JPH067178B2 - Fuel control Autonomous safety fast breeder reactor - Google Patents
Fuel control Autonomous safety fast breeder reactorInfo
- Publication number
- JPH067178B2 JPH067178B2 JP62194057A JP19405787A JPH067178B2 JP H067178 B2 JPH067178 B2 JP H067178B2 JP 62194057 A JP62194057 A JP 62194057A JP 19405787 A JP19405787 A JP 19405787A JP H067178 B2 JPH067178 B2 JP H067178B2
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- tank
- loading
- shape memory
- memory alloy
- 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.)
- Expired - Fee Related
Links
- 239000000446 fuel Substances 0.000 title claims description 127
- 229910001285 shape-memory alloy Inorganic materials 0.000 claims description 26
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 24
- 239000002826 coolant Substances 0.000 claims description 11
- 229910001338 liquidmetal Inorganic materials 0.000 claims description 5
- 239000011261 inert gas Substances 0.000 claims description 3
- 230000005484 gravity Effects 0.000 claims description 2
- 238000007599 discharging Methods 0.000 claims 1
- 230000000149 penetrating effect Effects 0.000 claims 1
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 7
- 230000007423 decrease Effects 0.000 description 7
- 229910052708 sodium Inorganic materials 0.000 description 7
- 239000011734 sodium Substances 0.000 description 7
- 239000007788 liquid Substances 0.000 description 3
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 2
- 230000002159 abnormal effect Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 229910052778 Plutonium Inorganic materials 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- 230000005856 abnormality Effects 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- 229910052786 argon Inorganic materials 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 239000002828 fuel tank Substances 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】 〈産業上の利用分野〉 この発明は、一般的には液体金属冷却材を用いた高速増
殖炉に関し、さらに詳しくは、燃料装荷ひいては炉出力
を自律的に制御することができるとともに運転中燃料交
換が可能な新規な自律安全型高速増殖炉に関するもので
ある。Description: FIELD OF THE INVENTION This invention relates generally to fast breeder reactors using liquid metal coolant, and more particularly to autonomously controlling fuel loading and hence reactor power. The present invention relates to a novel autonomous safe fast breeder reactor capable of performing refueling during operation.
〈従来の技術および問題点〉 従来の高速増殖炉においては、燃料交換を行なう場合に
炉を停止しなくてはならないため、稼働率を高めるには
交換のための炉停止期間をできるだけ短縮する努力をし
なければならないが、燃料交換のための燃料交換器や燃
料出入機といった装置の設置は不可欠である。<Conventional technology and problems> In the conventional fast breeder reactor, it is necessary to stop the reactor when refueling.Therefore, in order to improve the operation rate, efforts are made to shorten the reactor shutdown period for replacement as much as possible. However, it is indispensable to install devices such as a fuel exchanger and a fuel inlet / outlet for refueling.
またその運転にあたっては炉外部からの人為的出力制御
を必要とし、さらには外部環境への放射性物質の放出を
防止するために、制御棒や原紙炉緊急停止系等の安全の
ための多大な設備を必要としている。In addition, its operation requires artificial output control from the outside of the furnace, and in order to prevent the release of radioactive substances to the external environment, a large amount of safety equipment such as control rods and emergency stop system In need.
その結果、炉全体の構造は大型となり、一度設置すれば
その設置場所から移動させることなど全く不可能であ
る。As a result, the structure of the entire furnace becomes large, and once installed, it is completely impossible to move it from its installation location.
そこでこの発明は、運転中燃料交換が可能でしかも自律
的に出力制御でき、従って燃料交換や出力制御を行なう
ために従来から必要であった設備を大幅に削減できるの
で炉全体の構造がコンパクトで簡略化でき、その結果可
搬型としうるため僻地や洋上等いかなる場所にも設置可
能な自律安全型高速増殖炉を提供することを目的として
なされたものである。In view of this, the present invention makes it possible to perform fuel exchange during operation and to autonomously control the output, and therefore to significantly reduce the equipment conventionally required to perform the fuel exchange and the output control. The purpose of the present invention is to provide an autonomous safe fast breeder reactor which can be installed in any place such as a remote area or offshore because it can be simplified and can be made portable.
