JPH02206794A - Liquid-metal cooled fast reactor - Google Patents
Liquid-metal cooled fast reactorInfo
- Publication number
- JPH02206794A JPH02206794A JP1028423A JP2842389A JPH02206794A JP H02206794 A JPH02206794 A JP H02206794A JP 1028423 A JP1028423 A JP 1028423A JP 2842389 A JP2842389 A JP 2842389A JP H02206794 A JPH02206794 A JP H02206794A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- reflector
- core
- cooled fast
- output unit
- 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
- 229910001338 liquidmetal Inorganic materials 0.000 title claims abstract description 27
- 239000002826 coolant Substances 0.000 claims abstract description 38
- 230000017525 heat dissipation Effects 0.000 claims description 8
- 238000001816 cooling Methods 0.000 claims description 7
- 230000002093 peripheral effect Effects 0.000 claims 1
- 239000000446 fuel Substances 0.000 abstract description 6
- 239000000463 material Substances 0.000 description 7
- 230000009257 reactivity Effects 0.000 description 6
- 238000010521 absorption reaction Methods 0.000 description 3
- 230000007423 decrease Effects 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 3
- 239000012530 fluid Substances 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- 230000005855 radiation Effects 0.000 description 3
- 239000002184 metal Substances 0.000 description 2
- 229910052751 metal Inorganic materials 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 238000010248 power generation Methods 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 230000005251 gamma ray Effects 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 239000011261 inert gas Substances 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 230000000149 penetrating effect Effects 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
- 238000005096 rolling process Methods 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
- G21C1/03—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a coolant not essentially pressurised, e.g. pool-type reactors
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/30—Control of nuclear reaction by displacement of the reactor fuel or fuel elements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
この発明は、熱供給プラント及び発電プラントのいずれ
のプラントにも利用できる超小型固有安全炉を実現する
ための液体金属冷却高速炉構造の簡略化技術に関する。The present invention relates to a technology for simplifying the structure of a liquid metal cooled fast reactor for realizing an ultra-small inherently safe reactor that can be used in both heat supply plants and power generation plants.
従来の大型発電プラント等に採用されている液体金属冷
却高速炉は、原子炉容器内に向けて制御棒駆動機構や燃
料交換装置が設けられ、また、原子炉・容器の外部に熱
交換機や原子炉容器内の冷却材の循環を行なう１次冷却
循環ポンプが配管により接続された構造となっている。
現在の液体金属冷却高速炉よりも出力規模の数段小さい
超小型炉は、各国で検討されているが、小型化に伴って
発電単価が割高となる欠点があり、実用化には至ってい
ない。Liquid metal cooled fast reactors, which are used in conventional large-scale power plants, are equipped with a control rod drive mechanism and fuel exchange device inside the reactor vessel, and a heat exchanger and nuclear reactor installed outside the reactor vessel. A primary cooling circulation pump that circulates the coolant inside the furnace vessel is connected by piping. Ultra-small reactors, which have an output scale that is several orders of magnitude smaller than current liquid metal-cooled fast reactors, are being considered in many countries, but they have not been put into practical use because the unit cost of power generation is relatively high due to miniaturization.
【発明が解決しようとする課題】
上記従来の液体金属冷却高速増殖炉のシステムをそのま
ま小型化した場合、システムが複雑となり経済性が著し
く劣ったものとなる。
従って、この発明は、固有の安全性を維持しながら超小
型炉を実現する上で必要な液体金属冷却高速炉の構造並
びに運転制御技術及び運転制御システムの簡略化を行な
うことを目的とする。[Problems to be Solved by the Invention] If the conventional liquid metal cooled fast breeder reactor system described above is miniaturized as it is, the system will become complicated and the economical efficiency will be significantly lower. Therefore, it is an object of the present invention to simplify the structure, operation control technology, and operation control system of a liquid metal cooled fast reactor necessary to realize a micro reactor while maintaining inherent safety.
上記目的を達成するためのこの発明の液体金属冷却高速
炉は、原子炉容器内に環状の径方向反射体が冷却材中に
配置されて固定されていると共に、前記径方向反射体の
環内を貫通可能な炉心及び該炉心を挟んで接合する軸方
向に冷却材流路を形成した上下２つの軸方向反射体と、
上部軸方向反射体の上端に下端が接続され、両端間の所
定位置の周面に冷却材流通孔を開けた構造の出力ユニッ
ト管であって、前記径方向反射体の環内に前記炉心に上
端を固定した下部軸方向反射体の下端を挿入しても上端
が前記原子炉容器外に突出する長さの出力ユニット管と
を有することを特徴上する。A liquid metal cooled fast reactor of the present invention for achieving the above object includes an annular radial reflector disposed in a coolant and fixed in a reactor vessel, and a ring-shaped radial reflector within the ring of the radial reflector. a reactor core capable of penetrating the reactor core; and two upper and lower axial reflectors having coolant flow passages formed in the axial direction and joined to sandwich the reactor core;
An output unit tube having a structure in which a lower end is connected to an upper end of an upper axial reflector, and a coolant flow hole is formed in a circumferential surface at a predetermined position between both ends, the output unit tube having a structure in which a coolant flow hole is formed in a circumferential surface at a predetermined position between the two ends, and the output unit tube is connected to the reactor core within a ring of the radial reflector. The output unit tube has a length such that the upper end thereof protrudes outside the reactor vessel even when the lower end of the lower axial reflector whose upper end is fixed is inserted.
