CN105825904B - A kind of presurized water reactor recovery uranium is applied to the method for PHWR - Google Patents
A kind of presurized water reactor recovery uranium is applied to the method for PHWR Download PDFInfo
- Publication number
- CN105825904B CN105825904B CN201511020274.8A CN201511020274A CN105825904B CN 105825904 B CN105825904 B CN 105825904B CN 201511020274 A CN201511020274 A CN 201511020274A CN 105825904 B CN105825904 B CN 105825904B
- Authority
- CN
- China
- Prior art keywords
- uranium
- mrow
- recovery
- msubsup
- depleted
- 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
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Manufacturing & Machinery (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
The present invention provides a kind of method that presurized water reactor recovery uranium is applied to PHWR, and this method replaces natural uranium using equivalent natural uranium, the fuel for PHWR is produced on PHWR fuel production line;Equivalent natural uranium is made using following steps:(1) it is distributed using mass spectrograph measurement recovery uranium and metal uranium content, uranium isotope component and/or uranium isotope in depleted uranium;(2) according to the uranium isotope component of recovery uranium and depleted uranium, the mixed proportion α and 1 α and NUE desired values that reclaim uranium and depleted uranium for reaching equivalent with natural uranium are calculated using formula or batch mixing calculation procedure;(3) precise recovery uranium and depleted uranium, then carry out physically be mixed to form equivalent natural uranium;(4) analysis is sampled to the equivalent natural uranium being mixed to form;(5) fuel making of the natural uranium for PHWR is replaced using equivalent natural uranium.Present invention, avoiding the high influence of recovery uranium radioactivity, can realize that economical and efficient utilizes to recovery uranium;Reduce PHWR fuel cost.
Description
Technical field
The present invention relates to nuclear fuel recycling, and in particular to what presurized water reactor recovery uranium (abbreviation RU) utilized on PHWR
Method.
Background technology
Presurized water reactor is typically used as fuel using natural slightly enriched uranium (LEU).The fuel unloads after in-pile irradiation certain time
Go out reactor core, be referred to as spentnuclear fuel.About 94% material is uranium in presurized water reactor spentnuclear fuel, and the material is carried by post-processing technology separation
It is referred to as reclaiming uranium (also referred to as uranium after heap) after taking out.The uranium isotope composition and natural uranium (abbreviation NU) for reclaiming uranium have difference
It is different, reclaim in uranium and add man-made isotope232U、234U,236Fission product and actinides (such as Pu and Am of U and trace
Deng).Reclaim in uranium234U content is generally greater than natural uranium,235U enrichments are about 0.8%-1.5%.For convenience of storage management,
Uranium is reclaimed typically with UO3Or U3O8Form exist.
Recovery uranium utilizes on presurized water reactor, it is necessary to improves therein235U enrichments, typically using two ways:One kind is
Concentrate again, a kind of is to be mixed with the natural LEU of higher enrichment and (turn into high mixed later).For concentrating again,232U
、236U and234U is synchronously concentrated, and causes the radioactive level of fuel to significantly increase, and is needed more235U is compensated236U and234U causes
Neutron loss, while fuel cost is apparently higher than natural LEU fuel.For height is mixed, although the radioactivity of fuel can be with
Significantly reduce, but the utilization ratio for reclaiming uranium is very low, saves having little significance for natural uranium resource.Therefore, reclaim in the world at present
It is stand-by to be mostly converted into more stable form storage in addition to small part use for uranium.
On being utilized on PHWR, main research recovery uranium directly utilizes on PHWR both at home and abroad at present, to recovery
In uranium235U enrichments are not added with adjusting, and recovery uranium is equivalent to a kind of slightly enriched uranium.For fuel making cost is larger and reactor core turns
Originally the reason such as higher, this fuel have not yet to see the example of demonstration or engineer applied for chemical conversion.
The content of the invention
A kind of method of the invention for providing presurized water reactor recovery uranium and being applied to PHWR, it utilizes for recovery uranium and provides a warp
Help efficient approach, can not only utilize on operation PHWR but also on newly-built PHWR.
