JPH067179B2 - Self-refining molten metal fuel furnace - Google Patents
Self-refining molten metal fuel furnaceInfo
- Publication number
- JPH067179B2 JPH067179B2 JP62189546A JP18954687A JPH067179B2 JP H067179 B2 JPH067179 B2 JP H067179B2 JP 62189546 A JP62189546 A JP 62189546A JP 18954687 A JP18954687 A JP 18954687A JP H067179 B2 JPH067179 B2 JP H067179B2
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- phase
- alloy
- reactor
- salt
- 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 152
- 238000007670 refining Methods 0.000 title claims description 19
- 229910052751 metal Inorganic materials 0.000 title claims description 11
- 239000002184 metal Substances 0.000 title claims description 11
- 229910045601 alloy Inorganic materials 0.000 claims description 54
- 239000000956 alloy Substances 0.000 claims description 54
- 150000003839 salts Chemical class 0.000 claims description 48
- 238000002844 melting Methods 0.000 claims description 22
- 230000008018 melting Effects 0.000 claims description 22
- 230000004992 fission Effects 0.000 claims description 12
- 229910052778 Plutonium Inorganic materials 0.000 claims description 9
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 claims description 4
- 239000002826 coolant Substances 0.000 claims description 3
- 229910001338 liquidmetal Inorganic materials 0.000 claims description 3
- 229910000711 U alloy Inorganic materials 0.000 claims description 2
- 239000000155 melt Substances 0.000 claims description 2
- 239000012071 phase Substances 0.000 description 84
- 238000000034 method Methods 0.000 description 19
- 238000012958 reprocessing Methods 0.000 description 17
- 239000002915 spent fuel radioactive waste Substances 0.000 description 16
- 229910001361 White metal Inorganic materials 0.000 description 13
- 239000010969 white metal Substances 0.000 description 13
- 238000002485 combustion reaction Methods 0.000 description 11
- 230000008569 process Effects 0.000 description 11
- 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 10
- 229910052708 sodium Inorganic materials 0.000 description 10
- 239000011734 sodium Substances 0.000 description 10
- 238000006243 chemical reaction Methods 0.000 description 9
- 239000007788 liquid Substances 0.000 description 9
- 238000000605 extraction Methods 0.000 description 8
- 229910052783 alkali metal Inorganic materials 0.000 description 6
- 150000001340 alkali metals Chemical class 0.000 description 6
- 238000010008 shearing Methods 0.000 description 6
- 238000009491 slugging Methods 0.000 description 6
- 229910052770 Uranium Inorganic materials 0.000 description 5
- 238000012545 processing Methods 0.000 description 5
- 229910001152 Bi alloy Inorganic materials 0.000 description 4
- 229910052761 rare earth metal Inorganic materials 0.000 description 4
- 150000002910 rare earth metals Chemical class 0.000 description 4
- 238000005253 cladding Methods 0.000 description 3
- 229910000765 intermetallic Inorganic materials 0.000 description 3
- 239000007791 liquid phase Substances 0.000 description 3
- 230000007246 mechanism Effects 0.000 description 3
- 238000010128 melt processing Methods 0.000 description 3
- 230000009257 reactivity Effects 0.000 description 3
- 238000004064 recycling Methods 0.000 description 3
- 229910000905 alloy phase Inorganic materials 0.000 description 2
- 238000005266 casting Methods 0.000 description 2
- 150000004820 halides Chemical class 0.000 description 2
- 238000002347 injection Methods 0.000 description 2
- 239000007924 injection Substances 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 239000000047 product Substances 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- 229910052684 Cerium Inorganic materials 0.000 description 1
- 241000196324 Embryophyta Species 0.000 description 1
- 229910052693 Europium Inorganic materials 0.000 description 1
- 101100504379 Mus musculus Gfral gene Proteins 0.000 description 1
- 229910052772 Samarium Inorganic materials 0.000 description 1
- 229910001297 Zn alloy Inorganic materials 0.000 description 1
- 239000003513 alkali Substances 0.000 description 1
- 229910052797 bismuth Inorganic materials 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
- 238000005202 decontamination Methods 0.000 description 1
- 230000003588 decontaminative effect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 238000005868 electrolysis reaction Methods 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 229910052746 lanthanum Inorganic materials 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000010309 melting process Methods 0.000 description 1
- 229910052763 palladium Inorganic materials 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 229910052697 platinum Inorganic materials 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 239000002244 precipitate Substances 0.000 description 1
- 238000000746 purification Methods 0.000 description 1
- 238000009853 pyrometallurgy Methods 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 238000006479 redox reaction Methods 0.000 description 1
- 229910052703 rhodium Inorganic materials 0.000 description 1
- 229910052707 ruthenium Inorganic materials 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 230000000699 topical effect Effects 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
- Manufacture And Refinement Of Metals (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を冷却材して用い、炉
心に複数の燃料要素を配設してなる高速中性子炉に関
し、さらに詳しくは、プルトラウム（Ｐｕ）および／ま
たはウラン（Ｕ）の低融点合金燃料を溶融状態で燃焼さ
せるタイプの溶融金属燃料炉に関するものである。DETAILED DESCRIPTION OF THE INVENTION <Industrial field of application> The present invention generally relates to a fast neutron reactor in which a liquid metal is used as a coolant and a plurality of fuel elements are arranged in a core, and more particularly, The present invention relates to a molten metal fuel furnace of a type in which a low melting point alloy fuel of plutonium (Pu) and / or uranium (U) is burned in a molten state.