〈問題点を解決するための手段〉 上記の目的を達成するためこの発明によれば、炉心タン
クを中心に、その上方に新燃料装荷タンクを積み重ね、
その下方に使用済燃料カートリッジタンクを着脱自在に
取付けたタンク積み重ね構造の高速増殖炉が提供され
る。炉心タンクは、液体金属冷却材の入口および出口を
有し、かつ複数の燃料支持管が垂直に貫通している。新
燃料装荷タンクは、炉心タンクの各燃料支持管と一直線
となるように整合する複数の燃料装荷孔が貫通してお
り、各燃料装荷孔内は不活性ガス雰囲気とするとともに
各燃料装荷孔の上端開口はシールプラグにより密封され
ている。使用済燃料カートリッジタンクは、炉心タンク
の各燃料支持管と一直線となるように整合する複数の有
底の使用済燃料収納孔が穿設されている。<Means for Solving Problems> In order to achieve the above object, according to the present invention, a new fuel loading tank is stacked above the core tank,
Provided is a fast breeder reactor having a tank stack structure in which a spent fuel cartridge tank is removably attached below it. The core tank has an inlet and an outlet for liquid metal coolant and has a plurality of fuel support tubes vertically extending therethrough. The new fuel loading tank has a plurality of fuel loading holes that are aligned with and aligned with the fuel support tubes of the core tank.The inside of each fuel loading hole is an inert gas atmosphere and the fuel loading holes The upper end opening is sealed by a seal plug. The spent fuel cartridge tank is provided with a plurality of bottomed spent fuel accommodating holes that are aligned with the respective fuel support tubes of the core tank.
炉心タンクの各燃料支持管の上端には、新燃料装荷タン
クの燃料装荷孔から燃料支持管内に燃料要素が自重落下
する速度を制御するために温度変化によりその開口度が
変化する上部形状記憶合金部材が配設されており、また
各燃料支持管の下端には、燃料支持管から使用済燃料カ
ートリッジタンクの使用済燃料収納孔内へ使用済燃料要
素が自重落下する速度を制御するために温度変化により
その開口度が変化する下部形状記憶合金部材が配設され
ている。At the upper end of each fuel support tube of the core tank, the upper shape memory alloy whose opening degree changes due to temperature change in order to control the speed at which the fuel element falls by gravity from the fuel loading hole of the new fuel loading tank into the fuel support tube A member is provided, and at the lower end of each fuel support pipe, a temperature is controlled in order to control the speed at which the spent fuel element falls by its own weight from the fuel support pipe into the spent fuel storage hole of the spent fuel cartridge tank. A lower shape memory alloy member whose opening degree changes according to the change is disposed.
〈作用〉 上述のごとき構成のこの発明の高速増殖炉によれば、定
格運転温度においては、上部形状記憶合金部材は一定の
落下速度で燃料要素を新燃料装荷タンクの燃料装荷孔か
ら炉心タンクの燃料支持管内へ装荷し、一方下部形状記
憶合金部材は同じく一定落下速度で燃料要素を炉心タン
クの燃料支持管から使用済燃料カートリッジタンクの使
用済燃料収納孔へ排出する。その結果定格出力が維持さ
れる。<Operation> According to the fast breeder reactor of the present invention configured as described above, at the rated operating temperature, the upper shape memory alloy member moves the fuel element from the fuel loading hole of the new fuel loading tank to the core tank at a constant drop velocity. The lower shape memory alloy member also discharges the fuel element from the fuel support tube of the core tank to the spent fuel storage hole of the spent fuel cartridge tank while the lower shape memory alloy member is also loaded into the fuel support tube. As a result, the rated output is maintained.
