KR102522445B1 - Nuclear fuel, fuel pellets containing the nuclear fuel, and fuel rods containing the fuel pellets - Google Patents
Nuclear fuel, fuel pellets containing the nuclear fuel, and fuel rods containing the fuel pellets Download PDFInfo
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- G—PHYSICS
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- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
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- G—PHYSICS
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- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/44—Fluid or fluent reactor fuel
- G21C3/56—Gaseous compositions; Suspensions in a gaseous carrier
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- G—PHYSICS
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- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
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- G21C3/045—Pellets
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- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/60—Metallic fuel; Intermetallic dispersions
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- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
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- G21C3/62—Ceramic fuel
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Abstract
핵 연료로서, 텔루라이드 우라늄 UTe2 및 게르마나이드 우라늄 UGe2를 함유하고, 우라늄은 4.99중량%이하의 우라늄 235U 동위원소의 농축도를 가지며, 텔루라이드 우라늄 UTe2는 최대 농축도가 5% 미만이고 1:9의 비율로 분말형 게르마나이드 우라늄 UGe2에 비례한다.As a nuclear fuel, it contains telluride uranium UTe 2 and germanide uranium UGe 2 , wherein uranium has an enrichment of uranium 235U isotope of less than 4.99% by weight, and telluride uranium UTe 2 has a maximum enrichment of less than 5% and 1 It is proportional to powdered germanide uranium UGe 2 at a ratio of 9:9.
Description
본 발명은 핵연료, 이 핵연료를 함유하는 연료 펠릿, 및 이들 연료 펠릿을 포함하는 연료봉에 관한 것이다.The present invention relates to nuclear fuel, fuel pellets containing the nuclear fuel, and fuel rods containing the fuel pellets.
중수 및 경수 원자로용 핵연료(또한 다른 유형에 대해 약간의 수정 포함 - 경수 냉각 흑연 감속, 흑연 감속된 CO2 냉각, 중수 냉각 및 감속, 고속 원자로)는 세라믹 펠릿 형태로 소결된 이산화우라늄UO2 로 제조된다. 이러한 펠릿에서는 원자로 운전 중에 핵분열 연쇄반응이 일어나서, 열이 방출되고 핵분열 및 활성화 생성물이 생성된다. 이러한 프로세스의 결과는 센티미터보다 작은 직경을 가진 펠릿 내의 중심과 가장자리 사이의 온도 구배가 약 800℃라는 점이며, 비정상적이거나 우발적인 공정의 경우에는 더욱 그렇다. 펠릿이 쌓이고 지르코늄 합금(또는 흑연으로 감속된 CO2 냉각된 또는 고속 원자로의 경우 강철)으로 만든 클래딩에 넣어진다. 생성된 막대는 불활성 헬륨 공기로 채워지고, 상단과 하단이 밀봉된다. 연료봉은 그 후 핵연료 집합체로 조립되어 노심에 삽입된다.Nuclear fuel for heavy and light water reactors (also with minor modifications for other types - light water cooled graphite moderation, graphite moderated CO 2 cooling, heavy water cooling and moderation, fast reactors) is made of uranium dioxide UO2 sintered in the form of ceramic pellets. do. In these pellets, a fission chain reaction takes place during reactor operation, releasing heat and producing fission and activation products. The result of this process is a center-to-edge temperature gradient of about 800°C in pellets with a diameter of less than a centimeter, especially in the case of unusual or accidental processes. The pellets are stacked and encased in a cladding made of a zirconium alloy (or steel in the case of graphite-moderated CO 2 cooled or fast reactors). The resulting rod is filled with inert helium air and sealed at the top and bottom. The fuel rods are then assembled into fuel assemblies and inserted into the core.