〈従来の技術〉 従来から軽水炉による原子力発電においては、酸化物燃
料を燃焼させたのちの使用済燃料を再処理工場へ運び、
湿式法により処理したのち、回収したＰｕをリサイクル
している。また、従来の酸化物燃料を用いた高速増殖炉
もこれと同じシステムにより回収燃料をリサイクルして
いる。<Prior art> Conventionally, in nuclear power generation by a light water reactor, the spent fuel after burning the oxide fuel is transported to a reprocessing plant,
After processing by the wet method, the recovered Pu is recycled. Also, the conventional fast breeder reactor using oxide fuel recycles recovered fuel by the same system.
これに対して米国で提案されているＩＦＲ（Integral F
ast Reactor）は、Ｐｕの金属燃料を用い、使用済燃料
をハライド・スラッギング抽出反応と電解とを組合せた
再処理プロセスによって施設内で行ない、回収燃料をリ
サイクルするシステムである。On the other hand, IFR (Integral F
ast Reactor) is a system that uses a metallic fuel of Pu and uses spent fuel in a facility by a reprocessing process that combines halide slugging extraction reaction and electrolysis to recycle recovered fuel.
（"A Proposed Pyrometallurgical Process For Rapid
Recycle of Discharged Fuel Materials From The Inte
gral Fast Reactor",L.Burris et al,American Nuclear
Society International Topical Meeting(August 26-2
9,1984,Jachson,Wyoming,US)"Fuel Reprocessing and W
aste Management"Proceeding Vol. 2,pp 2-257 to2-277
参照。） 〈発明が解決しようとする問題点〉 上述した軽水炉や高速増殖炉における使用済燃料の再処
理は、プロセスも面倒で設備的にもコストのかかるもの
である。また米国のＩＦＲは酸化物燃料のリサイクルに
比べて使用済燃料の再処理設備はコンパクトになるもの
の、再処理プロセスは未だ複雑である。("A Proposed Pyrometallurgical Process For Rapid
Recycle of Discharged Fuel Materials From The Inte
gral Fast Reactor ", L.Burris et al, American Nuclear
Society International Topical Meeting (August 26-2
9,1984, Jachson, Wyoming, US) "Fuel Reprocessing and W
aste Management "Proceeding Vol. 2, pp 2-257 to2-277
reference. <Problems to be Solved by the Invention> The above-mentioned reprocessing of spent fuel in the light water reactor and the fast breeder reactor is complicated in process and expensive in terms of equipment. Further, although IFR in the United States has a compact reprocessing facility for spent fuel compared to the recycling of oxide fuel, the reprocessing process is still complicated.
そこでこの発明は使用済燃料の再処理をコンパクトな設
備でかつ簡略化されたプロセスで行なうことができる原
子炉システムを提供することを目的としてなされたもの
である。Therefore, the present invention has been made for the purpose of providing a nuclear reactor system capable of reprocessing spent fuel with a compact facility and in a simplified process.