上記構成のこの発明の液体金属冷却高速炉においては、
径方向反射体の環内に挿入した炉心の配置位置により、
炉心がこれを挟んで接合する上下２つの軸方向反射体と
環状の径方向反射体によって囲まれる囲まれ具合が変り
、この囲まれ具合に応じて炉心から出力される熱エネル
ギー量が変り、炉の出力は臨界一定格出力−最大出力一
定格出力一部分出カースクラムと順次変化する。
冷却材は、自然対流又は取付けられた循環ポンプにより
、通常、軸方向反射体に形成された軸方向の冷却材流路
及び炉心の隙間を通って原子炉容器内の底から上に向か
って流れ、出力ユニット管の冷却材流通孔を通って原子
力容器内又は循環ポンプが原子力容器の外側に設けられ
た場合の原子力容器、循環ポンプ、及び両者を接続する
配管によって形成された１次冷却系ループを循環する。
炉心の反応度は、上述した炉の出力に対応する炉心の径
方向反射体に対する配置位置及び炉心温度によって変り
、炉心温度が高くなるに従って抑制され、炉の出力を減
少させる性質を有する。従って、炉心の隙間を通って流
れる冷却材の温度が高くなったり、炉心流量を減少した
場合には、−次的に炉心温度が高くなるが、これにより
炉心の反応度が抑制されて炉心温度が元に戻り、冷却材
の吸熱容量、即ち、炉の出力が減少する。冷却材の温度
が低くなったり、炉心流量を減少した場合にはこの逆で
ある。
加えて、冷却材の温度が高くなった場合には出力ユニッ
ト管等が熱膨張し、原子炉運転中の出力ユニット管の上
端は固定されているので炉心は原子炉容器の底に向かっ
て移動する。他方、径方向反射体は原子炉容器に固定さ
れているので熱膨張により上方に移動し、炉心は径方向
反射体の環内に相対的に深く挿入される。従って両者の
相対的移動により炉心の反応度はやや低下する。In the liquid metal cooled fast reactor of the present invention having the above configuration,
Depending on the position of the core inserted within the ring of the radial reflector,
The extent to which the reactor core is surrounded by the two upper and lower axial reflectors and the annular radial reflector that are joined to each other changes, and the amount of thermal energy output from the core changes depending on this surrounding condition. The output changes sequentially as critical - rated output - maximum output - rated output - partial output Kerr scram. Coolant flows from the bottom up within the reactor vessel, typically through axial coolant channels formed in the axial reflector and through gaps in the core, either by natural convection or by installed circulation pumps. , the primary cooling system loop formed by the nuclear vessel, the circulation pump, and the piping connecting the two when the circulation pump is installed inside the nuclear vessel or outside the nuclear vessel through the coolant distribution hole of the output unit pipe. cycle. The reactivity of the reactor core varies depending on the position of the reactor core with respect to the radial reflector corresponding to the above-described reactor output and the core temperature, and has the property of being suppressed as the core temperature increases, reducing the reactor output. Therefore, if the temperature of the coolant flowing through the core gap increases or the core flow rate is reduced, the core temperature will increase, but this will suppress the core reactivity and reduce the core temperature. returns to normal, and the heat absorption capacity of the coolant, ie, the output of the furnace, decreases. The opposite is true if the coolant temperature is lowered or the core flow rate is reduced. In addition, when the temperature of the coolant increases, the output unit tubes, etc. will thermally expand, and since the upper end of the output unit tubes is fixed during reactor operation, the reactor core will move toward the bottom of the reactor vessel. do. On the other hand, since the radial reflector is fixed to the reactor vessel, it moves upward due to thermal expansion, and the core is inserted relatively deeply into the annulus of the radial reflector. Therefore, the reactivity of the core decreases slightly due to the relative movement of the two.