定格運転温度から上昇した時は、上部形状記憶合金部材
は開口度を縮小して燃料要素の燃料支持管への落下速度
を遅くし、一方下部形状記憶合金部材は開口度を拡大し
て燃料要素の使用済燃料収納孔への落下速度を速くし、
その結果、燃料支持管内の燃料要素の数が減少するた
め、炉心出力は低下し定格出力へ戻る。When the operating temperature rises above the rated operating temperature, the upper shape memory alloy member reduces the opening degree to slow down the falling speed of the fuel element into the fuel support tube, while the lower shape memory alloy member increases the opening degree to increase the fuel element. Increase the speed of falling into the spent fuel storage hole of
As a result, the number of fuel elements in the fuel support tube decreases, so the core power decreases and returns to the rated power.
定格運転温度から低下した時は、上部形状記憶合金部材
は開口度を拡大して燃料要素の落下速度を速くし、一方
下部形状記憶合金部材は開口度を縮小して燃料要素の落
下速度を遅くする結果、燃料支持管内の燃料要素数が増
加するため炉心出力は定格出力へ上昇する。When the operating temperature decreases from the rated operating temperature, the upper shape memory alloy member increases the opening degree to increase the falling speed of the fuel element, while the lower shape memory alloy member reduces the opening degree to decrease the falling speed of the fuel element. As a result, the number of fuel elements in the fuel support pipe increases, so the core power rises to the rated power.
また、温度が過度に上昇する異常時においては、上部形
状記憶合金部材の開口度は大幅に縮小して燃料要素の燃
料支持管への装荷は阻止され、下部形状記憶合金部材の
開口度は大幅に拡大されて燃料支持管内の燃料要素はそ
の大部分が使用済燃料収納孔へ落下,排出される結果、
炉心は未臨界となり出力は零となる。Further, in an abnormal case where the temperature rises excessively, the opening degree of the upper shape memory alloy member is significantly reduced, the loading of the fuel element on the fuel support pipe is blocked, and the opening degree of the lower shape memory alloy member is greatly increased. As a result, most of the fuel elements in the fuel support pipe are dropped into the spent fuel storage hole and discharged,
The core becomes subcritical and the power becomes zero.
このようにこの発明による高速増殖炉は炉出力を自律的
に制御できることにより、かくして燃料制御自律安全型
高速増殖炉と称することができる。As described above, the fast breeder reactor according to the present invention can autonomously control the reactor power, and thus can be referred to as a fuel control autonomous safety fast breeder reactor.
〈実施例〉 以下に図面に示す実施例を参照してこの発明をさらに説
明する。第1図はこの発明の高速増殖炉の一実施例を示
す説明図であって、炉心タンク10の上方に新燃料装荷
タンク20を積み重ね、下方に使用済燃料カートリッジ
タンク30が着脱自在に取付けられた全体として3つの
タンクの積み重ね構造となっている。<Examples> The present invention will be further described below with reference to the examples shown in the drawings. FIG. 1 is an explanatory view showing an embodiment of a fast breeder reactor of the present invention, in which a new fuel loading tank 20 is stacked above a core tank 10 and a spent fuel cartridge tank 30 is detachably attached below the core tank 10. In addition, it has a stacked structure of three tanks as a whole.
炉心タンク10は液体金属冷却材例えば液体ナトリウム
の入口11および出口12を有し、内部は液体ナトリウ
ム冷却材13で満たされており、さらに複数の燃料支持
管14が垂直に貫通している。燃料支持管14に装荷さ
れる燃料は、プルトニウムおよびウラン燃料を耐熱,耐
放射線性のステンレス合金等の円筒状または角柱状の被
覆管に封入した燃料要素15の形態とされ、これらの燃
料要素の複数個が燃料支持管14内に積み重ねられた燃
料配置で使用される。The core tank 10 has an inlet 11 and an outlet 12 for a liquid metal coolant, for example liquid sodium, the interior is filled with a liquid sodium coolant 13, and a plurality of fuel support tubes 14 penetrate vertically. The fuel loaded in the fuel support tube 14 is in the form of a fuel element 15 in which plutonium and uranium fuel are enclosed in a cylindrical or prismatic cladding tube of a heat-resistant, radiation-resistant stainless alloy or the like. A plurality of fuel stacks are used in the fuel arrangement stacked in the fuel support tube 14.
