JPH02184791A - High conversion and high combustion pressure tube type nuclear reactor - Google Patents
High conversion and high combustion pressure tube type nuclear reactorInfo
- Publication number
- JPH02184791A JPH02184791A JP1004466A JP446689A JPH02184791A JP H02184791 A JPH02184791 A JP H02184791A JP 1004466 A JP1004466 A JP 1004466A JP 446689 A JP446689 A JP 446689A JP H02184791 A JPH02184791 A JP H02184791A
- Authority
- JP
- Japan
- Prior art keywords
- fuel assembly
- heavy water
- pressure tube
- fuel
- assembly
- 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.)
- Granted
Links
- 238000002485 combustion reaction Methods 0.000 title claims abstract description 11
- 238000006243 chemical reaction Methods 0.000 title claims description 17
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 claims abstract description 72
- 239000000446 fuel Substances 0.000 claims abstract description 51
- 239000011261 inert gas Substances 0.000 claims abstract description 13
- 230000000712 assembly Effects 0.000 claims abstract description 7
- 238000000429 assembly Methods 0.000 claims abstract description 7
- 239000002826 coolant Substances 0.000 claims description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract description 6
- 230000008878 coupling Effects 0.000 abstract 2
- 238000010168 coupling process Methods 0.000 abstract 2
- 238000005859 coupling reaction Methods 0.000 abstract 2
- 239000007789 gas Substances 0.000 description 4
- 230000000694 effects Effects 0.000 description 3
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 description 2
- 238000010521 absorption reaction Methods 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 238000010586 diagram Methods 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 229910052757 nitrogen Inorganic materials 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 238000001228 spectrum Methods 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 239000011800 void material Substances 0.000 description 1
Classifications
-
- 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
Abstract
Description
本発明は、核燃料の有効利用を図るために高転換と高燃
焼度を達成することができる重水減速圧力管型原子炉に
関するものである。The present invention relates to a heavy water-moderated pressure tube nuclear reactor that can achieve high conversion and high burnup in order to effectively utilize nuclear fuel.
多くの減速材の中で核的特性が最も優れている重水を減
速材として使用する重水減速原子炉において、冷却材が
重水以外の場合には、冷却材を減速材と隔離する必要性
等から、圧力管型重水炉の形態が採用されていることに
ついては、従来公知である。通常、圧力管型重水炉は、
内部に重水減速材と不活性ガスを収納するカランドリア
タンクと、該カランドリアタンクの縦方向に多数配設し
たカランドリア管と、該カランドリア管内を貫通して配
設され内部に重水減速材を流通させる圧力管と、該圧力
管内に挿入される燃料集合体とから成る炉本体を有して
いる。
上記した圧力管型重水炉で、中性子吸収反応によって作
り出す新しい核分裂性物質の高転換を図るには、中性子
エネルギースペクトルを硬くすること、具体的には格子
ピッチの縮小または重水減速材のボイド化が必要である
が、格子ピッチの縮小は圧力管据付を困難にし、重水減
速材のボイド化は全てボイドにすると臨界性の問題で難
しく、部分的なボイド化は炉心安定性の点で問題となる
。一方、核燃料の高燃焼度化を図るには、重水減速材を
多くすることが必要であるが、この場合は冷却材ボイド
係数が悪化し、安全上問題となる。このように高転換と
高燃焼度の両方を同時に達成しようとすると、炉心構成
上はそれぞれ異なったものとなるのである。そこで、こ
れまでは、炉心を内側のガス領域と外側の重水領域の二
つに分け、内側のガス領域で高転換した燃料集合体を外
側の重水領域で高燃焼するという方法が考えられていた
。In heavy water-moderated nuclear reactors that use heavy water as a moderator, which has the best nuclear properties among many moderators, if the coolant is other than heavy water, it is necessary to separate the coolant from the moderator. It is conventionally known that a pressure tube type heavy water reactor is employed. Usually, a pressure tube heavy water reactor is
A calandria tank that stores heavy water moderator and inert gas inside, a large number of calandria pipes arranged in the vertical direction of the calandria tank, and a heavy water moderator that passes through the calandria pipes and distributes the heavy water moderator inside. It has a furnace body consisting of a pressure pipe and a fuel assembly inserted into the pressure pipe. In order to achieve high conversion of the new fissile material produced by the neutron absorption reaction in the pressure tube type heavy water reactor described above, it is necessary to harden the neutron energy spectrum, specifically by reducing the lattice pitch or voiding the heavy water moderator. Although it is necessary, reducing the lattice pitch makes it difficult to install pressure pipes, voiding the heavy water moderator is difficult due to criticality issues if all the heavy water moderator is voided, and partial voiding poses a problem in terms of core stability. . On the other hand, in order to increase the burnup of nuclear fuel, it is necessary to increase the amount of heavy water moderator, but in this case, the coolant void coefficient deteriorates, which poses a safety problem. In this way, attempting to achieve both high conversion and high burnup at the same time requires different core configurations. So far, a method has been considered in which the reactor core is divided into two regions: an inner gas region and an outer heavy water region, and the fuel assemblies, which are highly converted in the inner gas region, are combusted at a high rate in the outer heavy water region. .