以下に実施例を示し、この発明を更に具体的に説明する
。
第１図にこの発明の液体金属冷却高速炉の１例を示す。
この液体金属冷却高速炉は、原子炉容器１及び出力ユニ
ット２を含んで構成されている。
この内の原子炉容器１内には溶融金属、例えばＮａ又は
ＮｆｉＫから成る冷却材３が収容されている。また、こ
の原子炉容器１内の近底部に環状の径方向反射体４が支
持体５を介して固定されている。この支持体５は径方向
反射体４の環と同一内径の環状支持板５ａと開放管５ｂ
とから成り、環状支持板５ａが原子炉容器１内に接合さ
れ、環状支持板５ａに開放管５ｂが下向きに、径方向反
射体４が上向きに相互の内縁を合わせて接合され、また
、環状支持板５ａには冷却材３を流通可能とする複数の
穴５Ｃが開けられている。更に、原子炉容器１は、その
底端が原子炉容器１を囲むピット６に固定され、その上
部位置のピット６から突出する振れ止め７により横揺れ
が防止されるようになっている。
他方、出力ユニット２においては、径方向反射体４の環
内を貫通可能の径の炉心８及び炉心８を挟んで接合する
軸方向に冷却材３の複数の流路９ｃを形成した２つの軸
方向反射体９ａ。
９ｂの一方の端縁に炉心８及び軸方向反射体９ａ、９ｂ
と同径の出力ユニット管ｌＯの下端が接続されている。
。この出力ユニット管１０は径方向反射体４の環内に軸
方向反射体９ｂの下端を挿入しても上端が原子炉容器外
に突出する長さとなっおり、また、この際の冷却材３中
の液面近くに位置する所定位置の周面に冷却材３を出力
ユニット管１０の内側から外側へ流通可能とする複数の
流通孔１０ｃ及び冷却材３上に位置する所定位置の周囲
に上記冷却材３の流通をスムーズに行なうためのベント
孔１０ｄが開けられている。また、この出力ユニット管
１０内には上端から下端に向けて冷却材３の流路１１ｃ
を形成した２次系ヒートパイプ１１が、軸方向反射体９
ａと２次系ヒートパイプ１１との間には循環ポンプ１２
が配設され、出力ユニット管ＩＯの上端は遮蔽体１３に
よって気密に覆われている。更に出力ユニット管ＩＯの
上端外周部位にはその上端面を境として下側の区画に熱
電対変換器１４及び上側の区画に作動流体が流通する放
熱部１６が接合され、また側区画を貫通する放熱系ヒー
トパイプ１７が設けられている。以上の構成部材から成
る出力ユニット２は、放熱部Ｉ６の上端において図示し
ない駆動系に接続され、また、原子炉容器１の上端部は
、出力ユニット２が上下動可能な貫通口を有する遮蔽プ
ラグ１８により封栓されている。
また、上記構成部材において、例えば、炉心８で使用さ
れる燃料としてはＵ、Ｐｕの混合酸化物又はＵＮが挙げ
られ、反射体４，９の材質としては例えばＢｅ又はＢｅ
Ｏが使用される。
ヒートパイプ１１．１７、特に放熱系ヒートパイプ１７
の材質は、作動流体がＣｅの場合にはＴｉ又はＮｂ−Ｚ
ｒが適当であり、この場合、通常、４５０〜９００℃の
温度範囲で適用される。また、作動流体がＫの場合には
ＮＩが適当であり、この場合、通常、５ｆｌＯ−ｔ（１
００℃の温度範囲で適用される。
また、原子炉容器１の内壁、支持体５、出力ユニット管
１０等の冷却材３と接触し、かつ、上記に挙げられた構
成部材を除くものの材質としては、例えばステンレス鋼
が使用され、遮蔽体１３の材質としては、Ｌ ｉＨ，８
４Ｃ等の中性子遮蔽材及びＷ等のγ線遮蔽材が使用され
る。
上記構成の液体金属冷却高速炉において、冷却材３に使
用されるＮａ、ＮａＫ等の溶融金属は、原子炉容器１の
周囲に電気ヒータを巻いたり、あるいは原子炉容器１と
ピット６との間の隙間に高温のガスを流したりなどして
融点以上の温度に加熱した状態で注入する。次いで原子
炉容器１内に出力ユニット２を設置し、原子炉容器ｌ内
の冷却材３を自然対流又は循環ポンプＩ２により循環す
る。この冷却材３の循環は、第１図の矢印に従って行な
われる。即ち、冷却材３は、支持体５の開放管５ｂの管
内に流入し、順次、軸方向反射体９ａの流路９ｃ、炉心
８の隙間、他方の軸方向反射体９ｂの流路９Ｃを経て出
力ユニット管ｌＯの管内を上向きに流れ、次いで流通孔
１０ｃから管外に流出して出力ユニット管ＩＯと原子炉
容器１との間を下向きに流れ、支持体５の環状支持板５
ａに開けられた穴５Ｃを通って再び開放管５ｂの管内に
流入する。
原子炉を起動するには、出力ユニット２をその下端に位
置する軸方向反射体９ｂから徐々に径方向反射体４に挿
入する。すると径方向反射体４と炉心８の配置が徐々に
変り、炉心８が２つの軸方向反射体９ａ、９ｂと径方向
反射体４とによって囲まれるようになり（第２図ａ）こ
の液体金属冷却高速炉の出力は臨界に達する。更に出力
ユニット２の下端に位置する軸方向反射体９ａが径方向
反射体４中に深く挿入されるに従い、炉の出力が徐々に
上昇し、炉心８が径方向反射体４の中央に位置する（第
２図Ｃ）場合、炉の出力は最大となる。この場合、炉の
出力が臨界から最大に変化するまでの途中位置（第２図
ｂ）の定格出力を数ｌＯ％上回るが、後述する熱伝達系
の吸放熱過程により対処できる構成となっている。そし
て炉心８が径方向反射体４の中央位置（第２図Ｃ）を越
えて更に深く挿入されると、炉の出力は徐々に減少し、
第２図ｄに示す位置で再び定格出力に達し、次いで第２
図「に示す位置で臨界出力に対応する部分出力に達し１
、炉心８が径方向反射体４を完全に通過する（第２図「
）とスクラ・ムされる。炉心８の反応度に応じて炉心８
で発生した熱は、炉心８の回りで冷却材３により吸熱さ
れ、炉心８回りの冷却材３の温度を上昇させる。そして
高温となった冷却材３は流れに沿って出力ユニット管ｌ
Ｏ中の２次系ヒートパイプ１１を加熱し、２次系ヒート
