected to the lower ends of the first layered carbon bed 12 and the second layered carbon bed 13, and the gas outlet pipe 131 is connected to the upper end of the second layered carbon bed 13. The communicating pipe is in a U-shaped structure, and the first space and the second space are both two semicircular spaces formed by dividing the accommodating space 21 of the cylinder 2 by the partition plate 11.
Specifically, the activated carbon particles 14 in the activated carbon retention bed 1 can adsorb radioactive gases such as Kr and Xe in the exhaust gas of the nuclear power plant, and can react with non-radioactive N2、H2、CO2Etc. which do not adsorb, these non-radioactive gases may pass directly through the activated carbon granules 14.
In the utility model, the active carbon detention bed 1 comprises a baffle 11, and a first layered carbon bed 12 and a second layered carbon bed 13 which are connected with two opposite sides of the baffle 11; the first layered carbon bed 12 is located in the first space and is used for installing activated carbon granules 14 in the first space, and the second layered carbon bed 13 is located in the second space and is used for installing activated carbon granules 14 in the second space. Radioactive waste gas discharged by the nuclear power station enters the first space from the gas inlet pipe 121, is adsorbed by the activated carbon particles 14 on the first layered carbon bed 12, then enters the second space through the communicating pipe 122, is adsorbed by the activated carbon particles 14 in the second layered carbon bed 13, and is discharged to the external environment through the gas outlet pipe 131; wherein, the nuclear power plant waste gas in the first layered carbon bed 12 and the second layered carbon bed 13 needs to pass through the processes of adsorption-desorption-reabsorption of the activated carbon particles 14, so that the radioactive waste gas of the nuclear power plant is retained in the activated carbon particles 14 for a long time and decays, and finally, the amount of the radioactive content in the nuclear power plant waste gas discharged from the gas outlet pipe 131 meets the emission requirement; therefore, the hydrogen-containing waste gas treatment device for the nuclear power station improves the treatment efficiency of the waste gas of the nuclear power station, and meanwhile, a high-pressure storage tank is not required to be arranged, so that the storage time of the waste gas of the nuclear power station is effectively shortened, the problem of leakage caused by long-time high-pressure storage of the waste gas of the nuclear power station is avoided, and the safety of radioactive gas emission is improved.
In one embodiment, as shown in fig. 3 and 4, the first layered carbon bed 12 comprises at least two first semicircular bearing plates 123 arranged at intervals along the axial direction of the cylinder 2, and the second layered carbon bed 13 comprises at least two second semicircular bearing plates 132 arranged at intervals along the axial direction of the cylinder 2; the activated carbon granules 14 are mounted on each of the first semicircular bearing plate 123 and the second semicircular bearing plate 132. It can be understood that the first and second semicircular bearing plates 123 and 132 can be arranged as five, six, eight, ten, etc. according to actual requirements; the partition plate 11 partitions the inner installation space of the cylinder 2 into a first space for installing the first semicircular loading plate 123 and a second space for installing the second loading plate. Each first semicircular bearing plate 123 and each second semicircular bearing plate 132 are both in a semicircular design, so that the inner space of the cylinder body 2 can be utilized to the maximum extent, more activated carbon particles 14 can be arranged, and the adsorption efficiency of the hydrogen-containing waste gas treatment device of the nuclear power station on the waste gas of the nuclear power station is improved.
Further, the distance between each first semicircular bearing plate 123 can be set according to actual requirements, and the distance between each second semicircular bearing plate 132 can be set according to actual requirements.
In one embodiment, as shown in fig. 3 and 4, the first layered carbon bed 12 and the second layered carbon bed 13 are symmetrically disposed. Specifically, the first layered carbon bed 12 and the second layered carbon canister are symmetrically disposed with respect to the partition 11. Understandably, the first layered carbon bed 12 and the second layered carbon bed 13 which are symmetrically arranged have simple structures and low manufacturing cost, and simultaneously improve the adsorption efficiency of the activated carbon particles 14.
In one embodiment, as shown in fig. 1, the hydrogen-containing waste gas treatment device for the nuclear power plant further comprises a first flange 3 and a second flange 4 which are arranged at two opposite ends of the cylinder 2. Preferably, the hydrogen-containing waste gas treatment device for the nuclear power plant further comprises a conical cylinder 5 installed between the cylinder 2 and the second flange 4, and the cross-sectional area of the conical cylinder 5 perpendicular to the axis of the cylinder 2 gradually increases from the second flange 4 toward the cylinder 2. It is understood that the cone 5 has a shape with a large upper opening and a small lower opening. As can be understood, the first flange 3 and the second flange 4 are respectively installed at the upper end and the lower end of the sleeve and are used for sealing the upper end and the lower end of the barrel 2, so that the leakage of the nuclear power plant exhaust gas entering the barrel 2 is avoided.