Realize the technical scheme of the object of the invention:A kind of presurized water reactor recovery uranium is applied to the method for PHWR, and this method makes
Natural uranium (abbreviation NU) is replaced with equivalent natural uranium (abbreviation NUE), is produced on PHWR fuel production line for PHWR
Fuel;Described equivalent natural uranium is made using following steps:
(1) using mass spectrograph measurement recovery uranium and metal uranium content, uranium isotope component and/or uranium isotope in depleted uranium
Distribution;
(2) according to the recovery uranium of step (1) and the uranium isotope component of depleted uranium, using formula or based on Neutronics calculation journey
Sequence WIMS-AECL, or WIMS-D, or the MCNP batch mixing calculation procedure developed of calculating are calculated and reached and natural uranium is equivalent returns
Receive mixed proportion α and the 1- α of uranium and depleted uranium, 0 < α≤1 and NUE desired values;
(3) according to step (2) ratio, precise recovery uranium and depleted uranium, being mixed to form physically is then carried out
Equivalent natural uranium;
(4) the equivalent natural uranium being mixed to form to step (3) is sampled analysis;
NUE and NU nuclear properties equivalence is analyzed, it requires that the NUE's that batch mixing calculation procedure is calculated and NU is initial anti-
Answer sex differernce be less than 5.71mk and NUE fuel discharge burn-up the discharge burn-up of natural uranium fuel ± 75MWd/tU with
It is interior;Or analyze what is obtained235U,234U and236U enrichment is within ± the 0.001% of NUE desired values.
If meeting above-mentioned requirements, step (5) is carried out;Above-mentioned requirements are not met such as, then add depleted uranium or recovery uranium
Adjust in equivalent natural uranium235U weight percent content is until reach requirement;
(5) fuel making of the natural uranium for PHWR is replaced using equivalent natural uranium.
A kind of presurized water reactor recovery uranium as described above is applied to the method for PHWR, the use formula described in its step (2)
Mixed proportion α and the 1- α of the recovery uranium for reaching equivalent with natural uranium and depleted uranium is calculated, formula is as follows:
In above formulaRespectively equivalent natural uranium 235, recovery uranium 236, recovery uranium
234th, the weight percent content of uranium 235 and the uranium isotope in poor uranium 235 is reclaimed;In formula, a=0.708, b=
0.04395935 and c=0.1801096.
A kind of presurized water reactor recovery uranium as described above is applied to the method for PHWR, recovery uranium described in its step (3) and
Depleted uranium carry out physically be mixed to form equivalent natural uranium, will reclaim uranium specifically by dry method or wet method and depleted uranium mixes.
A kind of presurized water reactor recovery uranium as described above is applied to the method for PHWR, recovery uranium described in its step (3) and
Depleted uranium carry out physically be mixed to form equivalent natural uranium, specially with suction or other equipment by material be added to dissolving tank or
In dissolving tank, and dissolved, stirred with the nitric acid more than 3mol/L.
A kind of presurized water reactor recovery uranium as described above is applied to the method for PHWR, recovery uranium described in its step (3) and
Depleted uranium carry out physically be mixed to form equivalent natural uranium, material is specially added to single cone spiral with suction or other equipment
Or premixed in other mixing devices, then material is launched into dissolving tank or dissolving tank, with the nitric acid more than 3mol/L
Dissolved and stirred.