【発明が解決しようとする課題】
上記のように、炉心を内側のガス領域と外側の垂水領域
の二つに分けるには二重タンク構成としなければならな
いが1、炉心が占める範囲は拡大して耐圧容器を大形化
するから、構造上問題があった。また、中性子の不必要
な吸収や洩れをすくなくすることが重要な中性子経済上
も問題があった。
本発明の目的とするところは、前記した通常の圧力管型
重水炉の構造を変えることなく、燃料の有効利用が図れ
る高転換・高燃焼圧力管型原子炉を提供することにある
。[Problems to be Solved by the Invention] As mentioned above, in order to divide the reactor core into two, the inner gas region and the outer water region, a double tank configuration is required.1 However, the area occupied by the reactor core is expanded. This poses a structural problem as the pressure vessel is made larger. There was also a problem in terms of neutron economics, where it is important to minimize unnecessary absorption and leakage of neutrons. An object of the present invention is to provide a high conversion/high combustion pressure tube nuclear reactor that can utilize fuel effectively without changing the structure of the above-mentioned ordinary pressure tube heavy water reactor.
上記した目的を達成するため、本発明にあっては、圧力
管内に挿入される燃料集合体は上部燃料集合体と下部燃
料集合体とを接続部を介して軸方向に着脱自在に積み重
ねた構造となし、カランドリアタンク内の不活性ガス領
域と重水減速材領域とに配置して、高転換用領域と高燃
焼用領域とを上下に配設したものである。
各燃料集合体の上下端部には、他の燃料集合体を接続可
能とする接続部を形成しておくとよい。In order to achieve the above object, in the present invention, the fuel assembly inserted into the pressure pipe has a structure in which an upper fuel assembly and a lower fuel assembly are stacked in the axial direction via a connecting part so as to be detachable. The calandria tank is arranged in an inert gas region and a heavy water moderator region, and a high conversion region and a high combustion region are arranged above and below. It is preferable to form connection parts at the upper and lower ends of each fuel assembly to which other fuel assemblies can be connected.
重水がない不活性ガス領域に配設されている上部燃料集
合体はエネルギーの高い中性子により高転換され、重水
領域に配設されている下部燃料集合体はエネルギーの低
い中性子により高燃焼する。カランドリアタンク内の重
水減速材の水位を変えることで、上下に配設される高転
換用領域と高燃焼用領域との比率が可変である。
この炉心上部の不活性ガス領域で高転換された上部燃料
集合体を、つぎに下部燃料集合体の配設位置に組替えて
再度装荷すると、炉心下部の重水領域で高燃焼されるか
ら、高転換・高燃焼度を達成することができる。The upper fuel assembly disposed in the inert gas region where there is no heavy water is highly converted by high-energy neutrons, and the lower fuel assembly disposed in the heavy water region is highly combusted by low-energy neutrons. By changing the water level of the heavy water moderator in the calandria tank, the ratio of the high conversion region and the high combustion region arranged above and below can be varied. When the upper fuel assembly, which has been highly converted in the inert gas area at the top of the core, is then reassembled to the lower fuel assembly position and loaded again, it is burned at a high rate in the heavy water area at the bottom of the core, resulting in a high conversion rate.・High burnup can be achieved.