소결된 세라믹 이산화우라늄은 열전도율이 매우 낮아 경수 원자로의 핵연료 펠릿 내에 높은 방사상(radial) 온도 구배를 유발한다. 현재의 최신 기술은 높은 구배가 허용 가능한 것으로 간주된다. 그러나 이러한 구배로 인해 펠릿은 균열, 팽창, 부서지고, 방사선 손상에 대한 저항력이 떨어진다. 핵연료 클래딩이 손상된 경우, 1차 회로로 방사성 핵종이 방출될 가능성이 있다. 우발적인 상황 및 연료 온도의 급격한 상승의 경우, 주변 또는 연료 펠릿이 안전한 낮은 온도에 있더라도 연료의 중앙 부분이 UO2의 융점에 도달할 수 있다. 또 다른 문제는 연료 펠릿 내 온도 필드 함수의 적분에 비례하는 축적된 열이다. 냉각 손실 사고가 발생하면, 비정상적인 상황의 균형을 악화시키기 때문에 초기에 연료에서 이 열을 제거해야 한다.Sintered ceramic uranium dioxide has very low thermal conductivity, resulting in high radial temperature gradients within the fuel pellets of light water reactors. Current state of the art considers high gradients to be acceptable. However, these gradients make the pellets crack, swell, break, and become less resistant to radiation damage. If the fuel cladding is damaged, there is the potential for release of radionuclides into the primary circuit. In case of contingencies and sudden rises in fuel temperature, the central portion of the fuel may reach the melting point of UO 2 even if the surrounding or fuel pellets are at a safe low temperature. Another problem is the accumulated heat proportional to the integral of the temperature field function in the fuel pellet. In the event of a loss-of-cooling incident, this heat must be removed from the fuel initially, as it worsens the balance of the abnormal situation.
본 발명의 목적은 전술한 최신 기술의 단점을 제거하는 장치를 제공하는 것이다.It is an object of the present invention to provide a device which obviates the above mentioned disadvantages of the state of the art.
전술한 단점은 텔루라이드 우라늄(uranium telluride, UTe2)와 게르마나이드 우라늄(uranium germanide, UGe2)를 포함하는 핵연료에 의해 상당히 제거되며, 우라늄은 4.99중량% 이하의 우라늄 235U 동위원소 농축도를 가지며, 텔루라이드 우라늄 UTe2의 최대 농축도는 5% 미만이고 1:9의 비율로 분말형 게르마나이드 우라늄 UGe2에 비례한다.The aforementioned disadvantages are largely eliminated by nuclear fuel containing uranium telluride (UTe 2 ) and uranium germanide (UGe 2 ), which has a uranium 235U isotopic enrichment of less than 4.99% by weight. , the maximum enrichment of telluride uranium UTe2 is less than 5% and is proportional to powdered germanide uranium UGe2 in a ratio of 1:9.
전술한 단점들은 청구항에 따른 핵연료를 포함하는 연료 펠릿에 의해서도 상당히 제거된다.The aforementioned disadvantages are also largely eliminated by the fuel pellet comprising nuclear fuel according to the claims.
유리한 실시예에서, 원자로 운전 중에 핵연료의 전기량(electrical quantities)이 모니터링될 수 있게 하는 커넥터 및 전도체가 제공된다.In an advantageous embodiment, connectors and conductors are provided that allow electrical quantities of the nuclear fuel to be monitored during reactor operation.
다른 유리한 실시예에서, 그것은 최대 직경 1.5cm 및 최대 높이 2.5cm를 가진다.In another advantageous embodiment, it has a maximum diameter of 1.5 cm and a maximum height of 2.5 cm.
또 다른 유리한 실시예에서, 펠릿의 상부 및 하부 가장자리는 1mm 높이의 렌즈형 형상을 형성하도록 외측으로 연마된다.In another advantageous embodiment, the top and bottom edges of the pellet are polished outward to form a 1 mm high lenticular shape.
전술한 단점은 청구항 중 어느 한 항에 따른 연료 펠릿을 포함하는 연료봉에 의해서도 상당히 제거된다.The aforementioned disadvantages are also largely eliminated by a fuel rod comprising fuel pellets according to any one of the claims.
유리한 실시예에서, 전기적으로 부착된 전도체는 상부로부터의 제1 연료 펠릿 및 하부로부터의 제1 연료 펠릿 상에 배열되며, 이는 클래딩을 통해 전도되고 원자로 운전 중 연료 물질의 전기량 측정을 허용한다.In an advantageous embodiment, electrically attached conductors are arranged on the first fuel pellets from the top and the first fuel pellets from the bottom, which are conducted through the cladding and allow coulometric measurements of the fuel material during reactor operation.