パイプ１１により吸熱された後、出力管ＩＯの流通孔１
０ｅから外側へ流出される。他方２次系ヒートパイプ１
１により吸熱された熱は、２次系ヒートパイプ１１中を
伝わってその上端まで伝達され、熱雷対変換器１４によ
りその１部が電気エネルギーに変換（変換効率７％程度
）され、残部は放熱系ヒートパイプ１７を伝わって放熱
部１６にお咬１て冷却される。そして、上記熱伝達系の
吸放熱過程で生じた熱電対変換器１４の電気エネルギー
が炉から出力されて利用されることとなる。この炉の出
力の自己制御性は、炉心８の燃料にＵ。
Ｐｕの混合酸化物又はＵＮを使用した場合、それぞれの
ドツプラー効果によるフィードバック効果が期待できる
。また、炉心８で冷却材３の温度が高くなり過ぎても、
既に説明したように原子炉容器１及び出力ユニット２が
熱膨張して炉心８は径方向反射体４に対して中央から下
方に向かって移動するので前記冷却材３の温度に加え、
この炉心８の径方向反射体４に対する配置位置によって
も炉心８の反応度、従って炉の出力が抑制されて調節さ
れる。
以上に示したように第１図に示す液体金属冷却高速炉は
固有の安全性を有する。例えば循環ポンプ１２が停止し
ても冷却材３は自然循環により支障なく循環し、かつ駆
動系の故障によりスクラムが不可能となり、炉心８の温
度がある程度上昇しても冷却材３が高温となり、炉心８
の反応度が減少し、炉心８の温度は許容値以下に押える
ことができる。
この様にして炉心８が例えば７〜８年の年月の後にスク
ラムされた後には、出力ユニット２を原子炉容器１から
引抜き、新たな出力ユニット２と交換することにより炉
心８の燃料交換を行なうことができ、出力ユニット２内
の構成部材の保守補修の際にも出力ユニット２全体を引
抜き、付着している冷却材３からの放射線を遮蔽するた
め不活性ガス雰囲気の遮蔽容器に入れて運搬し、出力ユ
ニット２内の構成部材の保守補修が行なわれる。
以上にこの発明の液体金属冷却高速炉の１例を示したが
、この炉は、例えば炉心の規模に応じて循環ポンプ■２
のない構成とすることもでき、また、炉の出力として熱
エネルギーのみを利用する場合には熱電対変換器１４及
び放熱系ヒートパイプ１７を省略し、出力ユニット管１
（ｌの上端外周部位に２次系ヒートパイプ１１の上端が
位置する構造にすることができる。また、出力管ユニッ
ト２に内蔵した２次系ヒートパイプ１１及び循環ポンプ
１２を削除し、第３図ａに示す様に原子炉容器１の外部
に循環ポンプ１２を介して熱交換器２０を１次冷却系ル
ープを形成する配管１９ａ。
１９ｂ、 １９ｃにより接続したり、あるいは第３図す
に示すように原子炉容器１内の出力ユニット管の外部に
それぞれ循環ポンプ１２及び熱交換器２０を配設しても
良い。更に炉心の規模により第３図ａ及びｂに示す炉か
ら循環ポンプ１２を除いた構成とすることができるのは
勿論である。また、炉心がある程度大型化した場合には
第３図Ｃに示すように原子炉容器１の底に炉心８及び軸
方向反射体９ａ、９ｂの両者の隙間に軸方向に沿って出
し入れ可能な配置位置に制御棒２Ｉを必要な本数立設固
定しても良い。なお第３図Ｃの炉において、制御棒２１
は制御棒取付台２２に取付けられ、この制御棒取付台２
２が原子炉容器１の底に設けられた制御棒取付台受２３
に着脱自在に取付けられ、炉心８に制御棒案内管２４が
取付けられ、この制御棒案内管２４は少なくとも定格運
転中に完全に制御棒２１が挿入され、これ等により出力
ユニット２引抜き後の制御棒２１の交換が行なえ、地震
時の制御棒挿入性に問題の生じない構造となっている。
この様にこの発明の液体金属冷却高速炉は、特許請求の
範囲に記載された範囲内で、炉心の規模炉の利用途等に
より、様々な変形が可能である。
【発明の効果］
以上の説明から明らかなように、この発明によれば、従
来の液体金属冷却高速炉に必要とされていた制御棒駆動
機構及び燃料交換装置を省略でき、更に炉心の規模等に
より循環ポンプ等をも省略できるため、液体金属冷却高
速炉の小型化のために必要な簡略化が行なえ、更に固有
の安全性にも優れており、将来の超小型固有安全炉を実
現する上で適当な構造の液体金属冷却高速炉が提供され
る。EXAMPLES The present invention will be explained in more detail with reference to Examples below. FIG. 1 shows an example of the liquid metal cooled fast reactor of the present invention. This liquid metal cooled fast reactor includes a reactor vessel 1 and an output unit 2. Inside the reactor vessel 1, a coolant 3 made of molten metal, for example Na or NfiK, is accommodated. Further, an annular radial reflector 4 is fixed to the near bottom of the reactor vessel 1 via a support 5 . This support body 5 includes an annular support plate 5a having the same inner diameter as the ring of the radial reflector 4, and an open tube 5b.
