CN109727696B - MOX pellet recycling method - Google Patents
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Abstract
Description
技术领域technical field
本发明属于回收再利用领域,具体涉及一种MOX芯块回收再利用方法。The invention belongs to the field of recovery and reuse, and in particular relates to a method for recovery and reuse of MOX pellets.
背景技术Background technique
MOX生坯压制以及芯块烧结过程中,由于物料流动性、物料物化性质、烧结工艺等参数不理想导致生产出一定量的不合格芯块,为提高产品合格率,需对不合格芯块进行回收再利用。During the MOX green body pressing and pellet sintering process, a certain amount of unqualified pellets are produced due to unsatisfactory parameters such as material fluidity, material physical and chemical properties, and sintering process. In order to improve the product qualification rate, unqualified pellets need to be processed Recycle.
目前,传统的核燃料制造领域对于不合格产品主要采用容器贮存的方式进行处理,存在有三点不足,一是不合格芯块的贮存导致铀钚物料利用率低;二是芯块贮存费用昂贵,变相导致芯块制造成本高昂;三是积聚的芯块对设备和人员均会造成辐照损害。为了解决这些问题,本专利设计了一种MOX芯块回收再利用方法,通过对芯块不合格原因梳理,采用针对性的处理方式,解决铀钚物料利用率不高、芯块大量积存的问题,实现不合格芯块的合理利用,提高了产品合格率。At present, in the field of traditional nuclear fuel manufacturing, unqualified products are mainly processed by container storage. There are three shortcomings. First, the storage of unqualified pellets leads to low utilization of uranium and plutonium materials; The manufacturing cost of pellets is high; the third is that the accumulated pellets will cause radiation damage to equipment and personnel. In order to solve these problems, this patent designs a method of recycling MOX pellets. By sorting out the reasons for unqualified pellets and adopting targeted treatment methods, the problems of low utilization rate of uranium and plutonium materials and large accumulation of pellets are solved. , Realize the reasonable utilization of unqualified pellets, and improve the qualified rate of products.
发明内容Contents of the invention
本发明的目的在于提供一种MOX芯块回收再利用处理方法,解决目前不合格芯块处理方式单一的难题,实现不合格芯块的合理利用。The purpose of the present invention is to provide a method for recycling and reusing MOX pellets, which solves the problem of a single processing method for unqualified pellets and realizes rational utilization of unqualified pellets.
本发明的技术方案如下:一种MOX芯块回收再利用方法,包括以下步骤:Technical scheme of the present invention is as follows: a kind of MOX pellet recycling method comprises the following steps:
步骤一:选用MOX燃料芯块,对其外观、尺寸、铀钚含量、杂质含量、O/M、密度数据进行分析检测;Step 1: Select MOX fuel pellets, analyze and test their appearance, size, uranium and plutonium content, impurity content, O/M, and density data;
步骤二:O/M不在1.90~1.99之间的的芯块,认为是不合格的芯块,将芯块装入石英烧结舟中,再将烧结舟装入烧结炉内;将炉内气压抽至0.01~5.00Pa之间,以0.1~15.0L/min速度通入Ar+%H2,选择0.1~10.0%H2含量的混合气体,气压保持在8~18KPa之间,如此往复操作1~10次,氧势为-800~-150KJ/mol,露点-50~0℃,H2O含量为10~1000ppm;将烧结炉内温度以0.1~10℃/min的速度升温,并在600~1500℃保温0.5~48h,气压保持在1~14KPa之间,气体流量控制速度在0.1~35L/min,氧势为-700~-250KJ/mo,露点-5~-60℃,H2O含量为10~1000ppm;Step 2: Pellets whose O/M is not between 1.90 and 1.99 are regarded as unqualified pellets. Put the pellets into the quartz sintering boat, and then put the sintering boat into the sintering furnace; pump the air pressure in the furnace To 0.01-5.00Pa, pass Ar+% H2 at a speed of 0.1-15.0L/min, select a mixed gas with a content of 0.1-10.0%H2, keep the air pressure between 8-18KPa, and do this reciprocatingly for 1-10 times , the oxygen potential is -800~-150KJ/mol, the dew point is -50~0℃, the H 2 O content is 10~1000ppm; the temperature in the sintering furnace is raised at a rate of 0.1~10℃/min, and the Keep warm for 0.5-48 hours, keep the air pressure between 1-14KPa, control the gas flow rate at 0.1-35L/min, oxygen potential -700-250KJ/mo, dew point -5-60°C, H 2 O content of 10 ~1000ppm;