〈問題点を解決するための手段および作用〉 従来の使用済燃料の再処理は、燃料は炉内で燃焼させ、
再処理は燃焼後に炉外で行なうものという概念に立って
いるのに対し、この発明は、燃料を炉内で燃焼さながら
再処理操作を行ない、その後の炉外での精製の手間を省
くという発想のもとに考え出された全く新たな概念とい
えるものである。<Means and Actions for Solving Problems> In the conventional reprocessing of spent fuel, the fuel is burned in the furnace,
While the reprocessing is based on the concept of being carried out outside the furnace after combustion, the present invention is an idea that the reprocessing operation is performed while burning the fuel inside the furnace, and the subsequent labor for refining outside the furnace is omitted. It is a completely new concept that was conceived based on.
すなわちこの発明は、液体金属を冷却材として用い、炉
心に複数の燃料要素を配設してなる原子炉において、各
燃料要素の内部には、原子炉運転温度で溶融する低融点
プルトニウムおよび／またはウラン合金燃料相と低融点
塩相とガスプレナムとがこの順で下層から上層へ向けて
形成されており、これによって原子炉運転中は溶融形状
で該合金燃料相が燃焼し、このとき発生する核分裂ガス
は該ガスプレナムに集められ、また核分裂生成物の一部
は溶融状態の塩相へ移行し、もって該燃料要素内の合金
燃料に自己精製機能をもたせるようにしたことを特徴と
する自己精製溶融金属燃料炉である。That is, the present invention uses a liquid metal as a coolant, and in a nuclear reactor in which a plurality of fuel elements are arranged in a reactor core, low melting point plutonium and / or a low melting point plutonium that melts at a reactor operating temperature is provided inside each fuel element. A uranium alloy fuel phase, a low melting point salt phase, and a gas plenum are formed in this order from the lower layer to the upper layer, which causes the alloy fuel phase to burn in a molten form during reactor operation, and the fission that occurs at this time. The gas is collected in the gas plenum, and a part of the fission products is transferred to a salt phase in a molten state, so that the alloy fuel in the fuel element has a self-refining function. It is a metal fuel reactor.
炉運転温度は通常６００〜７００°Ｃであり、この温度
では燃料要素内の低融点合金燃料相と低融点塩相とはと
もに溶融状態となっている。かような溶融合金燃料相と
溶融塩相の間には、核分裂の進行に伴って合金燃料相中
に発生する核分裂生成分（以下ＦＰと略記する）の一部
（Ｅｕ，Ｓｍ，Ｌａ，Ｃｅ等の希土類；Ｓｒ，Ｂａ等の
アルカリ土類；Ｃｓ等のアルカリ金属）を酸化還元反応
により溶融塩相側へ抽出する反応（スラッギング抽出反
応）が起る。すなわち、合金燃料の燃焼中に希土類等の
一部のＦＰは常に溶融塩相に移行するため、合金燃料相
中のＦＰはかなり除去される。The furnace operating temperature is usually 600 to 700 ° C., and at this temperature, both the low melting point alloy fuel phase and the low melting point salt phase in the fuel element are in a molten state. Between the molten alloy fuel phase and the molten salt phase, a part (Eu, Sm, La, Ce) of fission product (hereinafter abbreviated as FP) generated in the alloy fuel phase as the fission progresses. And the like; rare earths such as Sr and Ba; alkaline earths such as Sr and Ba; alkali metals such as Cs) are extracted (slugging extraction reaction) into the molten salt phase side by redox reaction. That is, during burning of the alloy fuel, some FP such as rare earths always moves to the molten salt phase, so that FP in the alloy fuel phase is considerably removed.
一方、溶融合金燃料相中にはＰｔ，Ｒｕ，Ｒｈ，Ｐｄ等
の白金属のＦＰが主として残留する。これら白金属ＦＰ
は、その後の処理工程で精製，除去することができる。
また、燃焼により発生する核分裂ガスは燃料要素内のガ
スプレナムに全て集められる。On the other hand, FPs of white metals such as Pt, Ru, Rh, and Pd mainly remain in the molten alloy fuel phase. These white metal FP
Can be purified and removed in the subsequent processing steps.
In addition, the fission gas generated by combustion is all collected in the gas plenum in the fuel element.