新燃料装荷タンク20には、複数の燃料装荷孔21が垂
直に貫通し、各孔の上端開口はシールプラグ(図示せ
ず)により密封されている。新燃料装荷タンク20が炉
心タンク10の上に積み重ねられたとき、各燃料装荷孔
21は燃料支持管14の各々と一直線に整合するように
なっているが、各燃料装荷孔21内はアルゴンガスのご
とき不活性ガス雰囲気とされているため、炉心タンク1
0内の液体ナトリウムが燃料装荷孔21を介して空気と
接触しないようにされている。各燃料装荷孔21内には
燃料装荷クレーン40から新たな燃料要素15が逐次装
荷され溜められている。A plurality of fuel loading holes 21 penetrate vertically through the new fuel loading tank 20, and an upper end opening of each hole is sealed by a seal plug (not shown). When the new fuel loading tank 20 is stacked on the core tank 10, each fuel loading hole 21 is aligned with each of the fuel support pipes 14, but the inside of each fuel loading hole 21 is filled with argon gas. Since the atmosphere is an inert gas atmosphere such as
The liquid sodium in 0 is prevented from coming into contact with air through the fuel loading hole 21. New fuel elements 15 are sequentially loaded and stored in the fuel loading holes 21 from the fuel loading crane 40.
使用済燃料カートリッジタンク30には、複数の有底の
使用済燃料収納孔31が穿設されている。このタンク3
0は炉心タンク10の下に着脱自在に取付けられるよう
になっており、着装されたときに各収納孔31は炉心タ
ンクの燃料支持管14の各々と一直線に整合する。The spent fuel cartridge tank 30 is provided with a plurality of bottomed spent fuel storage holes 31. This tank 3
No. 0 is detachably attached to the bottom of the core tank 10, and when it is mounted, each storage hole 31 is aligned with each of the fuel support pipes 14 of the core tank.
上述した燃料装荷孔21、燃料支持管14および使用済
燃料収納孔31はいずれも、燃料要素15が自重で落下
しうる直径を備えている。Each of the fuel loading hole 21, the fuel support pipe 14, and the spent fuel storage hole 31 described above has a diameter that allows the fuel element 15 to fall by its own weight.
炉心タンク10の各燃料支持管14の上端には上部形状
記憶合金部材Aが配設されている。この部材Aは炉心の
定格運転温度において約1週間で燃料要素1個を自重で
落下させて燃料装荷孔21から燃料支持管14内へ装荷
するように設定した開口度(燃料要素と部材Aとのギャ
ップ)を有し、温度が上昇するにつれてこの開口度が縮
小して燃料要素15の落下速度を送らせ、さらには落下
を阻止するようにされている。一方、各燃料支持管14
の下端には下部形状記憶合金部材Bが配設されている。
この部材Bは定格運転温度において約1週間で燃料要素
1個を自重で落下させて燃料支持管14から使用済燃料
収納孔31内へ排出するように設定された開口度を有
し、定格温度より10℃高くなると開口度を拡げて燃料
要素落下速度を速くし、さらに温度が上昇すると燃料要
素を直ちに落下させるようになっている。An upper shape memory alloy member A is arranged at the upper end of each fuel support pipe 14 of the core tank 10. This member A has an opening degree set so that one fuel element is dropped by its own weight and loaded into the fuel support tube 14 from the fuel loading hole 21 at the rated operating temperature of the core in about one week (fuel element and member A The opening degree of the fuel element 15 is reduced as the temperature rises so as to send the falling velocity of the fuel element 15 and prevent the fuel element 15 from falling. On the other hand, each fuel support tube 14
A lower shape memory alloy member B is disposed at the lower end of the.
This member B has an opening degree set so that one fuel element is dropped by its own weight and discharged from the fuel support pipe 14 into the spent fuel storage hole 31 at a rated operating temperature in about one week. When the temperature rises by 10 ° C., the opening degree is expanded to increase the fuel element falling speed, and when the temperature further rises, the fuel element is immediately dropped.