An annular support plate 5a is joined to the inside of the reactor vessel 1, an open tube 5b is joined to the annular support plate 5a facing downward, and a radial reflector 4 is joined to the radial reflector 4 facing upward with their inner edges aligned, and A plurality of holes 5C are formed in the support plate 5a to allow the coolant 3 to flow therethrough. Further, the bottom end of the reactor vessel 1 is fixed to a pit 6 surrounding the reactor vessel 1, and a steady rest 7 protruding from the pit 6 at an upper position prevents the reactor vessel 1 from rolling. On the other hand, the output unit 2 includes a core 8 having a diameter that can penetrate the inside of the ring of the radial reflector 4, and two shafts that are joined with the core 8 in between and have a plurality of flow paths 9c for the coolant 3 in the axial direction. Directional reflector 9a. The core 8 and the axial reflectors 9a, 9b are attached to one edge of the core 9b.
The lower end of the output unit pipe 1O having the same diameter as 1 is connected. . The output unit pipe 10 has a length such that its upper end protrudes outside the reactor vessel even if the lower end of the axial reflector 9b is inserted into the ring of the radial reflector 4. A plurality of circulation holes 10c that allow the coolant 3 to flow from the inside to the outside of the output unit pipe 10 on the circumferential surface of a predetermined position located near the liquid surface of the A vent hole 10d is provided to allow the material 3 to flow smoothly. In addition, a flow path 11c for the coolant 3 is provided in the output unit pipe 10 from the upper end to the lower end.
The secondary heat pipe 11 formed with the axial reflector 9
A circulation pump 12 is installed between the a and the secondary heat pipe 11.
is provided, and the upper end of the output unit pipe IO is hermetically covered by a shield 13. Furthermore, a thermocouple converter 14 is connected to the upper end of the output unit pipe IO in the outer circumferential region of the upper end thereof, and a thermocouple converter 14 is connected to the lower section of the output unit pipe IO as a boundary, and a heat dissipation section 16 through which the working fluid flows is connected to the upper section. A heat dissipation system heat pipe 17 is provided. The output unit 2 made up of the above components is connected to a drive system (not shown) at the upper end of the heat dissipation part I6, and the upper end of the reactor vessel 1 is connected to a shielding plug having a through hole through which the output unit 2 can move up and down. It is sealed by 18. Further, in the above-mentioned structural members, for example, the fuel used in the core 8 may be a mixed oxide of U or Pu, or UN, and the material of the reflectors 4 and 9 may be, for example, Be or Be.
O is used. Heat pipe 11.17, especially heat dissipation system heat pipe 17
The material of is Ti or Nb-Z when the working fluid is Ce.
r is suitable, in which case it is usually applied at a temperature range of 450-900°C. Furthermore, when the working fluid is K, NI is suitable; in this case, usually 5flO-t(1
Applicable in the temperature range of 00°C. In addition, the materials that come into contact with the coolant 3, such as the inner wall of the reactor vessel 1, the support body 5, the output unit tube 10, and other than the above-mentioned structural members, are made of, for example, stainless steel. The material of the body 13 is L iH,8
Neutron shielding materials such as 4C and gamma ray shielding materials such as W are used. In the liquid metal cooled fast reactor having the above configuration, the molten metal such as Na and NaK used as the coolant 3 is heated by wrapping an electric heater around the reactor vessel 1 or between the reactor vessel 1 and the pit 6. It is injected after being heated to a temperature above the melting point, such as by flowing a high-temperature gas through the gap between the two. Next, an output unit 2 is installed in the reactor vessel 1, and the coolant 3 in the reactor vessel 1 is circulated by natural convection or by a circulation pump I2. This circulation of the coolant 3 is performed according to the arrows in FIG. That is, the coolant 3 flows into the open tube 5b of the support body 5, and sequentially passes through the channel 9c of the axial reflector 9a, the gap in the core 8, and the channel 9C of the other axial reflector 9b. It flows upward in the output unit pipe IO, then flows out of the pipe from the flow hole 10c, flows downward between the output unit pipe IO and the reactor vessel 1, and flows through the annular support plate 5 of the support body 5.
It flows into the open tube 5b again through the hole 5C made in the hole 5C. To start the reactor, the power unit 2 is gradually inserted into the radial reflector 4 starting with the axial reflector 9b located at its lower end. Then, the arrangement of the radial reflectors 4 and the core 8 gradually changes, and the core 8 is now surrounded by the two axial reflectors 9a, 9b and the radial reflector 4 (Fig. 2a). The output of the cooled fast reactor reaches criticality. Furthermore, as the axial reflector 9a located at the lower end of the output unit 2 is inserted deeper into the radial reflector 4, the output of the furnace gradually increases, and the core 8 is located at the center of the radial reflector 4. (Fig. 2C), the furnace output is maximum. In this case, the furnace output exceeds the rated output by several 10% at the intermediate position (Fig. 2b) before changing from critical to maximum, but the configuration is such that this can be dealt with by the heat absorption and release process of the heat transfer system, which will be described later. . As the core 8 is inserted deeper beyond the center position of the radial reflector 4 (FIG. 2C), the power of the reactor gradually decreases.