この発明において使用できる低融点合金燃料としては、
例えば融点600〜700℃程度のＰｕ−Ｂｉ合金、濃縮Ｕ−
Ｂｉ合金、Ｐｕ−Ｕ−Ｂｉ合金あるいはＰｕ−Ｕ−Ｍｇ
−Ｚｎ合金等が使用できる。As the low melting point alloy fuel that can be used in the present invention,
For example, a Pu-Bi alloy with a melting point of 600-700 ° C, concentrated U-
Bi alloy, Pu-U-Bi alloy or Pu-U-Mg
-Zn alloy etc. can be used.
また低融点の塩相としては、例えばＬｉＣｌ−ＫＣｌ−
ＭｇＣｌ２といった３成分系の混合塩が挙げられる。Further, as the low melting point salt phase, for example, LiCl-KCl-
A three-component mixed salt such as MgCl 2 may be mentioned.
合金燃料相と塩相との溶融状態での接触により起る反応
は、例えば希土類（ＲＥ）とＭｇＣｌ２との間では次の
ようないわゆるハライド・スラッギング抽出反応が行わ
れる： ＲＥ ＋３／２ＭｇＣｌ２ＲＥＣｌ３＋３／２Ｍｇ （合金相） （塩相） （塩相） （合金相） この発明の原子炉の特徴を簡単に述べれば、燃料要素内
に合金燃料と塩を封入しておき、炉内で合金燃料を燃焼
させながら、溶融状態の合金燃料相と塩相との間に上記
したスラッギング抽出反応を行なわせてＦＰを塩相側へ
抽出させることである。すなわち、合金燃料は燃えなが
らにして自分自信のＦＰを精製，除去してしまうため
“自己精製”炉と名付けることができるのである。The reaction caused by the contact between the alloy fuel phase and the salt phase in the molten state is, for example, the following so-called halide slugging extraction reaction between rare earth (RE) and MgCl 2 : RE + 3 / 2MgCl 2 RECl 3 + 3 / 2Mg (alloy phase) (salt phase) (salt phase) (alloy phase) To briefly describe the features of the reactor of the present invention, the alloy fuel and salt are enclosed in the fuel element, and While burning the alloy fuel, the slagging extraction reaction is performed between the molten alloy fuel phase and the salt phase to extract FP to the salt phase side. In other words, alloy fuel purifies and removes its own FP while burning, so it can be named "self-refining" reactor.
合金燃料相で燃焼しきっていないＰｕおよびＵが含まれ
る場合は２３８Ｕ→２３９Ｐｕで新たに生じたＰｕは、
回収，リサイクルして燃料として再度原子炉に戻すので
あるが、この発明の自己精製炉においては、炉内での溶
融合金燃料の燃焼中にＦＰの多くが溶融塩相へ抽出さ
れ、ＰｕおよびＵの合金燃料相は既にかなり精製されて
いることになるため、使用済燃料要素を取り出して冷却
し、燃料要素内で両相とも固化した段階で燃料要素を剪
断して両相を分離してしまえば、かなり精製された使用
済合金燃料を回収できることになる。その結果、この燃
料の再処理プロセスを大幅に簡略化することが可能とな
る。また核分裂ガスは燃料要素内のガスプロナムに全て
集められているため、再処理プロセスにおけるガスの処
理も簡略に行なえる。When Pu and U that are not completely burned in the alloy fuel phase are included, the newly generated Pu from 238 U → 239 Pu is
The fuel is recovered and recycled and then returned to the reactor as fuel again. In the self-refining furnace of the present invention, most of FP is extracted into the molten salt phase during combustion of the molten alloy fuel in the reactor, and Pu and U Since the alloy fuel phase of is already considerably refined, the spent fuel element is taken out, cooled, and when both phases are solidified in the fuel element, the fuel element is sheared and the two phases are separated. For example, it will be possible to recover highly purified spent alloy fuel. As a result, this fuel reprocessing process can be greatly simplified. Further, since the fission gas is all collected in the gas pronum in the fuel element, the gas treatment in the reprocessing process can be simplified.
〈実施例〉 以下に図面を参照してこの発明の実施例を説明する。<Examples> Examples of the present invention will be described below with reference to the drawings.