步骤三:对于密度值小于91%TD的芯块,将芯块装入石英烧结舟中,再将烧结舟装入烧结炉内;将炉内气压抽至0.05~2.00Pa之间,以1~10L/min速度通入Ar+%H2,H2含量为1~15%,气压保持在5~16KPa之间,如此往复操作1~10次,氧势为-600~-150KJ/mol,露点-30~0℃,H2O含量为50~700ppm;将烧结炉内温度以0.1~3℃/min的速度升温,并在1200~1800℃保温0.5~12h,气压保持在2~22KPa之间,气体流量控制速度在0.5~10L/min,氧势为-600~-100KJ/mo,露点-10~-40℃,H2O含量为200~1200ppm;;Step 3: For pellets with a density value less than 91% TD, put the pellets into a quartz sintering boat, and then put the sintering boat into the sintering furnace; pump the air pressure in the furnace to between 0.05 and 2.00 Pa. 10L/min speed feeds Ar+%H 2 , the content of H 2 is 1-15%, the air pressure is kept between 5-16KPa, and this reciprocating operation is performed 1-10 times, the oxygen potential is -600--150KJ/mol, and the dew point is - 30~0℃, H 2 O content is 50~700ppm; the temperature in the sintering furnace is raised at a rate of 0.1~3℃/min, and kept at 1200~1800℃ for 0.5~12h, and the air pressure is kept between 2~22KPa. The gas flow control speed is 0.5~10L/min, the oxygen potential is -600~-100KJ/mo, the dew point is -10~-40℃, and the H 2 O content is 200~1200ppm;
步骤四:对于外径超过8.8mm的芯块,以5~20cm/min的速度送入磨削机中,以30~800rpm的转速度芯块进行磨削处理;Step 4: Send the pellets with an outer diameter exceeding 8.8mm into the grinding machine at a speed of 5-20cm/min, and grind the pellets at a speed of 30-800rpm;
步骤五:对于密度值高于97.3%TD、芯块高度在7.3mm以下,外径小于3.5mm、UO2含量低于56.4%,PuO2含量低于3.3%、杂质含量超过6550μg/g(U+Pu)的芯块,按照10~80%的装填率加入破碎机中,以10~1000rpm的破碎速度,在10~500N的压力下进行破碎处理10~2000min;当破碎后的颗粒粒径分布在2~200μm布区间、比表面积为0.1~10m2/g,后,按照20~400%装填率加入球磨罐中,按照1:1的比例加入直径为1~10mm的ZrO2磨球,以0.5~10L/h的速度通入N2,以1~30r/min的速度将物料预先混合均匀1~90min;然后以2~20L/h的速度通入N2,按照1~25r/min的速度逐渐增加球磨速度,以10~1000rpm的转速搅拌20~500min,处理结束后,以3~60r/min的速度逐渐减小搅拌速度直至停止;Step 5: For a density value higher than 97.3% TD, a pellet height of less than 7.3mm, an outer diameter of less than 3.5mm, a UO2 content of less than 56.4%, a PuO2 content of less than 3.3%, and an impurity content of more than 6550 μg/g (U +Pu) pellets, put them into the crusher according to the filling rate of 10-80%, and carry out the crushing treatment at the crushing speed of 10-1000rpm under the pressure of 10-500N for 10-2000min; when the crushed particle size distribution In the 2-200μm distribution area, the specific surface area is 0.1-10m 2 /g, after that, according to the filling rate of 20-400%, add ZrO2 grinding balls with a diameter of 1-10mm in the ratio of 1:1 to Feed in N 2 at a speed of 0.5-10L/h, pre-mix the materials uniformly at a speed of 1-30r/min for 1-90min; then feed N 2 at a speed of 2-20L/h, Gradually increase the speed of ball milling, and stir at a speed of 10-1000rpm for 20-500min. After the treatment, gradually reduce the stirring speed at a speed of 3-60r/min until it stops;
步骤六:对球磨细化获得的混合粉末分析铀钚含量、粒度、比表面、杂质含量进行分析,若混合粉末力度在0.3~1.2μm之间,比表面积为7.2~36.4㎡/g,均匀性在98.3~99.9之间,杂质含量小于1730μg/g,则为合格粉末。Step 6: Analyze the uranium and plutonium content, particle size, specific surface, and impurity content of the mixed powder obtained by ball milling. If the strength of the mixed powder is between 0.3 and 1.2 μm, the specific surface area is 7.2 to 36.4㎡/g, and the uniformity Between 98.3 and 99.9, if the impurity content is less than 1730μg/g, it is a qualified powder.