上述した構成を有するこの発明の高速増殖炉の動作を次
に説明する。炉の始動に際しては、炉内温度が低いため
上部形状記憶合金部材Aは全開となっており、新燃料装
荷タンク20から炉心タンク10の各燃料支持管14内
へ燃料要素15が落下するが、下部形状記憶合金部材B
は開口度が最小となっているため落下せず、各燃料支持
管14内に燃料要素スタックが形成され、燃料の核分裂
反応は臨界となって徐々に温度が上昇し始める。温度上
昇に伴い、上部形状記憶合金部材Aの開口度が次第に縮
小し、新燃料装荷タンク20からの燃料要素装荷は所定
の設定速度となり、一方、下部形状記憶合金部材Bの開
口度は次第に拡大して燃料支持管14から使用済燃料カ
ートリッジタンク30へ燃料要素は所定の設定速度で落
下するようになり、炉心は定格出力となる(第2図参
照)。なお、ナトリウム冷却材13は沸点が約900℃と
高く、500〜600℃の炉運転温度では大気圧であるため、
燃料要素15は新燃料装荷タンク20から炉心タンク1
0へ自重で落下できる。The operation of the fast breeder reactor of the present invention having the above-mentioned structure will be described below. At the time of starting the furnace, the upper shape memory alloy member A is fully opened because the temperature inside the furnace is low, and the fuel element 15 drops from the new fuel loading tank 20 into each fuel support pipe 14 of the core tank 10. Lower shape memory alloy member B
Has a minimum opening degree and does not drop, a fuel element stack is formed in each fuel support tube 14, the nuclear fission reaction of the fuel becomes critical, and the temperature gradually starts to rise. As the temperature rises, the opening degree of the upper shape memory alloy member A gradually decreases, and the fuel element loading from the new fuel loading tank 20 reaches a predetermined set speed, while the opening degree of the lower shape memory alloy member B gradually increases. Then, the fuel element falls from the fuel support pipe 14 to the spent fuel cartridge tank 30 at a predetermined set speed, and the core has a rated output (see FIG. 2). Since the sodium coolant 13 has a high boiling point of about 900 ° C and is at atmospheric pressure at a furnace operating temperature of 500 to 600 ° C,
The fuel element 15 is from the new fuel loading tank 20 to the core tank 1
It can fall to 0 by its own weight.
出力が定格状態より高くなり始めると、下部形状記憶合
金部材Bの開口度が拡大し燃料要素の落下速度が次第に
速くなり、炉心出力が低下して出力は定格状態にもど
る。When the output begins to become higher than the rated state, the opening degree of the lower shape memory alloy member B increases, the falling velocity of the fuel element gradually increases, the core output decreases, and the output returns to the rated state.
また、何らかの原因で炉心出力が過度に上昇したり、ナ
トリウム冷却材13流量が減少するような異常時におい
ては、ナトリウム温度は定格時より上昇し、上部形状記
憶合金部材Aは開口度が最大限に縮小して燃料15の装
荷を阻止する一方、下部形状記憶合金部材Bは開口度が
最大限に拡大して各燃料支持管14内の燃料要素15は
最上部1個(上部形状記憶合金部材Aに挾持されてい
る)を残して全て落下する。その結果、炉心は直ちに未
臨界となり、出力は零となる(第3図参照)。この発明
の高速増殖炉においては、余剰反応はほとんど零である
ため、異常時に炉心タンク燃料支持管14から数個の燃
料要素15を落下させるだけで未臨界となる。In addition, in an abnormal case where the core power excessively rises or the flow rate of the sodium coolant 13 decreases for some reason, the sodium temperature rises from the rated time, and the upper shape memory alloy member A has the maximum opening degree. To prevent the fuel 15 from being loaded, while the lower shape memory alloy member B has the maximum degree of opening and the fuel element 15 in each fuel support tube 14 has one uppermost fuel element (upper shape memory alloy member). All are dropped except for (held by A). As a result, the core immediately becomes subcritical and the power becomes zero (see Fig. 3). In the fast breeder reactor of the present invention, since the excess reaction is almost zero, it becomes subcritical simply by dropping a few fuel elements 15 from the core tank fuel support pipe 14 at the time of an abnormality.