The rated output is reached again at the position shown in Figure 2d, and then the second
The partial power corresponding to the critical power is reached at the position shown in the figure 1.
, the core 8 completely passes through the radial reflector 4 (see Figure 2).
) and is scrammed. Core 8 depending on the reactivity of core 8
The heat generated is absorbed by the coolant 3 around the core 8, increasing the temperature of the coolant 3 around the core 8. The high temperature coolant 3 flows along the flow into the output unit pipe l.
After the secondary heat pipe 11 in O is heated and heat is absorbed by the secondary heat pipe 11, the flow hole 1 of the output pipe IO is heated.
It flows out from 0e. On the other hand, secondary heat pipe 1
The heat absorbed by 1 is transmitted through the secondary heat pipe 11 to its upper end, and a part of it is converted into electrical energy by the thermal lightning pair converter 14 (conversion efficiency is about 7%), and the rest is It is transmitted through the heat dissipation system heat pipe 17 and cooled by the heat dissipation part 16. Then, the electrical energy of the thermocouple converter 14 generated during the heat absorption/dissipation process of the heat transfer system is outputted from the furnace and used. The self-controllability of the output of this reactor is based on the fuel in the core 8. When a mixed oxide of Pu or UN is used, a feedback effect due to the Doppler effect of each can be expected. Furthermore, even if the temperature of the coolant 3 in the core 8 becomes too high,
As already explained, as the reactor vessel 1 and the output unit 2 thermally expand and the reactor core 8 moves downward from the center relative to the radial reflector 4, in addition to the temperature of the coolant 3,
The reactivity of the core 8 and, therefore, the output of the reactor are suppressed and regulated by the arrangement position of the core 8 with respect to the radial reflector 4. As shown above, the liquid metal cooled fast reactor shown in FIG. 1 has inherent safety. For example, even if the circulation pump 12 stops, the coolant 3 continues to circulate without any problem due to natural circulation, and a drive system failure makes scram impossible, and even if the temperature of the core 8 rises to a certain extent, the coolant 3 becomes high temperature. core 8
The reactivity of the reactor core 8 is reduced, and the temperature of the reactor core 8 can be kept below the permissible value. After the reactor core 8 has been scrammed in this way, for example after 7 to 8 years, the refueling of the reactor core 8 can be carried out by pulling out the power unit 2 from the reactor vessel 1 and replacing it with a new power unit 2. During maintenance and repair of the components inside the output unit 2, the entire output unit 2 can be pulled out and placed in a shielded container with an inert gas atmosphere to shield radiation from the coolant 3 attached. The output unit 2 is transported, and the components inside the output unit 2 are maintained and repaired. An example of the liquid metal cooled fast reactor of the present invention has been shown above.
In addition, when only thermal energy is used as the output of the furnace, the thermocouple converter 14 and the heat dissipation system heat pipe 17 can be omitted, and the output unit pipe 1
(It is possible to have a structure in which the upper end of the secondary heat pipe 11 is located at the outer circumferential portion of the upper end of the As shown in Figure a, the heat exchanger 20 is connected to the outside of the reactor vessel 1 via the circulation pump 12 through piping 19a, 19b, 19c forming a primary cooling system loop, or as shown in Figure 3. As shown in FIG. Of course, it is possible to have a configuration in which the reactor core 8 and axial reflectors 9a and 9b are removed from the bottom of the reactor vessel 1, as shown in FIG. The required number of control rods 2I may be fixed upright in a position where they can be taken in and out along the axial direction in the gap between the two.In addition, in the furnace shown in FIG.
is attached to the control rod mount 22, and this control rod mount 2
2 is a control rod mount support 23 provided at the bottom of the reactor vessel 1.
A control rod guide tube 24 is attached to the reactor core 8, and the control rods 21 are completely inserted into the control rod guide tube 24 at least during rated operation. The structure allows the rod 21 to be replaced and there is no problem with inserting the control rod during an earthquake. In this manner, the liquid metal cooled fast reactor of the present invention can be modified in various ways within the scope of the claims, depending on the use of the core scale reactor, etc. [Effects of the Invention] As is clear from the above description, according to the present invention, the control rod drive mechanism and fuel exchange device required for conventional liquid metal cooled fast reactors can be omitted, and the scale of the reactor core can be reduced. Since circulation pumps, etc. can be omitted, the simplification necessary for downsizing liquid metal-cooled fast reactors can be achieved, and it also has excellent inherent safety, which will help realize future ultra-small inherently safe reactors. A liquid metal cooled fast reactor of suitable construction is provided.