A kind of presurized water reactor recovery uranium as described above is applied to the method for PHWR, and the equivalent natural uranium described in it is using such as
Lower step is made:
(1) using mass spectrograph measurement recovery uranium and metal uranium content, uranium isotope component and/or uranium isotope in depleted uranium
Distribution;
(2) according to the recovery uranium of step (1) and the uranium isotope component of depleted uranium, using formula or based on Neutronics calculation journey
Sequence WIMS-AECL, or WIMS-D, or the MCNP batch mixing calculation procedure developed of calculating are calculated and reached and natural uranium is equivalent returns
Receive mixed proportion α and the 1- α of uranium and depleted uranium, 0 < α≤1 and NUE desired values;
Formula is as follows:
In above formulaRespectively equivalent natural uranium 235, recovery uranium 236, recovery uranium
234th, the weight percent content of uranium 235 and the uranium isotope in poor uranium 235 is reclaimed;
In formula, a=0.708, b=0.04395935 and c=0.1801096;
(3) according to step (2) ratio, precise recovery uranium and depleted uranium, being mixed to form physically is then carried out
Equivalent natural uranium;
Described recovery uranium and depleted uranium carry out physically be mixed to form equivalent natural uranium, specially with suction or other set
It is standby that material is added in dissolving tank or dissolving tank, and dissolved with the nitric acid more than 3mol/L, stir;
Or described recovery uranium and depleted uranium carry out physically be mixed to form equivalent natural uranium, specially with suction or its
Material is added in single cone spiral or other mixing devices by his equipment to be premixed, and is then launched material and is arrived dissolving tank or molten
Solve in tank, dissolved and stirred with the nitric acid more than 3mol/L;
(4) the equivalent natural uranium being mixed to form to step (3) is sampled analysis;
NUE and NU nuclear properties equivalence is analyzed, it requires that the NUE's that batch mixing calculation procedure is calculated and NU is initial anti-
Answer sex differernce be less than 5.71mk and NUE fuel discharge burn-up the discharge burn-up of natural uranium fuel ± 75MWd/tU with
It is interior;Or analyze what is obtained235U,234U and236U enrichment is within ± the 0.001% of NUE desired values;
If meeting above-mentioned requirements, step (5) is carried out;Above-mentioned requirements are not met such as, then add depleted uranium or recovery uranium
Adjust in equivalent natural uranium235U weight percent content is until reach requirement;
(5) fuel making of the natural uranium for PHWR is replaced using equivalent natural uranium.
Effect of the invention is that:A kind of presurized water reactor recovery uranium of the present invention is applied to the method for PHWR, and it is kept away
Exempt to reclaim the high influence of uranium radioactivity, can realize that economical and efficient utilizes to recovery uranium;The technology can run and newly-built
It is applicable on PHWR.The diversified PHWR nuclear fuel source of the present invention, reduces PHWR fuel cost.Presurized water reactor of the present invention returns
Receive uranium and be used for PHWR, important supplement is provided for nuclear fuel enclosed fuel circulating system.
Embodiment
The method for being applied to PHWR to a kind of presurized water reactor recovery uranium of the present invention with reference to specific embodiment is made
Further describe.
Embodiment 1
According to recovery uranium235U enrichments are higher than the characteristics of natural uranium, are mixed with depleted uranium (DU) with recovery uranium, by accurate
The mixed proportion of regulation recovery uranium and depleted uranium, makes the nuclear properties of mixture and natural uranium fuel equivalent.Letter after this mixture
Claim equivalent natural uranium.The present invention replaces natural uranium using equivalent natural uranium, and carrying out production on PHWR fuel production line is used for
The fuel of PHWR.
Comprise the following steps that:
(1) using mass spectrograph measurement recovery uranium and metal uranium content, uranium isotope component and/or uranium isotope in depleted uranium
Distribution;
(2) according to the recovery uranium of step (1) and the uranium isotope component of depleted uranium, calculated and reached with natural uranium etc. using formula
The recovery uranium of effect and mixed proportion α and the 1- α of depleted uranium, 0 < α≤1 and NUE desired values;
Described mixed proportion α and the 1- α that the recovery uranium for reaching equivalent with natural uranium and depleted uranium are calculated using formula, formula
It is as follows:
In above formulaRespectively equivalent natural uranium 235, recovery uranium 236, recovery uranium
234th, the weight percent content of uranium 235 and the uranium isotope in poor uranium 235 is reclaimed;In formula, a=0.708, b=
0.04395935 and c=0.1801096.
(3) according to step (2) ratio, precise recovery uranium and depleted uranium, being mixed to form physically is then carried out
Equivalent natural uranium;Described recovery uranium and depleted uranium carry out physically be mixed to form equivalent natural uranium, specially with suction or its
Material is added in dissolving tank or dissolving tank equipment by he, and is dissolved with the nitric acid more than 3mol/L, stirs.