なお、使用済燃料カートリッジタンク30の収納孔31
が炉心から落下してくる燃料要素により一杯になった
ら、炉運転中でもこのカートリッジタンク30を炉心タ
ンク10から取り外して新たな空のカートリッジタンク
30′(第1図)を炉心タンク10に装着することがで
きる。取り外したカートリッジタンク30は使用済燃料
再処理場へ運搬して再処理される。In addition, the storage hole 31 of the spent fuel cartridge tank 30
When the fuel tank is full of fuel elements falling from the core, remove this cartridge tank 30 from the core tank 10 and install a new empty cartridge tank 30 '(Fig. 1) into the core tank 10 even while the reactor is operating. You can The removed cartridge tank 30 is transported to the spent fuel reprocessing site and reprocessed.
〈発明の効果〉 この発明の高速増殖炉は上述したごとき構成を有してい
るため、次のような効果が得られる。<Effects of the Invention> Since the fast breeder reactor of the present invention has the configuration as described above, the following effects can be obtained.
(1)燃料要素は自重落下により炉心に装荷され、ナトリ
ウム冷却材温度により燃料要素落下速度が調節されるた
め炉出力は自律的に制御されることになり、安全性が高
い。(1) The fuel element is loaded into the core by its own weight drop, and the fuel element drop speed is adjusted by the sodium coolant temperature, so the reactor output is autonomously controlled, and the safety is high.
(2)従来必要であった制御棒や原子炉緊急停止系、さら
には燃料交換装置が不要となり、設備が大幅に削減でき
る。(2) The control rod, the reactor emergency stop system, and the fuel exchange device, which were required in the past, are not required, and the equipment can be significantly reduced.
(3)運転中燃料交換のため稼働率が向上する。(3) The operation rate is improved due to the refueling during operation.
(4)原子炉構成機器はタンクが主なため、構造が簡単で
製造・組立てが容易であり可搬型原子炉となる。そのた
め僻地や洋上などいかなる場所の設置も可能となる。(4) Since the reactor is mainly composed of tanks, it has a simple structure, is easy to manufacture and assemble, and is a portable reactor. Therefore, it can be installed in any place such as a remote area or offshore.
(5)運転中燃料交換を行なえること、および構造が簡単
で主要構成機器の信頼性が高いことから、メンテナンス
フリーで連続運転ができる。(5) Maintenance-free continuous operation is possible because the fuel can be exchanged during operation and the structure is simple and the main components are highly reliable.
第1図はこの発明の高速増殖炉の一実施例を概念的に説
明する断面図、第2図は炉運転時の燃料要素の配置を示
す説明図、第3図は異常時における燃料要素の配置を示
す説明図である。 10…炉心タンク、11…冷却材入口、12…冷却材出
口、13…液体金属冷却材、14…燃料支持管、15…
燃料要素、20…新燃料装荷タンク、21…燃料装荷
孔、30,30′…使用済燃料カートリッジタンク、3
1…使用済燃料収納孔、A…上部形状記憶合金部材、B
…下部形状記憶合金部材。FIG. 1 is a sectional view conceptually explaining an embodiment of the fast breeder reactor of the present invention, FIG. 2 is an explanatory view showing the arrangement of fuel elements during the operation of the reactor, and FIG. It is explanatory drawing which shows arrangement. 10 ... Core tank, 11 ... Coolant inlet, 12 ... Coolant outlet, 13 ... Liquid metal coolant, 14 ... Fuel support pipe, 15 ...
Fuel element, 20 ... New fuel loading tank, 21 ... Fuel loading hole, 30, 30 '... Spent fuel cartridge tank, 3
1 ... spent fuel storage hole, A ... upper shape memory alloy member, B
... Lower shape memory alloy member.