본 발명에 따른 핵연료는 텔루라이드 우라늄 UTe2 및/또는 게르마나이드 우라늄 UGe2을 임의의 중량비로 함유하고, 사용된 우라늄은 최대 4.99 중량%의 우라늄 235U 동위원소 농축도를 갖는다.The nuclear fuel according to the present invention contains telluride uranium UTe 2 and/or germanide uranium UGe 2 in any weight ratio, and the uranium used has a uranium 235U isotopic enrichment of at most 4.99 weight percent.
예시적인 실시예에서, 분말형 표준 텔루라이드 우라늄 UTe2는 235U 중량의 5% 미만의 최대 농축도를 가지며 1:9의 중량비로 분말형 게르마나이드 우라늄UGe2와 혼합된다.In an exemplary embodiment, powdered standard telluride uranium UTe 2 is mixed with powdered germanide uranium UGe 2 in a weight ratio of 1:9 with a maximum concentration of less than 5% by weight of 235 U.
본 발명은 또한 소결; 추가로 연삭; 및 커넥터 및 전도체 제공에 의해 형성된 연료펠릿에 관한 것으로, 아래를 참조하라.The present invention also relates to sintering; additional grinding; and fuel pellets formed by providing connectors and conductors, see below.
연료 펠릿의 최대 직경은 1.5cm, 최대 높이는 2.5cm이다. 펠릿의 상하 가장자리는 운전 중 펠릿이 결속되지 않고 전기적, 열적 접촉을 보장하기 위해 펠릿의 중심에서 바깥쪽으로 1mm 높이로 렌즈 모양으로 연마된다. 운전 중 연료 물질의 전기량을 모니터링하기 위해 와이어가 펠릿에 부착된다.The maximum diameter of the fuel pellet is 1.5 cm and the maximum height is 2.5 cm. The upper and lower edges of the pellets are lenticularly polished at a height of 1 mm outward from the center of the pellets to ensure electrical and thermal contact without binding the pellets during operation. Wires are attached to the pellets to monitor the amount of electricity in the fuel material during operation.
따라서, 혁신적인 솔루션의 본질은 현재 사용되는 세라믹 재료 대신 상기 화합물 및 이들의 조합이 고유한 열기계적 특성을 가지며 중성자-물리적 특성이 핵연료에 적절하기 때문에, 사용된다는 사실에 기반을 둔다. 이러한 물질은 전기 및 열 전도성이 높기 때문에 핵연료의 온도 구배를 수백도까지 줄일 수 있다. 게르마늄 결합 반응도는 텔루륨 결합 반응도보다 약간 높으며, 계산에 따르면 세라믹 산화물 연료와 유사한 연료 캠페인(campaign)이 동위원소 우라늄(235U)과 동일한 농축도를 가진 제안된 연료로 달성할 수 있음을 보여준다.Thus, the essence of the innovative solution is based on the fact that these compounds and their combinations are used instead of currently used ceramic materials, since they have unique thermomechanical properties and their neutron-physical properties are suitable for nuclear fuel. Because these materials have high electrical and thermal conductivity, they can reduce the temperature gradient of nuclear fuel by hundreds of degrees. The germanium binding reactivity is slightly higher than the tellurium binding reactivity, and calculations show that a fuel campaign similar to ceramic oxide fuel can be achieved with the proposed fuel with the same enrichment as the isotopic uranium (235U).
새 연료는 우수한 열 및 전기 전도체이다. 휘어짐(연료가 활 모양으로 휘어짐)을 방지하기 위해, 핵연료 펠릿은 바람직하게는 펠릿의 중심에 닿도록 바깥쪽으로 렌즈 모양으로 연마된다. 계산에 따르면 개별 펠릿 사이의 상대적으로 집중적인 축 방향 열 전달이 이러한 방식으로 달성될 수 있다. 동시에, 펠릿 사이의 양호한 전기적 접촉이 보장된다.The new fuel is an excellent conductor of heat and electricity. To prevent bowing (bowing of the fuel), the fuel pellets are preferably lensed outward to reach the center of the pellet. Calculations have shown that relatively intensive axial heat transfer between the individual pellets can be achieved in this way. At the same time, good electrical contact between the pellets is ensured.