(4) the equivalent natural uranium being mixed to form to step (3) is sampled analysis;
NUE and NU nuclear properties equivalence is analyzed, it requires what analysis obtained235U,234U and236U enrichment is in NUE mesh
Within ± the 0.001% of scale value;
If meeting above-mentioned requirements, step (5) is carried out;Above-mentioned requirements are not met such as, then add depleted uranium or recovery uranium
Adjust in equivalent natural uranium235U weight percent content is until reach requirement;
(5) fuel making of the natural uranium for PHWR is replaced using equivalent natural uranium.
Embodiment 2
The present invention replaces natural uranium using equivalent natural uranium, and production is carried out on PHWR fuel production line and is used for PHWR
Fuel.
Comprise the following steps that:
(1) using mass spectrograph measurement recovery uranium and metal uranium content, uranium isotope component and/or uranium isotope in depleted uranium
Distribution;
(2) according to the recovery uranium of step (1) and the uranium isotope component of depleted uranium, using based on Neutronics calculation program
WIMS-AECL, or WIMS-D, or the MCNP batch mixing calculation procedure developed of calculating calculate and reach the recovery equivalent with natural uranium
Mixed proportion α and the 1- α of uranium and depleted uranium, 0 < α≤1 and NUE desired values;
(3) according to step (2) ratio, precise recovery uranium and depleted uranium, being mixed to form physically is then carried out
Equivalent natural uranium;Described recovery uranium and depleted uranium carry out physically be mixed to form equivalent natural uranium, specially with suction or its
Material is added in single cone spiral or other mixing devices by his equipment to be premixed, and is then launched material and is arrived dissolving tank or molten
Solve in tank, dissolved and stirred with the nitric acid more than 3mol/L;
(4) the equivalent natural uranium being mixed to form to step (3) is sampled analysis;
NUE and NU nuclear properties equivalence is analyzed, it requires what analysis obtained235U,234U and236U enrichment is in NUE mesh
Within ± the 0.001% of scale value;
If meeting above-mentioned requirements, step (5) is carried out;Above-mentioned requirements are not met such as, then add depleted uranium or recovery uranium
Adjust in equivalent natural uranium235U weight percent content is until reach requirement;
(5) fuel making of the natural uranium for PHWR is replaced using equivalent natural uranium.
Embodiment 3
The present invention replaces natural uranium using equivalent natural uranium, and production is carried out on PHWR fuel production line and is used for PHWR
Fuel.
Comprise the following steps that:
(1) using mass spectrograph measurement recovery uranium and metal uranium content, uranium isotope component and/or uranium isotope in depleted uranium
Distribution;
(2) according to step (1) recovery uranium and depleted uranium uranium isotope component, using batch mixing calculation procedure calculate reach with
Mixed proportion α and the 1- α of the equivalent recovery uranium of natural uranium and depleted uranium, 0 < α≤1 and NUE desired values;
The batch mixing calculation procedure is to be based on Neutronics calculation program WIMS-AECL, or WIMS-D, or MCNP calculating institute
The computer program of exploitation.
(3) according to step (2) ratio, precise recovery uranium and depleted uranium, being mixed to form physically is then carried out
Equivalent natural uranium;Uranium will be reclaimed specifically by dry method or wet method and depleted uranium mixes.
(4) the equivalent natural uranium being mixed to form to step (3) is sampled analysis;
NUE and NU nuclear properties equivalence is analyzed, it requires that the NUE's that batch mixing calculation procedure is calculated and NU is initial anti-
Answer sex differernce be less than 5.71mk and NUE fuel discharge burn-up the discharge burn-up of natural uranium fuel ± 75MWd/tU with
It is interior;
If meeting above-mentioned requirements, step (5) is carried out;Above-mentioned requirements are not met such as, then add depleted uranium or recovery uranium
Adjust in equivalent natural uranium235U weight percent content is until reach requirement;
(5) fuel making of the natural uranium for PHWR is replaced using equivalent natural uranium.