Claims (1)
つ複数の燃料支持管が垂直に貫通している炉心タンクの
上方に、該燃料支持管と一直線となるように整合する複
数の燃料装荷孔が貫通している新燃料装荷タンクを積み
重ね、該炉心タンクの下方に、該燃料支持管と一直線と
なるように整合する複数の有底の使用済燃料収納孔が穿
設されている使用済燃料カートリッジタンクを着脱自在
に取付けてなり、該炉心タンクの各燃料支持管の上端に
は、該新燃料装荷タンクの燃料装荷孔から該燃料支持管
内に燃料要素が自重落下する速度を制御するために温度
変化によりその開口度が変化する上部形状記憶合金部材
を配設し、該各燃料支持管の下端には、該燃料支持管か
ら該使用済燃料カートリッジタンクの使用済燃料収納孔
内へ使用済燃料要素が自重落下する速度を制御するため
に温度変化によりその開口度が変化する下部形状記憶合
金部材を配設し、該新燃料装荷タンクの燃料装荷孔内は
不活性ガス雰囲気とするとともに該燃料装荷孔の上端開
口はシールプラグにより密封してなり、これによって、
温度変化による上部および下部形状記憶合金部材の開口
度の変化によって炉心タンクの燃料支持管内燃料要素の
装荷および排出を調節することにより炉出力を自律的に
制御できるようにするとともに、運転中燃料交換を可能
にしたことを特徴とする燃料制御自律安全型高速増殖
炉。1. A plurality of fuels aligned in line with a fuel support tube above a core tank having a liquid metal coolant inlet and an outlet and having a plurality of fuel support tubes vertically extending therethrough. A stack of new fuel loading tanks having loading holes penetrating therethrough, and a plurality of bottomed spent fuel storage holes that are aligned below the core tank and are aligned with the fuel support tube A fresh fuel cartridge tank is removably attached to the upper end of each fuel support tube of the core tank to control the speed at which the fuel element falls by gravity from the fuel loading hole of the new fuel loading tank into the fuel support tube. For this purpose, an upper shape memory alloy member whose opening degree changes according to temperature changes is provided, and at the lower end of each fuel support pipe, from the fuel support pipe into the spent fuel storage hole of the spent fuel cartridge tank. Spent fuel required A lower shape memory alloy member whose opening degree changes according to temperature change is arranged to control the speed at which the fuel drops by its own weight, and an inert gas atmosphere is provided in the fuel loading hole of the new fuel loading tank and the fuel loading is performed. The top opening of the hole is sealed by a seal plug, which allows
The reactor power can be controlled autonomously by adjusting the loading and discharging of fuel elements in the fuel support tube of the core tank by changing the opening degree of the upper and lower shape memory alloy members due to temperature changes, and at the same time fuel exchange during operation A fuel control autonomous safe fast breeder reactor characterized by enabling the following.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62194057A JPH067178B2 (en) | 1987-08-03 | 1987-08-03 | Fuel control Autonomous safety fast breeder reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62194057A JPH067178B2 (en) | 1987-08-03 | 1987-08-03 | Fuel control Autonomous safety fast breeder reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6438692A JPS6438692A (en) | 1989-02-08 |
| JPH067178B2 true JPH067178B2 (en) | 1994-01-26 |
Family
ID=16318230
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62194057A Expired - Fee Related JPH067178B2 (en) | 1987-08-03 | 1987-08-03 | Fuel control Autonomous safety fast breeder reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH067178B2 (en) |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH0612183U (en) * | 1991-05-31 | 1994-02-15 | 小川ポンプ工業株式会社 | Fixing device for various devices |
| JP6008793B2 (en) * | 2013-05-21 | 2016-10-19 | 日立Geニュークリア・エナジー株式会社 | Radioactive substance fragment collection container, collection method, and collection device |
| CN112635083B (en) * | 2020-12-04 | 2024-05-10 | 中广核工程有限公司 | Molten salt reactor capable of online material changing and material changing method thereof |
-
1987
- 1987-08-03 JP JP62194057A patent/JPH067178B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6438692A (en) | 1989-02-08 |
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