In addition, the first flange 3 may be designed such that the activated carbon retention bed 1 is taken out from the upper end port of the cylinder 2 at the time of future maintenance; the design of the second flange 4 provides an inlet for monitoring the adsorption performance of the activated carbon particles 14 regularly in the future; before the activated carbon retention bed 1 is maintained, the second flange 4 needs to be opened, and N is blown into the cylinder 2 through the lower port of the cylinder 22Thereby ensuring that the radioactivity content and the hydrogen content of the nuclear power plant exhaust gas remaining in the barrel 2 are reduced.
In an embodiment, as shown in fig. 1, the hydrogen-containing waste gas treatment device of the nuclear power plant further includes a draft tube 6, and the air inlet pipe 121 is connected to the first space through the draft tube 6. As can be understood, the activated carbon particles 14 have a certain radioactivity after absorbing the exhaust gas discharged from the nuclear power plant; radioactive substances released by the activated carbon particles 14 pass through the outer wall of the cylinder 2 and are released to the external environment of the nuclear electric control area; in order to reduce the influence of the activated carbon particles 14 on the external environment of the nuclear power control area, the flow guide pipe 6 presents a state that the middle flow rate of the nuclear power plant exhaust gas discharged to the first layered carbon bed 12 is large and the outer flow rate of the nuclear power plant exhaust gas is small (specifically, the cross section of the opening of the flow guide pipe 6 gradually decreases from the partition plate 11 along the inner wall of the cylinder 2, that is, the opening of the flow guide pipe 6 at the position close to the partition plate 11 is large, and the opening at the position close to the inner wall of the cylinder 2 is small), and the design of the flow guide pipe 6 increases the safety of the hydrogen-containing exhaust gas treatment device of the nuclear power plant.
In an embodiment, as shown in fig. 1 and 2, the hydrogen-containing waste gas treatment device for a nuclear power plant further comprises a plurality of legs 7 mounted on the outer wall of the cylinder 2 and used for supporting the cylinder 2. It can be understood that the number of the legs 7 can be designed according to actual requirements, for example, three legs 7 are uniformly arranged along the circumferential direction of the cylinder 2, and for example, four legs 7 are uniformly arranged along the circumferential direction of the cylinder 2.
In an embodiment, the apparatus for treating hydrogen-containing waste gas from a nuclear power plant further includes a hanger (not shown) mounted on the barrel 2. It can understand, on the crossbeam in house can be installed to the hoist, when needs follow take off in the barrel 2 during active carbon detention bed 1, the hoist can be followed hang out in the barrel 2 active carbon detention bed 1 to make things convenient for nuclear power station maintenance personnel to take out active carbon detention bed 1 has reduced nuclear power station maintenance personnel's work load.
In one embodiment, the gas outlet tube 131 is provided with a detector (not shown) for monitoring activity of the radioactive gas. Preferably, the detector is a beta sensitive detector, which can be used to monitor the activity concentration of the radioactive gas after adsorption on the activated carbon retention bed 1. The design of the detector further ensures that the exhaust gas discharged to the environment is of a type that meets emission standards (low activity).
The above description is only an embodiment of the hydrogen-containing waste gas treatment device for nuclear power plant, and should not be construed as limiting the present invention, and any modification, equivalent replacement, and improvement made within the spirit and principle of the present invention should be included in the protection scope of the present invention.
Claims (10)
1. The hydrogen-containing waste gas treatment device for the nuclear power station is characterized by comprising an active carbon retention bed and a cylinder body, wherein the cylinder body is provided with a containing space for containing the active carbon retention bed; the activated carbon retention bed comprises a partition plate, a first layered carbon bed and a second layered carbon bed which are connected to two opposite sides of the partition plate; the partition plate divides the accommodating space into a first space and a second space, the first layered carbon bed is positioned in the first space and used for installing activated carbon particles in the first space, and the second layered carbon bed is positioned in the second space and used for installing activated carbon particles in the second space;
the first layered carbon bed is provided with an air inlet pipe communicated with the first space, and the second layered carbon bed is provided with an air outlet pipe communicated with the second space; and a communicating pipe for communicating the first space and the second space is also arranged between the first layered carbon bed and the second layered carbon bed.