炉内で合金燃料を燃焼している間に溶融塩によるスラッ
ギング抽出反応を効率良く行なわせるための燃料要素形
状が種々考えられる。この発明において特に留意する点
は、燃料は溶融状態で使用されるため熱伝導上の問題が
あまりないこと、およびスラッギング抽出反応を効率良
く行なわせるために溶融合金燃料相と溶融塩相とを対流
により接触させることが望ましいことである。Various fuel element shapes are conceivable for efficiently performing the slugging extraction reaction by the molten salt while burning the alloy fuel in the furnace. In this invention, the points to be particularly noted are that the fuel is used in a molten state, so that there are few problems in heat conduction, and convection between the molten alloy fuel phase and the molten salt phase in order to efficiently carry out the slugging extraction reaction. It is desirable to make contact with each other.
第１図はこの発明で使用される燃料要素の形状の一例で
あるバレル形状燃料要素１ａを示すものであって、円筒
形の燃料被覆２ａ内にはＰｕ，Ｕを含む合金燃料相３と
塩相４とがこの順で下層と上層に設けられ、塩相４の上
にはさらにガスプレナム５が形成されている。第１Ｂ図
は燃料要素の炉心配置例を示し、液体ナトリウム２１を
満たした炉容器２０内に複数本のバレル形状燃料要素１
ａが配列されている。FIG. 1 shows a barrel-shaped fuel element 1a which is an example of the shape of the fuel element used in the present invention, in which an alloy fuel phase 3 containing Pu and U and a salt are contained in a cylindrical fuel cladding 2a. The phase 4 is provided in this order in the lower layer and the upper layer, and the gas plenum 5 is further formed on the salt phase 4. FIG. 1B shows an example of core arrangement of fuel elements, in which a plurality of barrel-shaped fuel elements 1 are arranged in a reactor vessel 20 filled with liquid sodium 21.
a is arranged.
第２Ａ図は六角柱形の燃料要素１ｂの例を示しており、
六角柱形の燃料被覆２ｂ内に合金燃料相３、塩相４およ
びガスプレナム５が形成されている点はバレル形状燃料
要素１ａと同じである。第２Ｂ図は六角柱形燃料要素１
ｂの炉心配置例を示している。FIG. 2A shows an example of a hexagonal prismatic fuel element 1b,
Similar to the barrel-shaped fuel element 1a, the alloy fuel phase 3, the salt phase 4, and the gas plenum 5 are formed in the hexagonal-shaped fuel cladding 2b. FIG. 2B shows a hexagonal columnar fuel element 1
The core arrangement example of b is shown.
第３図は断面扇形の板状の燃料要素１ｃを示し、第４Ａ
図は第３の板状燃料要素１ｃと第１Ａ図のバレル形状燃
料要素１ａとを３本の連通管６で連結した構造の変形板
状燃料要素１ｄを示す。第４Ｂ図は第４Ａ図の燃料要素
の炉心配置例であり、バレル形状燃料要素部分が外側に
なるように円周方向に等間隔で配列され、中央には制御
棒２２が挿入自在に配設される。第４Ｂ図のように変形
板状燃料要素１ｄを放射方向に配列する場合には、第４
Ｃ図からわかるように、炉心中央部の高温と炉心外寄り
のやや低温の間の温度差によって、燃料要素１ｄ内で溶
融合金燃料相３および溶融塩相４の対流（矢印）が起
り、溶融塩相４によるスラッギング抽出反応を効率良く
行なわせることができる。FIG. 3 shows a plate-shaped fuel element 1c having a fan-shaped cross section,
The figure shows a deformed plate-shaped fuel element 1d having a structure in which the third plate-shaped fuel element 1c and the barrel-shaped fuel element 1a of FIG. 1A are connected by three communication pipes 6. FIG. 4B is an example of the core arrangement of the fuel elements shown in FIG. 4A, in which the barrel-shaped fuel element portions are arranged at equal intervals in the circumferential direction, and the control rods 22 are arranged in the center so that they can be inserted. To be done. When the deformed plate-shaped fuel elements 1d are arranged in the radial direction as shown in FIG.
As can be seen from Fig. C, the convection (arrow) of the molten alloy fuel phase 3 and the molten salt phase 4 occurs in the fuel element 1d due to the temperature difference between the high temperature in the central part of the core and the slightly low temperature outside the core, causing melting. The slugging extraction reaction by the salt phase 4 can be efficiently performed.