所述步骤二中,保温结束后,以2~40℃/min的速度降温至35~70℃,将芯块转运出烧结炉,检测O/M后贮存备用。In the second step, after the heat preservation is completed, the temperature is lowered to 35-70°C at a rate of 2-40°C/min, and the pellets are transported out of the sintering furnace, and stored for later use after O/M detection.
所述步骤三中,保温结束后,以0.1~10.0℃/min的速度降温至室温℃,将芯块转运出烧结炉,检测密度后贮存备用。In the third step, after the heat preservation is completed, the temperature is lowered to room temperature at a rate of 0.1-10.0°C/min, and the pellets are transported out of the sintering furnace, and stored for later use after the density is detected.
所述步骤五中,破碎介质为WC硬质合金,介质为球形,直径为1~30mm。In the fifth step, the crushing medium is WC hard alloy, the medium is spherical, and the diameter is 1-30 mm.
所述步骤六中,若各项参数不合格则返回相应步骤进行处理,直至分析结果合格,然后按照5~40%w.t.的比例与UO2、PuO2原料粉末混合,进行MOX芯块制备后续处理。In the step 6, if each parameter is unqualified, return to the corresponding step for processing until the analysis result is qualified, and then mix with UO 2 and PuO 2 raw material powder according to the ratio of 5-40%wt, and carry out the subsequent processing of MOX pellet preparation .
具体实施方式Detailed ways
一种MOX芯块回收再利用方法,包括以下步骤:A method for recycling MOX pellets, comprising the following steps:
步骤一:选用MOX燃料芯块,对其外观、尺寸、铀钚含量、杂质含量、O/M、密度数据进行分析检测。Step 1: Select MOX fuel pellets, analyze and test their appearance, size, uranium and plutonium content, impurity content, O/M, and density data.
步骤二:O/M不在1.90~1.99之间的的芯块,认为是不合格的芯块,将芯块装入石英烧结舟中,再将烧结舟装入烧结炉内;将炉内气压抽至0.01~5.00Pa之间,以0.1~15.0L/min速度通入Ar+%H2,选择0.1~10.0%H2含量的混合气体,气压保持在8~18KPa之间,如此往复操作1~10次,氧势为-800~-150KJ/mol,露点-50~0℃,H2O含量为10~1000ppm;将烧结炉内温度以0.1~10℃/min的速度升温,并在600~1500℃保温0.5~48h,气压保持在1~14KPa之间,气体流量控制速度在0.1~35L/min,氧势为-700~-250KJ/mo,露点-5~-60℃,H2O含量为10~1000ppm;保温结束后,以2~40℃/min的速度降温至35~70℃,将芯块转运出烧结炉,检测O/M后贮存备用;Step 2: Pellets whose O/M is not between 1.90 and 1.99 are regarded as unqualified pellets. Put the pellets into the quartz sintering boat, and then put the sintering boat into the sintering furnace; pump the air pressure in the furnace To 0.01-5.00Pa, pass Ar+% H2 at a speed of 0.1-15.0L/min, select a mixed gas with a content of 0.1-10.0%H2, keep the air pressure between 8-18KPa, and do this reciprocatingly for 1-10 times , the oxygen potential is -800~-150KJ/mol, the dew point is -50~0℃, the H 2 O content is 10~1000ppm; the temperature in the sintering furnace is raised at a rate of 0.1~10℃/min, and the Keep warm for 0.5-48 hours, keep the air pressure between 1-14KPa, control the gas flow rate at 0.1-35L/min, oxygen potential -700-250KJ/mo, dew point -5-60°C, H 2 O content of 10 ~1000ppm; after the heat preservation is over, cool down to 35-70°C at a rate of 2-40°C/min, transfer the pellets out of the sintering furnace, and store them for later use after detecting O/M;
步骤三:对于密度值小于91%TD的芯块,将芯块装入石英烧结舟中,再将烧结舟装入烧结炉内。将炉内气压抽至0.05~2.00Pa之间,以1~10L/min速度通入Ar+%H2,H2含量为1~15%,气压保持在5~16KPa之间,如此往复操作1~10次,氧势为-600~-150KJ/mol,露点-30~0℃,H2O含量为50~700ppm;将烧结炉内温度以0.1~3℃/min的速度升温,并在1200~1800℃保温0.5~12h,气压保持在2~22KPa之间,气体流量控制速度在0.5~10L/min,氧势为-600~-100KJ/mo,露点-10~-40℃,H2O含量为200~1200ppm。保温结束后,以0.1~10.0℃/min的速度降温至室温℃,将芯块转运出烧结炉,检测密度后贮存备用。Step 3: For pellets with a density value less than 91% TD, put the pellets into a quartz sintering boat, and then put the sintering boat into a sintering furnace. Pump the air pressure in the furnace to 0.05-2.00Pa, feed Ar+% H2 at a speed of 1-10L/min, the H2 content is 1-15%, and the air pressure is kept between 5-16KPa, and the reciprocating operation is 1-10KPa. 10 times, the oxygen potential is -600~-150KJ/mol, the dew point is -30~0℃, the H 2 O content is 50~700ppm; the temperature in the sintering furnace is raised at a rate of 0.1~3℃/min, and the Insulate at 1800°C for 0.5 to 12 hours, keep the air pressure between 2 and 22KPa, control the gas flow rate at 0.5 to 10L/min, oxygen potential at -600 to -100KJ/mo, dew point at -10 to -40°C, H 2 O content 200-1200ppm. After the heat preservation is over, cool down to room temperature at a rate of 0.1-10.0°C/min, transfer the pellets out of the sintering furnace, check the density and store them for later use.