図面に示す実施例において、周囲を重水反射体2で取り
囲んでいるカランドリアタンク1内は、重水減速材領域
5と、ヘリウム、窒素等不活性ガス領域6となっている
。そのカランドリアタンク1の縦方向に貫通して設けた
多数のカランドリア管3に挿入されている圧力管4に燃
料集合体7が配置され、炉心下部の入口管8より圧力管
4内に流入した冷却材は、炉心内で沸騰して、出口管9
より流出するようになっている。
原子炉の下方に設備されている燃料交換装置および運転
中でも燃料交換を行い得るようにするための圧力管4下
端部に装着されているシールプラグは、図示するを省略
している。
圧力管4内の燃料集合体7は、上部燃料集合体7aと下
部燃料集合体7bが連結部10を介して2段に積み重ね
られている。連結部10は後述する理由から各燃料集合
体7 a s 7 bの上下端部に形成しているとよい
。図にはカランドリアタンク1内の重水減速材領域5と
不活性ガス領域6との境界、つまりカランドリアタンク
1内の重水減速材の水位とほぼ合致させて連結部10を
配設しているが、重水減速材の水位は適宜変えることが
でる。これによってガス領域6中にあって高変換作用を
受ける上部燃料集合体7a部分と、重水減速材領域5中
にあって高燃焼作用を受ける下部燃料集合体7b部分の
比率を適宜変えられる。
連結部10が各燃料集合体7a、7bの上下端部に形成
していると、原子炉運転中または原子炉停止時に燃料交
換装置により燃料交換を行うに際し、下部燃料集合体7
bを取り出して使用済み燃料プール(図示せず)に置き
、次に高転換した上部燃料集合体7bを取り出して、そ
の上に新しい燃料集合体を装着したのち炉心内に再装荷
し、このように組替えられて下になった上部燃料集合体
7aを今度は高燃焼させることができる。
尚、主として高転換を図るときには、炉心上部の上部燃
料集合体7aを下になるように組替える必要はない。そ
の侭取り出して、これを再処理することにより高転換し
たPuを得、このPuを他炉型の燃料として供給する。In the embodiment shown in the drawings, a calandria tank 1 surrounded by a heavy water reflector 2 has a heavy water moderator region 5 and an inert gas region 6 such as helium or nitrogen. A fuel assembly 7 is arranged in a pressure pipe 4 inserted into a large number of calandria pipes 3 provided vertically through the calandria tank 1, and fuel flows into the pressure pipe 4 from an inlet pipe 8 at the bottom of the reactor core. The coolant boils in the reactor core and exits the outlet pipe 9.
It's starting to leak more. A fuel exchange device installed below the reactor and a seal plug attached to the lower end of the pressure pipe 4 to enable fuel exchange even during operation are not shown. The fuel assemblies 7 in the pressure pipe 4 are stacked in two stages, including an upper fuel assembly 7a and a lower fuel assembly 7b via a connecting portion 10. The connecting portions 10 are preferably formed at the upper and lower ends of each fuel assembly 7 a s 7 b for reasons described later. In the figure, the connecting portion 10 is arranged at the boundary between the heavy water moderator region 5 and the inert gas region 6 in the calandria tank 1, that is, at almost the same level as the water level of the heavy water moderator in the calandria tank 1. However, the water level of the heavy water moderator can be changed as appropriate. As a result, the ratio of the portion of the upper fuel assembly 7a located in the gas region 6 and subjected to a high conversion action to the portion of the lower fuel assembly 7b located in the heavy water moderator region 5 and subjected to a high combustion action can be changed as appropriate. If the connecting portions 10 are formed at the upper and lower ends of each of the fuel assemblies 7a and 7b, the lower fuel assemblies 7
b is taken out and placed in a spent fuel pool (not shown), then the highly converted upper fuel assembly 7b is taken out, a new fuel assembly is installed on top of it, and then reloaded into the reactor core. The upper fuel assembly 7a, which has been rearranged into the lower part, can now be highly combusted. Incidentally, when mainly aiming at high conversion, there is no need to rearrange the upper fuel assembly 7a in the upper part of the core so that it is facing downward. By extracting the residual material and reprocessing it, highly converted Pu is obtained, and this Pu is supplied as fuel for other reactor types.
本発明によれば、高転換用領域と高燃焼用領域とを上下
に配設したから、原子炉構造は従来と変わりのないもの
でよく、炉心を二重タンク構成とするときの構造上の問
題や中性子経済上の問題は解消される。しかも、カラン
ドリアタンク内の重水減速材の水位の調節により、不活
性ガス領域に配設されて高転換作用を受ける上部燃料集
合体部分と、重水領域に配設されて高燃焼作用を受ける
下部燃料集合体部分の比率を適宜変更可能である。更に
炉心上部の不活性ガス領域で高転換を図った上部燃料集
合体を組替えによって炉心下部の重水領域に配設できる
から、高燃焼度を達成でき、こうして高転換・高燃焼度
を図ることができる。According to the present invention, since the high conversion region and the high combustion region are arranged above and below, the reactor structure can be the same as the conventional one. Problems and neutron economic problems will be eliminated. Moreover, by adjusting the water level of the heavy water moderator in the calandria tank, the upper fuel assembly part is placed in the inert gas area and receives a high conversion effect, and the lower part is placed in the heavy water area and receives a high combustion effect. The ratio of the fuel assembly portions can be changed as appropriate. Furthermore, the upper fuel assembly, which has achieved high conversion in the inert gas region at the top of the core, can be rearranged and placed in the heavy water region at the bottom of the core, making it possible to achieve high burnup. can.