2. The apparatus for treating hydrogen-containing exhaust gas from nuclear power plant according to claim 1, wherein the first layered carbon bed comprises at least two first semicircular bearing plates arranged at intervals in the axial direction of the cylindrical body, and the second layered carbon bed comprises at least two second semicircular bearing plates arranged at intervals in the axial direction of the cylindrical body; and the activated carbon particles are arranged on each first semicircular bearing plate and each second semicircular bearing plate.
3. The apparatus for treating hydrogen-containing off-gas in nuclear power plant according to claim 1, wherein the first and second layered carbon beds are symmetrically disposed.
4. The nuclear power plant hydrogen-containing exhaust gas treatment device according to claim 1, further comprising a first flange and a second flange mounted at opposite ends of the barrel.
5. The apparatus for treating hydrogen-containing exhaust gas from a nuclear power plant according to claim 4, further comprising a conical cylinder installed between the cylinder and the second flange, wherein a cross-sectional area of the conical cylinder perpendicular to an axis of the cylinder increases gradually from the second flange toward the cylinder.
6. The apparatus for treating hydrogen-containing off-gas in a nuclear power plant according to claim 1, further comprising a flow guide pipe through which the intake pipe is connected to the first space.
7. The device for treating the hydrogen-containing waste gas in the nuclear power plant according to claim 1, wherein the diameter of the activated carbon particles ranges from 3 mm to 5 mm.
8. The nuclear power plant hydrogen-containing exhaust gas treatment device according to claim 1, further comprising a plurality of legs mounted on an outer wall of the cylinder and supporting the cylinder.
9. The nuclear power plant hydrogen-containing exhaust gas treatment device according to claim 1, further comprising a hanger mounted on the barrel.
10. The apparatus for treating hydrogen-containing waste gas from nuclear power plant according to claim 1, wherein the gas outlet pipe is provided with a detector for monitoring activity of radioactive gas.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202022731965.1U CN215183121U (en) | 2020-11-23 | 2020-11-23 | Hydrogen-containing waste gas treatment device for nuclear power station |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202022731965.1U CN215183121U (en) | 2020-11-23 | 2020-11-23 | Hydrogen-containing waste gas treatment device for nuclear power station |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN215183121U true CN215183121U (en) | 2021-12-14 |
Family
ID=79350367
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202022731965.1U Active CN215183121U (en) | 2020-11-23 | 2020-11-23 | Hydrogen-containing waste gas treatment device for nuclear power station |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN215183121U (en) |
-
2020
- 2020-11-23 CN CN202022731965.1U patent/CN215183121U/en active Active
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN112717625A (en) | Hydrogen-containing waste gas treatment system of nuclear power station | |
| CN202460420U (en) | Breathing bucket device for purifying tail gas exhausted by storage tank | |
| CN110954939B (en) | Tritium monitor laboratory calibrating device | |
| CN109166641B (en) | Low-level radioactive waste gas treatment system in lead bismuth reactor | |
| CN104143368B (en) | Nuclear power station radioactive waste gas treatment system | |
| CN208742218U (en) | A kind of activated carbon adsorption device | |
| CN215183121U (en) | Hydrogen-containing waste gas treatment device for nuclear power station | |
| CN102226949B (en) | Method and device for carrying out adsorption quantity improvement and dehydrogenation on radioactive gases | |
| CN105355249A (en) | Radioactive waste gas processing device for nuclear power station | |
| CN103871532B (en) | Non-tight radioactive substance storage cabinet | |
| CN112691501A (en) | Modular adsorption bed with high sealing performance | |
| CN111174101A (en) | Self-releasing absorption type hydrogen active safety protection device | |
| KR20170069618A (en) | Hydrogen storage apparatus using a metal hydride of pillar | |
| CN115295199A (en) | Hydrogen-containing radioactive waste gas treatment system and method for nuclear power plant | |
| CN112473340A (en) | Nuclear power plant containment filtering and discharging system | |
| CN208878213U (en) | A kind of VOCs adsorption/desorption active carbon case | |
| CN108364698B (en) | Hydrogen elimination method and system for small space of nuclear power station | |
| CN214715488U (en) | Modular adsorption bed with high sealing performance | |
| CN112712909A (en) | Feeding device for soluble neutron poison | |
| CN214624458U (en) | Nuclear power station exhaust treatment device | |
| CN111156415B (en) | Hydrogen leakage adsorption system | |
| CN217822091U (en) | Hydrogen-containing radioactive waste gas treatment device | |
| CN217795324U (en) | VOC gas composite material adsorption equipment | |
| CN210356638U (en) | Production system for treating butanol tail gas generated by butyl glycolate device | |
| CN219043328U (en) | Sealing shielding system for gaseous Po-210 test |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| GR01 | Patent grant | ||
| GR01 | Patent grant |