Claims (5)
1. a kind of presurized water reactor recovery uranium is applied to the method for PHWR, it is characterised in that this method uses equivalent natural uranium (abbreviation
NUE natural uranium (abbreviation NU)) is replaced, the fuel for PHWR is produced on PHWR fuel production line;Described equivalent day
Right uranium is made using following steps:
(1) using mass spectrograph measurement recovery uranium and metal uranium content, uranium isotope component and/or uranium isotope point in depleted uranium
Cloth;
(2) according to the recovery uranium of step (1) and the uranium isotope component of depleted uranium, using formula or based on Neutronics calculation program
WIMS-AECL, or WIMS-D, or MCNP calculate developed batch mixing calculation procedure and calculated and reach the recovery uranium equivalent with natural uranium
With mixed proportion α and the 1- α of depleted uranium, 0 < α≤1 and NUE desired values;
Described mixed proportion α and the 1- α that the recovery uranium for reaching equivalent with natural uranium and depleted uranium are calculated using formula, formula is such as
Under:
<mrow>
<mi>&alpha;</mi>
<mo>=</mo>
<mfrac>
<mrow>
<msubsup>
<mi>U</mi>
<mrow>
<mi>N</mi>
<mi>U</mi>
<mi>E</mi>
</mrow>
<mn>235</mn>
</msubsup>
<mo>-</mo>
<msubsup>
<mi>U</mi>
<mrow>
<mi>D</mi>
<mi>U</mi>
</mrow>
<mn>235</mn>
</msubsup>
</mrow>
<mrow>
<msubsup>
<mi>U</mi>
<mrow>
<mi>R</mi>
<mi>U</mi>
</mrow>
<mn>235</mn>
</msubsup>
<mo>-</mo>
<msubsup>
<mi>U</mi>
<mrow>
<mi>D</mi>
<mi>U</mi>
</mrow>
<mn>235</mn>
</msubsup>
</mrow>
</mfrac>
</mrow>
<mrow>
<msubsup>
<mi>U</mi>
<mrow>
<mi>N</mi>
<mi>U</mi>
<mi>E</mi>
</mrow>
<mn>235</mn>
</msubsup>
<mo>=</mo>
<mi>a</mi>
<mo>+</mo>
<mi>b</mi>
<mo>*</mo>
<msubsup>
<mi>U</mi>
<mrow>
<mi>R</mi>
<mi>U</mi>
</mrow>
<mn>236</mn>
</msubsup>
<mo>+</mo>
<mi>c</mi>
<mo>*</mo>
<msubsup>
<mi>U</mi>
<mrow>
<mi>R</mi>
<mi>U</mi>
</mrow>
<mn>234</mn>
</msubsup>
</mrow>
In above formulaRespectively equivalent natural uranium 235, recovery uranium 236, recovery uranium 234,
Reclaim the weight percent content of uranium 235 and the uranium isotope in poor uranium 235;In formula, a=0.708, b=0.04395935
And c=0.1801096;
(3) according to step (2) ratio, precise recovery uranium and depleted uranium, then carry out physically be mixed to form it is equivalent
Natural uranium;
(4) the equivalent natural uranium being mixed to form to step (3) is sampled analysis;
NUE and NU nuclear properties equivalence is analyzed, it requires the NUE that batch mixing calculation procedure is calculated and NU initial reactivity
Difference is less than the discharge burn-up of 5.71mk and NUE fuel within the ± 75MWd/tU of the discharge burn-up of natural uranium fuel;Or
What analysis obtained235U,234U and236U enrichment is within ± the 0.001% of NUE desired values;
If meeting above-mentioned requirements, step (5) is carried out;Above-mentioned requirements are not met such as, then add depleted uranium or recovery uranium regulation
In equivalent natural uranium235U weight percent content is until reach requirement;
(5) fuel making of the natural uranium for PHWR is replaced using equivalent natural uranium.
2. a kind of presurized water reactor recovery uranium according to claim 1 is applied to the method for PHWR, it is characterised in that step
(3) recovery uranium described in and depleted uranium carry out physically be mixed to form equivalent natural uranium, will specifically by dry method or wet method
Reclaim uranium and depleted uranium mixing.
3. a kind of presurized water reactor recovery uranium according to claim 1 is applied to the method for PHWR, it is characterised in that step
(3) recovery uranium described in and depleted uranium carry out physically be mixed to form equivalent natural uranium, specially will with suction or other equipment
Material is added in dissolving tank or dissolving tank, and is dissolved with the nitric acid more than 3mol/L, stirs.