図は本発明になる高転換高燃焼圧力管型原子炉の説明図
である。
1・・・カランドリアタンク、3・・・カランドリア管
、4・・・圧力管、5・・・重水減速材領域、6・・・
不活性ガス領域、7・・・燃料集合体、7a・・・上部
燃料集合体、7b・・・下部燃料集合体、10・・・接
続部。The figure is an explanatory diagram of a high conversion, high combustion pressure tube reactor according to the present invention. DESCRIPTION OF SYMBOLS 1... Calandria tank, 3... Calandria pipe, 4... Pressure pipe, 5... Heavy water moderator area, 6...
Inert gas region, 7... Fuel assembly, 7a... Upper fuel assembly, 7b... Lower fuel assembly, 10... Connection portion.
Claims (1)
リアタンクと、該カランドリアタンクの縦方向に多数配
設したカランドリア管と、該カランドリア管内を貫通し
て配設され内部に冷却材を流通させる圧力管と、該圧力
管内に挿入される燃料集合体とから成る炉本体を有して
いる圧力管型原子炉において、圧力管内に挿入される燃
料集合体は、上部燃料集合体と下部燃料集合体とを接続
部を介して軸方向に着脱自在に積み重ねた構造となし、
その上部燃料集合体と下部燃料集合体とはカランドリア
タンク内の不活性ガス領域と重水減速材領域とに配置し
て、高転換用領域と高燃焼用領域とを上下に配設したこ
とを特徴とする高転換高燃焼圧力管型原子炉。 2、各燃料集合体の上下端部には、他の燃料集合体を接
続可能とする接続部を形成している請求項1の高転換高
燃焼重水減速型圧力管型原子炉。[Claims] 1. A calandria tank that stores a heavy water moderator and an inert gas inside, a large number of calandria tubes arranged in the longitudinal direction of the calandria tank, and a calandria tube arranged to penetrate inside the calandria tubes. In a pressure tube nuclear reactor, the reactor body is composed of a pressure tube through which coolant flows, and a fuel assembly inserted into the pressure tube.The fuel assembly inserted into the pressure tube is The upper fuel assembly and the lower fuel assembly are stacked in the axial direction via a connecting part so that they can be attached and detached freely,
The upper fuel assembly and the lower fuel assembly are arranged in the inert gas region and heavy water moderator region in the calandria tank, and the high conversion region and the high combustion region are arranged above and below. A high-conversion, high-combustion-pressure tube nuclear reactor. 2. The high conversion, high combustion, heavy water moderated pressure tube nuclear reactor according to claim 1, wherein the upper and lower ends of each fuel assembly are formed with connecting portions to which other fuel assemblies can be connected.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP1004466A JPH0718940B2 (en) | 1989-01-11 | 1989-01-11 | High conversion high combustion pressure tube reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP1004466A JPH0718940B2 (en) | 1989-01-11 | 1989-01-11 | High conversion high combustion pressure tube reactor |
Publications (2)
Publication Number | Publication Date |
---|---|
JPH02184791A true JPH02184791A (en) | 1990-07-19 |
JPH0718940B2 JPH0718940B2 (en) | 1995-03-06 |
Family
ID=11584906
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP1004466A Expired - Fee Related JPH0718940B2 (en) | 1989-01-11 | 1989-01-11 | High conversion high combustion pressure tube reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH0718940B2 (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN102097138A (en) * | 2010-10-29 | 2011-06-15 | 中国原子能科学研究院 | Heavy water tank |
-
1989
- 1989-01-11 JP JP1004466A patent/JPH0718940B2/en not_active Expired - Fee Related
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN102097138A (en) * | 2010-10-29 | 2011-06-15 | 中国原子能科学研究院 | Heavy water tank |
Also Published As
Publication number | Publication date |
---|---|
JPH0718940B2 (en) | 1995-03-06 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
LAPS | Cancellation because of no payment of annual fees |