第５図はこの発明による自己精製溶融金属燃料炉の概念
を説明するものであり、ＰｕおよびＵの合金燃料相３と
塩相４とガスプレナム５とを含む燃料要素１の複数本を
液体ナトリウム２１で満たされた炉心容器２０内に装荷
し、600〜700℃の運転温度で合金燃料相３は溶融状態で
燃焼する。燃焼により発生した熱はナトリウム循環系２
３を介して蒸気発生器２４へ導かれ、ここで生成された
蒸気２５によりタービン２６が駆動される。この間、合
金燃料３の燃焼により生成したＦＰのうちの希土類，ア
ルカリ土類，アルカリ金属等は、燃焼中に溶融塩相４に
抽出され（矢印Ｙ）、一方白金属のＦＰは合金燃料相３
に残る。燃料の燃焼が終了した時点で炉から使用済燃料
要素１１を取り出し、冷却して溶融状態の両相を固化し
たのち、ＦＰを多量に含む塩相１４とＦＰが多量に除去
された合金燃料相１３とを剪断して分離する。ＦＰを多
量に含む塩相１４は核分裂ガスが満たされているガスプ
レナム１５とともに廃棄するか、あるいは塩相１４を精
製して塩のみ再利用し、一方合金燃料相１３は精製して
白金属ＦＰを除去して、Ｐｕを回収するためには、以下
に説明するような種々の方法が考えられる。FIG. 5 illustrates the concept of a self-refining molten metal fuel reactor according to the present invention, in which a plurality of fuel elements 1 including an alloy fuel phase 3 of Pu and U, a salt phase 4 and a gas plenum 5 are provided with liquid sodium 21. The alloy fuel phase 3 is loaded into the core vessel 20 filled with the fuel and the alloy fuel phase 3 burns in a molten state at an operating temperature of 600 to 700 ° C. The heat generated by combustion is the sodium circulation system 2
3 is led to the steam generator 24, and the turbine 26 is driven by the steam 25 generated here. During this period, rare earths, alkaline earths, alkali metals, etc. of the FP generated by the combustion of the alloy fuel 3 are extracted into the molten salt phase 4 during the combustion (arrow Y), while the white metal FP is the alloy fuel phase 3
Remain in. After the combustion of the fuel is completed, the spent fuel element 11 is taken out of the furnace, cooled to solidify both phases in a molten state, and then a salt phase 14 containing a large amount of FP and an alloy fuel phase in which a large amount of FP is removed. 13 and 13 are sheared and separated. The salt phase 14 containing a large amount of FP is discarded together with the gas plenum 15 which is filled with the fission gas, or the salt phase 14 is purified and only the salt is reused, while the alloy fuel phase 13 is purified to produce white metal FP. In order to remove Pu and recover Pu, various methods as described below can be considered.
(1)剪断・炉外電解精製法（第６図） 剪断により塩相１４と分離された使用済合金燃料相１３
（Ｐｕ，Ｂｉ，白金属ＦＰを含む）を、原子炉外に設置
された溶融電解精製炉３０にて溶融電解し、Ｐｕを還元
精製して電極３１に金属Ｐｕを折出せしめる。得られた
Ｐｕは再びＢｉ等と合金化し、溶融してインジェクショ
ン・キャスティングにより燃料に成形し、塩とともに燃
料要素１に組み立てられる。(1) Shearing / external furnace electrorefining method (Fig. 6) Spent alloy fuel phase 13 separated from salt phase 14 by shearing
(Including Pu, Bi, and white metal FP) is melt-electrolyzed in a melting electrolytic refining furnace 30 installed outside the nuclear reactor, and Pu is reduced and refined to cause metal Pu to be extruded on the electrode 31. The obtained Pu is alloyed with Bi and the like again, melted and molded into a fuel by injection casting, and assembled into a fuel element 1 together with a salt.