4. a kind of presurized water reactor recovery uranium according to claim 1 is applied to the method for PHWR, it is characterised in that step
(3) recovery uranium described in and depleted uranium carry out physically be mixed to form equivalent natural uranium, specially will with suction or other equipment
Material, which is added in single cone spiral or other mixing devices, to be premixed, and then launches material into dissolving tank or dissolving tank,
Dissolved and stirred with the nitric acid more than 3mol/L.
5. a kind of presurized water reactor recovery uranium according to claim 1 is applied to the method for PHWR, it is characterised in that described
Equivalent natural uranium is made using following steps:
(1) using mass spectrograph measurement recovery uranium and metal uranium content, uranium isotope component and/or uranium isotope point in depleted uranium
Cloth;
(2) according to the recovery uranium of step (1) and the uranium isotope component of depleted uranium, using formula or based on Neutronics calculation program
WIMS-AECL, or WIMS-D, or MCNP calculate developed batch mixing calculation procedure and calculated and reach the recovery uranium equivalent with natural uranium
With mixed proportion α and the 1- α of depleted uranium, 0 < α≤1 and NUE desired values;
Formula is as follows:
<mrow>
<mi>&alpha;</mi>
<mo>=</mo>
<mfrac>
<mrow>
<msubsup>
<mi>U</mi>
<mrow>
<mi>N</mi>
<mi>U</mi>
<mi>E</mi>
</mrow>
<mn>235</mn>
</msubsup>
<mo>-</mo>
<msubsup>
<mi>U</mi>
<mrow>
<mi>D</mi>
<mi>U</mi>
</mrow>
<mn>235</mn>
</msubsup>
</mrow>
<mrow>
<msubsup>
<mi>U</mi>
<mrow>
<mi>R</mi>
<mi>U</mi>
</mrow>
<mn>235</mn>
</msubsup>
<mo>-</mo>
<msubsup>
<mi>U</mi>
<mrow>
<mi>D</mi>
<mi>U</mi>
</mrow>
<mn>235</mn>
</msubsup>
</mrow>
</mfrac>
</mrow>
<mrow>
<msubsup>
<mi>U</mi>
<mrow>
<mi>N</mi>
<mi>U</mi>
<mi>E</mi>
</mrow>
<mn>235</mn>
</msubsup>
<mo>=</mo>
<mi>a</mi>
<mo>+</mo>
<mi>b</mi>
<mo>*</mo>
<msubsup>
<mi>U</mi>
<mrow>
<mi>R</mi>
<mi>U</mi>
</mrow>
<mn>236</mn>
</msubsup>
<mo>+</mo>
<mi>c</mi>
<mo>*</mo>
<msubsup>
<mi>U</mi>
<mrow>
<mi>R</mi>
<mi>U</mi>
</mrow>
<mn>234</mn>
</msubsup>
</mrow>
In above formulaRespectively equivalent natural uranium 235, recovery uranium 236, recovery uranium 234,
Reclaim the weight percent content of uranium 235 and the uranium isotope in poor uranium 235;In formula, a=0.708, b=0.04395935
And c=0.1801096;
(3) according to step (2) ratio, precise recovery uranium and depleted uranium, then carry out physically be mixed to form it is equivalent
Natural uranium;
Described recovery uranium and depleted uranium carry out physically be mixed to form equivalent natural uranium, specially will with suction or other equipment
Material is added in dissolving tank or dissolving tank, and is dissolved with the nitric acid more than 3mol/L, stirs;
Or described recovery uranium and depleted uranium carry out physically be mixed to form equivalent natural uranium, specially with suction or other set
Standby material is added in single cone spiral or other mixing devices is premixed, and is then launched material and is arrived dissolving tank or dissolving tank
In, dissolved and stirred with the nitric acid more than 3mol/L;
(4) the equivalent natural uranium being mixed to form to step (3) is sampled analysis;
NUE and NU nuclear properties equivalence is analyzed, it requires the NUE that batch mixing calculation procedure is calculated and NU initial reactivity
Difference is less than the discharge burn-up of 5.71mk and NUE fuel within the ± 75MWd/tU of the discharge burn-up of natural uranium fuel;Or
What analysis obtained235U,234U and236U enrichment is within ± the 0.001% of NUE desired values;
If meeting above-mentioned requirements, step (5) is carried out;Above-mentioned requirements are not met such as, then add depleted uranium or recovery uranium regulation
In equivalent natural uranium235U weight percent content is until reach requirement;