步骤四:对于外径超过8.8mm的芯块,以5~20cm/min的速度送入磨削机中,以30~800rpm的转速度芯块进行磨削处理。Step 4: Send the pellets with an outer diameter exceeding 8.8 mm into the grinding machine at a speed of 5-20 cm/min, and grind the pellets at a rotational speed of 30-800 rpm.
步骤五:对于密度值高于97.3%TD、芯块高度在7.3mm以下,外径小于3.5mm、UO2含量低于56.4%,PuO2含量低于3.3%、杂质含量超过6550μg/g(U+Pu)的芯块,按照10~80%的装填率加入破碎机中,以10~1000rpm的破碎速度,在10~500N的压力下进行破碎处理10~2000min,破碎介质为WC硬质合金,介质为球形,直径为1~30mm;当破碎后的颗粒粒径分布在2~200μm布区间、比表面积为0.1~10m2/g,后,按照20~400%装填率加入球磨罐中,按照1:1的比例加入直径为1~10mm的ZrO2磨球,以0.5~10L/h的速度通入N2,以1~30r/min的速度将物料预先混合均匀1~90min;然后以2~20L/h的速度通入N2,按照1~25r/min的速度逐渐增加球磨速度,以10~1000rpm的转速搅拌20~500min,处理结束后,以3~60r/min的速度逐渐减小搅拌速度直至停止;Step 5: For a density value higher than 97.3% TD, a pellet height of less than 7.3mm, an outer diameter of less than 3.5mm, a UO2 content of less than 56.4%, a PuO2 content of less than 3.3%, and an impurity content of more than 6550 μg/g (U +Pu) pellets are added to the crusher at a filling rate of 10-80%, crushed at a crushing speed of 10-1000rpm, under a pressure of 10-500N for 10-2000min, and the crushing medium is WC cemented carbide. The medium is spherical, with a diameter of 1-30mm; when the particle size distribution of the crushed particles is in the distribution range of 2-200μm, and the specific surface area is 0.1-10m 2 /g, then they are added to the ball mill tank according to the filling rate of 20-400%. Add ZrO 2 grinding balls with a diameter of 1-10mm at a ratio of 1:1, feed N 2 at a speed of 0.5-10L/h, and pre-mix the materials uniformly at a speed of 1-30r/min for 1-90min; Feed N 2 at a speed of ~20L/h, gradually increase the ball milling speed at a speed of 1~25r/min, stir at a speed of 10~1000rpm for 20~500min, after the treatment is completed, gradually decrease at a speed of 3~60r/min stirring speed until it stops;
步骤六:对球磨细化获得的混合粉末分析铀钚含量、粒度、比表面、杂质含量进行分析,若混合粉末力度在0.3~1.2μm之间,比表面积为7.2~36.4㎡/g,均匀性在98.3~99.9之间,杂质含量小于1730μg/g,则为合格粉末;若各项参数不合格则返回相应步骤进行处理,直至分析结果合格,然后按照5~40%w.t.的比例与UO2、PuO2原料粉末混合,进行MOX芯块制备后续处理。Step 6: Analyze the uranium and plutonium content, particle size, specific surface, and impurity content of the mixed powder obtained by ball milling. If the strength of the mixed powder is between 0.3 and 1.2 μm, the specific surface area is 7.2 to 36.4㎡/g, and the uniformity Between 98.3 and 99.9, if the impurity content is less than 1730μg/g, it is a qualified powder; if the parameters are unqualified, return to the corresponding steps for processing until the analysis result is qualified, and then mix with UO 2 , PuO 2 raw material powders were mixed for subsequent processing of MOX pellet preparation.