第１図は、この発明の液体金属冷却高速炉の１例を示す
説明図、
第２図ａないしｒは、炉の出力が臨界からスクラムに至
るまでのこの発明に係る炉心、の配置を順次示す説明図
、
第３図ａないしＣは、それぞれこの発明の液体金属冷却
高速炉の別の１例を示す説明図である。
ｌ・・・原子炉容器、２・・・出力ユニット、３・・・
冷却材、４・・・径方向反射体、８・・・炉心、９・・
・軸方向反射体、１０・・・出力ユニット管、１１・・
・２次系ヒートパイプ、１２・・・循環ポンプ、１４・
・・熱電対変換器、１７・・・放熱系ヒートパイプ、２
０・・・熱交換器、２１・・・制御棒、９ｃ、ｌｌｃ・
・・冷却材流路、ＬＯｃ・・・冷却材流通孔。
）（２川
リＣ１
ｌ・・・原子炉容器
２・・・出力ユニ１ト
３・・・冷却祠
ｌｌ・・・径ノｒ１句ｊ５ｆ−Ｑ４ （本８・・・炉心
９・・・軸）ｌ向板ｑ（体
１０・・・出力−１，ニツト管
１１・・・２次系ヒートバイア
１２・・・■環ボン１
１／Ｉ・・・熱電対交換２ｉｉ
１７・・・放熱系ヒートバイ１
２０・・・熱交換器
２１・・・制御ツ１＋
１１＋・・・・冷却ｔ４流路
ｌＯ（：・・・冷却（イ流通孔
！を勤ｔへFIG. 1 is an explanatory diagram showing one example of the liquid metal cooled fast reactor of the present invention, and FIGS. 2 a to 2 r sequentially show the arrangement of the reactor core according to the present invention as the reactor output ranges from critical to scram. The explanatory diagrams shown in FIGS. 3A to 3C are explanatory diagrams each showing another example of the liquid metal cooled fast reactor of the present invention. l...Reactor vessel, 2...Output unit, 3...
Coolant, 4... Radial reflector, 8... Core, 9...
・Axial reflector, 10... Output unit tube, 11...
・Secondary system heat pipe, 12...Circulation pump, 14・
...Thermocouple converter, 17...Radiation system heat pipe, 2
0...Heat exchanger, 21...Control rod, 9c, llc・
...Coolant flow path, LOc...Coolant distribution hole. ) (2 rivers C1 l...Reactor vessel 2...Output unit 13...Cooling shrine ll...Diameter r1 clause j5f-Q4 (Book 8...Core 9...Axis ) l facing plate q (body 10...output -1, knit tube 11...secondary system heat via 12...■ ring bomb 1 1/I...thermocouple exchange 2ii 17...radiation system heat via 1 20...Heat exchanger 21...Control 1+ 11+...Cooling t4 flow path lO(:...Cooling (a)
Claims (1)
置されて固定されていると共に、前記径方向反射体の環
内を貫通可能な炉心及び該炉心を挟んで接合する軸方向
に冷却材流路を形成した上下２つの軸方向反射体と、上
部軸方向反射体の上端に下端が接続され、両端間の所定
位置の周面に冷却材流通孔を開けた構造の出力ユニット
管であって、前記径方向反射体の環内に前記炉心に上端
を固定した下部軸方向反射体の下端を挿入しても上端が
前記原子炉容器外に突出する長さの出力ユニット管とを
有することを特徴とする液体金属冷却高速炉。 ２、出力ユニット管内に上端から下端に向けて冷却材流
路を形成した２次系ヒートパイプを配設した請求項１記
載の液体金属冷却高速炉。 ３、出力ユニット管の上端外周部位に放熱系ヒートパイ
プ及び熱電対変換器を配設した請求項２記載の液体金属
冷却高速炉。 ４、２次系ヒートパイプと軸方向反射体との間に循環ポ
ンプを設けた請求項２又は３記載の液体金属冷却高速炉
。 ５、熱交換器を原子炉容器に１次冷却系ループを形成す
る配管により接続した請求項１記載の液体金属冷却高速
炉。 ６、熱交換器と原子炉容器との間に循環ポンプを介設し
た請求項５記載の液体金属冷却高速炉。 ７、原子炉容器内の出力ユニット管配置位置周辺に熱交
換器を配設した請求項１記載の液体金属冷却高速炉。 ８、原子炉容器内の出力ユニット管配置位置周辺に更に
循環ポンプを配設した請求項７記載の液体金属冷却高速
炉。 ９、原子炉容器内底部から炉心及び軸方向反射体の両者
の隙間に軸方向に沿って出し入れ可能な配置位置に制御
棒を立設した請求項１ないし８のいずれか１項記載の液
体金属冷却高速炉。[Scope of Claims] 1. A reactor core in which an annular radial reflector is disposed and fixed in a coolant in a reactor vessel, and the inside of the ring of the radial reflector can be penetrated, and the core There are two upper and lower axial reflectors that form a coolant flow path in the axial direction that are sandwiched and joined, and the lower end is connected to the upper end of the upper axial reflector, and coolant flow holes are formed on the circumferential surface at a predetermined position between both ends. An output unit tube having an open structure, the output unit tube having a length such that its upper end protrudes outside the reactor vessel even if the lower end of a lower axial reflector whose upper end is fixed to the reactor core is inserted into the ring of the radial reflector. A liquid metal cooled fast reactor, characterized in that it has a power unit tube. 2. The liquid metal cooled fast reactor according to claim 1, further comprising a secondary heat pipe having a coolant flow path formed in the output unit tube from the upper end to the lower end. 3. The liquid metal cooled fast reactor according to claim 2, wherein a heat dissipation system heat pipe and a thermocouple converter are disposed at the outer peripheral portion of the upper end of the output unit tube. 4. The liquid metal cooled fast reactor according to claim 2 or 3, further comprising a circulation pump provided between the secondary heat pipe and the axial reflector. 5. The liquid metal cooled fast reactor according to claim 1, wherein the heat exchanger is connected to the reactor vessel by piping forming a primary cooling system loop. 6. The liquid metal cooled fast reactor according to claim 5, further comprising a circulation pump interposed between the heat exchanger and the reactor vessel. 7. The liquid metal cooled fast reactor according to claim 1, further comprising a heat exchanger disposed around the output unit tube arrangement position within the reactor vessel. 8. The liquid metal cooled fast reactor according to claim 7, further comprising a circulation pump disposed around the output unit pipe arrangement position within the reactor vessel. 9. The liquid metal according to any one of claims 1 to 8, wherein the control rod is erected at a position where it can be taken in and out along the axial direction from the inner bottom of the reactor vessel into the gap between both the reactor core and the axial reflector. Cooled fast reactor.