(5) fuel making of the natural uranium for PHWR is replaced using equivalent natural uranium.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201511020274.8A CN105825904B (en) | 2015-12-30 | 2015-12-30 | A kind of presurized water reactor recovery uranium is applied to the method for PHWR |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201511020274.8A CN105825904B (en) | 2015-12-30 | 2015-12-30 | A kind of presurized water reactor recovery uranium is applied to the method for PHWR |
Publications (2)
Publication Number | Publication Date |
---|---|
CN105825904A CN105825904A (en) | 2016-08-03 |
CN105825904B true CN105825904B (en) | 2018-02-13 |
Family
ID=56514936
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN201511020274.8A Active CN105825904B (en) | 2015-12-30 | 2015-12-30 | A kind of presurized water reactor recovery uranium is applied to the method for PHWR |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN105825904B (en) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN109215824A (en) * | 2017-06-30 | 2019-01-15 | 孙福民 | The nuclear reaction device of nuke rubbish production capacity power generation can be used |
-
2015
- 2015-12-30 CN CN201511020274.8A patent/CN105825904B/en active Active
Also Published As
Publication number | Publication date |
---|---|
CN105825904A (en) | 2016-08-03 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
Coleman et al. | Evaluation of multiple, self-recycling of reprocessed uranium in LWR | |
CN110184464A (en) | A kind of extraction separating method of thorium | |
CN105825904B (en) | A kind of presurized water reactor recovery uranium is applied to the method for PHWR | |
CN109517992A (en) | A kind of separation method of trivalent actinium series and lanthanide series | |
Taylor et al. | Development of actinide separation processes for future nuclear fuel cycles in Europe. | |
EP3961653B1 (en) | Remix - fuel for a nuclear fuel cycle | |
US2856337A (en) | Method of operating nuclear reactors | |
CN104018013B (en) | A kind of method being prepared uranium plutonium co-precipitation feed liquid by solvent extraction | |
Settle | Uranium to electricity: The chemistry of the nuclear fuel cycle | |
CN114717430B (en) | Method for extracting molybdenum from uranium fission products and ionic liquid system | |
Chen et al. | Transmutation of Minor Actinides and Power Flattening in PWR MOX Fuel | |
Nayak et al. | Thorium technology development in an Indian perspective | |
Ban et al. | Reduction kinetics of Pu (IV) and Np (VI) by N, N-dimethylhydrazine, and its potential application in nuclear fuel reprocessing | |
CN105913887B (en) | It is a kind of to use formaldoxime to be stripped the plutonium purification cycle technique of reagent | |
RU2691621C1 (en) | Fuel composition for water-cooled thermal-neutron reactors | |
CN114561561B (en) | Method for recovering plutonium from plutonium-containing organic phase | |
CN112516795B (en) | System for precipitation separation of lithium isotopes | |
Haidon et al. | Modulation of tetravalent actinide oxalate morphology through organic compounds | |
Fan et al. | Study on the phase separation behavior of (U, Nd) 3 O 8 powder by high temperature oxidation | |
Shimokawa et al. | The Isotopic Exchange Reaction between U (IV) and U (VI) Ions in a Mixed System of Acidic Solution and Cation Exchange Resin,(I) Experimental Method and Exchange Reaction Rate | |
CN115572841A (en) | Extraction method for extracting Sr (II) from Sr (II) -containing solution | |
Kovalev et al. | A new approach to nuclear fuel recycling for LWR REMIX-fuel concept: Status and trends | |
Cota-Sanchez et al. | Separation of americium from aged plutonium dioxide | |
Cairns et al. | Solvent Extraction of Thorium and Uranium from Beryllium Nitrate Feeds by Tri-n-butyl Phosphate | |
Koopman et al. | SLUDGE BATCH 6 PHASE II FLOWSHEET SIMULATIONS |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
C06 | Publication | ||
PB01 | Publication | ||
C10 | Entry into substantive examination | ||
SE01 | Entry into force of request for substantive examination | ||
GR01 | Patent grant | ||
GR01 | Patent grant |