이러한 펠릿은 서로의 상단에 배치되고 기존의 지르코늄 합금 클래딩(또는 다른 표준 클래딩)으로 둘러싸여, 본 발명의 주제이기도 한 연료봉을 형성한다. 제안된 버전에서, 연료봉은 전기적으로 부착된 전도체가 위에서 제1 펠릿에 배치되고 아래에서 제1 펠릿에 배치되도록 배열된다. 전도체는 클래딩을 통과하여 원자로 출력, 국부 핵연료 연소, 국부 원자로 중성자속 밀도, 중성자 섭동 등에 따라 원자로 운전 중 연료 물질의 전기량을 측정할 수 있다. 이 독특한 핵연료 모니터링 방법은 새로운 UTe2 및 UGe2 물질의 특정 속성과 특정 제안 솔루션에 의해 가능하다.These pellets are placed on top of each other and surrounded by a conventional zirconium alloy cladding (or other standard cladding) to form the fuel rod, which is also the subject of the present invention. In the proposed version, the fuel rods are arranged such that electrically attached conductors are disposed on the first pellet from above and from below on the first pellet. Conductors can pass through the cladding to measure the amount of electricity in the fuel material during reactor operation according to reactor power, local fuel burning, local reactor neutron flux density, and neutron perturbation. This unique fuel monitoring method is enabled by the specific properties of the new UTe 2 and UGe 2 materials and specific proposed solutions.
Claims (7)
상기 핵 연료는 텔루라이드 우라늄 UTe2 및 게르마나이드 우라늄 UGe2를 함유하고, 우라늄은 4.99중량%이하의 우라늄 235U 동위원소의 농축도를 가지며, 텔루라이드 우라늄 UTe2는 최대 농축도가 5 중량% 미만이고 1:9의 비율로 분말형 게르마나이드 우라늄 UGe2에 비례하는 것인, 핵연료.As nuclear fuel,
The nuclear fuel contains telluride uranium UTe 2 and germanide uranium UGe 2 , wherein the uranium has an enrichment of the uranium 235U isotope of less than 4.99% by weight, and the telluride uranium UTe 2 has a maximum enrichment of less than 5% by weight; Nuclear fuel, proportional to powdered germanide uranium UGe 2 in a ratio of 1:9.
원자로 운전 중에 핵연료의 전기량이 모니터링될 수 있게 하는 커넥터 및 전도체가 제공되는, 연료 펠릿.According to claim 2,
A fuel pellet provided with connectors and conductors that allow the electrical quantity of the nuclear fuel to be monitored during reactor operation.
최대 직경이 1.5cm이고 최대 높이가 2.5cm인, 연료 펠릿.According to claim 2 or 3,
Fuel pellets with a maximum diameter of 1.5 cm and a maximum height of 2.5 cm.
상기 펠릿의 상부 및 하부 가장자리가 1mm 높이의 렌즈형 형상을 형성하도록 외측으로 연마되는 것인, 연료 펠릿.According to claim 2 or 3,
wherein the top and bottom edges of the pellet are polished outward to form a 1 mm high lenticular shape.
Applications Claiming Priority (3)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CZ2019800A CZ308689B6 (en) | 2019-12-27 | 2019-12-27 | Nuclear fuel, a fuel pellet containing this nuclear fuel, and a fuel rod containing these fuel pellets |
| CZPV2019-800 | 2019-12-27 | ||
| PCT/CZ2020/050100 WO2021129899A2 (en) | 2019-12-27 | 2020-12-23 | Nuclear fuel, a fuel pellet containing this nuclear fuel, and a fuel rod containing these fuel pellets |
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| Publication Number | Publication Date |
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| KR20220101213A KR20220101213A (en) | 2022-07-19 |
| KR102522445B1 true KR102522445B1 (en) | 2023-04-14 |
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| CZ (1) | CZ308689B6 (en) |
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| EP3364418B1 (en) * | 2017-02-21 | 2021-04-14 | Westinghouse Electric Sweden AB | A sintered nuclear fuel pellet, a fuel rod, a fuel assembly, and a method of manufacturing a sintered nuclear fuel pellet |
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| SE2250733A1 (en) | 2022-06-17 |
| WO2021129899A2 (en) | 2021-07-01 |
| WO2021129899A3 (en) | 2021-07-29 |
| CZ2019800A3 (en) | 2021-02-24 |
| SE545115C2 (en) | 2023-04-04 |
| CZ308689B6 (en) | 2021-02-24 |
| KR20220101213A (en) | 2022-07-19 |
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