(2)剪断・溶融精製法（第７図） 剪断により塩相１４と分離された使用済合金燃料相１３
を原子炉外に設置された溶融処理タンク４０に入れて溶
融する。この際、溶融温度をコントロールすることによ
って、Ｐｕと白金属ＦＰ例えばＲｈとの溶融度の違いを
利用して、Ｒｈを例えばＢｉとの金属間化合物Ｂｉ２Ｒ
ｈやＢｉ４Ｒｈとして折出させることができる。かくし
て溶融処理タンク４０から液相を取り出すことによって
Ｒｈ含有率の低いＰｕ−Ｂｉ合金を得ることができる。
一方、折出物として取り出した金属間化合物からは要す
ればＲｈ等の白金属を回収することができる。(2) Shearing / melting refining method (Fig. 7) Spent alloy fuel phase 13 separated from salt phase 14 by shearing
Is placed in a melting treatment tank 40 installed outside the nuclear reactor and melted. At this time, by controlling the melting temperature, the difference in the melting degree between Pu and the white metal FP such as Rh is utilized to make Rh an intermetallic compound Bi 2 R with Bi.
It can be projected as h or Bi 4 Rh. Thus, by extracting the liquid phase from the melt processing tank 40, a Pu-Bi alloy having a low Rh content can be obtained.
On the other hand, if necessary, white metal such as Rh can be recovered from the intermetallic compound taken out as a protrusion.
(3)電解精製機構付き燃料要素を用いる方法（第８図） 予め各燃料要素１に電極７とリード線８とからなる電解
精製機構を装着しておく。合金燃料相３の燃焼中には、
希土類，アルカリ土類，アルカリ金属等のＦＰが溶融塩
相４によって抽出される。燃焼後は、原子炉を停止した
のち燃料要素１を炉心内に設置したまま各燃料要素１の
電解精製機構７，８に通電することによってＰｕを還元
精製し、各電極７に金属Ｐｕを折出せしめる。(3) Method of using fuel element with electrolytic refining mechanism (FIG. 8) An electrolytic refining mechanism including electrodes 7 and lead wires 8 is attached to each fuel element 1 in advance. During combustion of alloy fuel phase 3,
FPs such as rare earths, alkaline earths and alkali metals are extracted by the molten salt phase 4. After the combustion, after stopping the reactor, the fuel element 1 is installed in the core and the electrolytic refining mechanisms 7 and 8 of each fuel element 1 are energized to reduce and purify Pu, and the metal Pu is broken at each electrode 7. Give it out.
次いで使用済燃料要素１１を炉心から取り出し、塩相１
４と合金燃料相１３とを剪断して分離したのち、電極７
を含む塩相１４をガスプレナム部１５とともに溶融タン
ク５０に入れて600〜700℃に加熱し、塩相１４のみを溶
融して金属Ｐｕを回収する。回収したＰｕは再びＢｉ等
と合金化されて燃料に成形され、塩とともに燃料要素に
組み立てられる。Then, the spent fuel element 11 is taken out from the core, and the salt phase 1
4 and the alloy fuel phase 13 are sheared and separated, and then the electrode 7
The salt phase 14 containing P is put into the melting tank 50 together with the gas plenum 15 and heated to 600 to 700 ° C., and only the salt phase 14 is melted to recover metallic Pu. The recovered Pu is alloyed again with Bi and the like to be molded into a fuel, which is then assembled with the salt into a fuel element.
使用済合金燃料相から白金属ＦＰを除去してＰｕを回収
するためには上述したごとき種々の方法が採用できる
が、場合によっては、使用済合金燃料相に残留する白金
属ＦＰを除去することなく、そのまま使用済合金燃料相
を溶融して燃料に成形し、新燃料として再利用してもよ
い。なぜならば、この発明の自己精製炉によれば、放射
能の大部分を占める希土類，アルカリ土類，アルカリ金
属といったＦＰは燃焼中の燃料要素内で溶融塩相によっ
て抽出，除去されているため、この塩相を剪断により除
去すれば、使用済合金燃料相をそのままリサイクルして
も放射能に関する問題はあまりないからである。Although various methods as described above can be adopted to remove the white metal FP from the spent alloy fuel phase and recover Pu, in some cases, the white metal FP remaining in the spent alloy fuel phase can be removed. Alternatively, the spent alloy fuel phase may be directly melted and shaped into a fuel, and reused as a new fuel. Because, according to the self-refining furnace of the present invention, FPs such as rare earths, alkaline earths, and alkali metals that account for most of the radioactivity are extracted and removed by the molten salt phase in the burning fuel element. This is because if this salt phase is removed by shearing, there will not be many problems regarding radioactivity even if the spent alloy fuel phase is recycled as it is.