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Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6479691A (en) * | 1987-09-22 | 1989-03-24 | Kobe Steel Ltd | Manufacture of mox fuel |
| US5882552A (en) * | 1997-06-27 | 1999-03-16 | Korea Atomic Energy Research Institute | Method for recycling fuel scrap into manufacture of nuclear fuel pellets |
| JP2912920B1 (en) * | 1998-07-30 | 1999-06-28 | 核燃料サイクル開発機構 | Pretreatment method for dissolving uranium-plutonium mixed oxide in nitric acid |
| JPH11242096A (en) * | 1998-02-25 | 1999-09-07 | Nuclear Fuel Ind Ltd | Method and apparatus for decontamination and recovery of tray for sintering nuclear fuel pellets |
| JPH11287890A (en) * | 1998-04-03 | 1999-10-19 | Hitachi Ltd | Reprocessing of spent nuclear fuel |
| EP1683162A2 (en) * | 2003-10-06 | 2006-07-26 | Commissariat A L'Energie Atomique | Method of producing pellets of a nuclear fuel based on mixed oxide (u,pu)o2 or (u,th)o2 |
| JP2007155380A (en) * | 2005-12-01 | 2007-06-21 | Global Nuclear Fuel-Japan Co Ltd | Device for recovering nuclear fuel uranium scrap |
| JP2011033504A (en) * | 2009-08-03 | 2011-02-17 | Japan Atomic Energy Agency | Manufacturing method of nuclear fuel pellet, and the nuclear fuel pellet |
| CN106782736A (en) * | 2017-01-12 | 2017-05-31 | 中国原子能科学研究院 | The Dry recovery technique of mox fuel pellet waste product |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US7070717B2 (en) * | 2002-03-11 | 2006-07-04 | Belgonucleaire Sa | MOX fuel fabrication process from weapon plutonium feed |
| KR101265258B1 (en) * | 2011-12-13 | 2013-05-16 | 한국수력원자력 주식회사 | The method for producing porous uo2 sintered pellet for electroreduction process using continuous process, and the porous uo2 sintered pellet thereby |
| KR101252110B1 (en) * | 2011-12-13 | 2013-04-12 | 한국수력원자력 주식회사 | The method for producing porous uo2 sintered pellet for electroreduction process using discontinuous process, and the porous uo2 sintered pellet thereby |
-
2017
- 2017-10-30 CN CN201711041149.4A patent/CN109727696B/en active Active
Patent Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6479691A (en) * | 1987-09-22 | 1989-03-24 | Kobe Steel Ltd | Manufacture of mox fuel |
| US5882552A (en) * | 1997-06-27 | 1999-03-16 | Korea Atomic Energy Research Institute | Method for recycling fuel scrap into manufacture of nuclear fuel pellets |
| JPH11242096A (en) * | 1998-02-25 | 1999-09-07 | Nuclear Fuel Ind Ltd | Method and apparatus for decontamination and recovery of tray for sintering nuclear fuel pellets |
| JPH11287890A (en) * | 1998-04-03 | 1999-10-19 | Hitachi Ltd | Reprocessing of spent nuclear fuel |
| JP2912920B1 (en) * | 1998-07-30 | 1999-06-28 | 核燃料サイクル開発機構 | Pretreatment method for dissolving uranium-plutonium mixed oxide in nitric acid |
| EP1683162A2 (en) * | 2003-10-06 | 2006-07-26 | Commissariat A L'Energie Atomique | Method of producing pellets of a nuclear fuel based on mixed oxide (u,pu)o2 or (u,th)o2 |
| JP2007155380A (en) * | 2005-12-01 | 2007-06-21 | Global Nuclear Fuel-Japan Co Ltd | Device for recovering nuclear fuel uranium scrap |
| JP2011033504A (en) * | 2009-08-03 | 2011-02-17 | Japan Atomic Energy Agency | Manufacturing method of nuclear fuel pellet, and the nuclear fuel pellet |
| CN106782736A (en) * | 2017-01-12 | 2017-05-31 | 中国原子能科学研究院 | The Dry recovery technique of mox fuel pellet waste product |
Non-Patent Citations (1)
| Title |
|---|
| 用电解精炼法回收和纯化铀和钚的研究Ⅰ.铀-锆合金芯块的直接溶解;叶玉星,高源;《核化学与放射化学》;19941120(第04期);第230-234页 * |
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