Priority Applications (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1028423A JPH0715503B2 (en) | 1989-02-07 | 1989-02-07 | Liquid metal cooling fast reactor |
| FR9001307A FR2642888A1 (en) | 1989-02-07 | 1990-02-05 | Fast reactor cooled with liquid metal |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1028423A JPH0715503B2 (en) | 1989-02-07 | 1989-02-07 | Liquid metal cooling fast reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH02206794A true JPH02206794A (en) | 1990-08-16 |
| JPH0715503B2 JPH0715503B2 (en) | 1995-02-22 |
Family
ID=12248250
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1028423A Expired - Lifetime JPH0715503B2 (en) | 1989-02-07 | 1989-02-07 | Liquid metal cooling fast reactor |
Country Status (2)
| Country | Link |
|---|---|
| JP (1) | JPH0715503B2 (en) |
| FR (1) | FR2642888A1 (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2012509467A (en) * | 2008-11-17 | 2012-04-19 | ニュースケール パワー インコーポレイテッド | Through-flow integrated reactor vessel reflector |
| JP2012154644A (en) * | 2011-01-21 | 2012-08-16 | Toshiba Corp | Heat transportation device of reactor container and method of the same |
| JP2013519094A (en) * | 2010-02-04 | 2013-05-23 | ジェネラル アトミックス | Modular fission waste converter |
| CN114530264A (en) * | 2022-01-04 | 2022-05-24 | 中国原子能科学研究院 | Space heap |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR101404954B1 (en) * | 2012-10-23 | 2014-06-12 | 국립대학법인 울산과학기술대학교 산학협력단 | Method Of Nuclear Corium Cooling Using Liquid Metal Layer, And Nuclear Corium Cooling System Using The Same |
| CN114530263B (en) * | 2022-01-04 | 2024-03-22 | 中国原子能科学研究院 | Nuclear reactor |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3385759A (en) * | 1967-05-08 | 1968-05-28 | Atomic Energy Commission Usa | Fast burst neutronic reactor |
| US3664923A (en) * | 1968-09-11 | 1972-05-23 | Thomas J Connolly | Fast neutronic reactor utilizing plutonium 240 fuel |
| DE3579588D1 (en) * | 1984-09-05 | 1990-10-11 | Georg Vecsey | METHOD FOR PASSIVE TRANSFER OF HEAT FROM CORE REACTORS AND DEVICE FOR OPERATING THIS METHOD. |
-
1989
- 1989-02-07 JP JP1028423A patent/JPH0715503B2/en not_active Expired - Lifetime
-
1990
- 1990-02-05 FR FR9001307A patent/FR2642888A1/en active Granted
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2012509467A (en) * | 2008-11-17 | 2012-04-19 | ニュースケール パワー インコーポレイテッド | Through-flow integrated reactor vessel reflector |
| US10636529B2 (en) | 2008-11-17 | 2020-04-28 | Nuscale Power, Llc | Reactor vessel reflector with integrated flow-through |
| JP2013519094A (en) * | 2010-02-04 | 2013-05-23 | ジェネラル アトミックス | Modular fission waste converter |
| US9767926B2 (en) | 2010-02-04 | 2017-09-19 | General Atomics | Modular nuclear fission waste conversion reactor |
| JP2012154644A (en) * | 2011-01-21 | 2012-08-16 | Toshiba Corp | Heat transportation device of reactor container and method of the same |
| CN114530264A (en) * | 2022-01-04 | 2022-05-24 | 中国原子能科学研究院 | Space heap |
| CN114530264B (en) * | 2022-01-04 | 2024-02-20 | 中国原子能科学研究院 | Space pile |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0715503B2 (en) | 1995-02-22 |
| FR2642888A1 (en) | 1990-08-10 |
| FR2642888B1 (en) | 1993-06-04 |
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