第９図は、この発明の自己精製溶融金属燃料炉と使用済
燃料要素の処理とを組み合せた１つのシステムの例を示
すものである。すなわち、この発明の自己精製溶融金属
燃料炉の炉心容器２０で燃焼中の燃料要素から発生した
熱は一次ナトリウム系23aによって中間熱交換器２７へ
取り出され、ここで二次ナトリウム系２３ｂと熱交換
し、この二次ナトリウム系23bにより蒸気発生器２４に
て蒸気２５が精製され、この蒸気によりタービン２６が
駆動されて発電がなされる。FIG. 9 shows an example of one system combining the self-refining molten metal fuel furnace of the present invention with the treatment of spent fuel elements. That is, the heat generated from the fuel element burning in the core vessel 20 of the self-refining molten metal fuel reactor of the present invention is taken out to the intermediate heat exchanger 27 by the primary sodium system 23a, where it is exchanged with the secondary sodium system 23b. Then, the steam 25 is purified by the steam generator 24 by the secondary sodium system 23b, and the turbine 26 is driven by this steam to generate electricity.
一方、炉心においては例えば第１Ａ図に示したごとき燃
料要素１内部で溶融状態の合金燃料相が燃焼し、このと
き精製する核分裂ガスは燃料要素内のガスプレナムに集
められ、ＦＰのうち希土類，アルカリ土類，アルカリ金
属々は溶融塩相ヘスラッギング抽出反応により抽出さ
れ、溶融合金燃料相中には白金属ＦＰが残留する。燃焼
が進んだ燃料要素は炉心から取り出し、例えば第７図の
剪断・溶融精製法により再処理を行なう。すなわち取り
出した燃料要素１１内部の溶融相を固化したのち、剪断
して塩相１４と合金燃料相１３とに分離する。塩相１４
は精製後塩のみを分離して燃料加工工程へリサイクルし
て再利用する。一方、合金燃料相１３は、溶融処理タン
ク４０にて溶融して析出物（白金属ＦＰの金属間化合
物）と液相（Ｐｕ，Ｂｉ）とに分離し、液相のみをＰｕ
合金として燃料加工工程へリサイクルする。なお、溶融
処理タンク４０における熱源は、炉心から高温液体ナト
リウムを溶融処理タンク外周に循環２８させて得ること
により、エネルギーの有効利用を図ることができる。On the other hand, in the core, for example, the molten alloy fuel phase burns inside the fuel element 1 as shown in FIG. 1A, and the fission gas to be purified at this time is collected in the gas plenum in the fuel element, and rare earth and alkali in FP are contained. The earth and alkali metals are extracted by the molten salt phase hesslagging extraction reaction, and the white metal FP remains in the molten alloy fuel phase. The burned fuel element is taken out of the core and reprocessed by, for example, the shearing / melting refining method shown in FIG. That is, after the molten phase inside the taken out fuel element 11 is solidified, it is sheared and separated into a salt phase 14 and an alloy fuel phase 13. Salt phase 14
After refining, only the salt is separated and recycled to the fuel processing process for reuse. On the other hand, the alloy fuel phase 13 is melted in the melting treatment tank 40 and separated into a precipitate (intermetallic compound of white metal FP) and a liquid phase (Pu, Bi), and only the liquid phase is Pu.
It is recycled as an alloy into the fuel processing process. The heat source in the melt processing tank 40 is obtained by circulating 28 the high temperature liquid sodium from the core to the outer periphery of the melt processing tank, so that the energy can be effectively used.
燃料加工工程においては、インジェクション・キャステ
ィング等により合金燃料相と塩相とを燃料被覆内に封入
し、新たな燃料要素１に組み立て、新燃料として炉心に
装荷する。In the fuel processing step, the alloy fuel phase and the salt phase are enclosed in the fuel cladding by injection casting or the like, assembled into a new fuel element 1, and loaded as a new fuel in the core.
上述の説明からも理解できるように、この発明の自己精
製溶融金属燃料炉は、単なる原子炉として使用されるも
のではなく、使用済燃料のリサイクルをも含めたリサイ
クリング・クローズド・システムを構成する原子炉とし
て使用する点に特に意義のあるものである。炉から取り
出したのちの使用済燃料の処理はセル内で遠隔操作で行
なえるため、除染係数の高い精製を必ずしも必要としな
い。As can be understood from the above description, the self-refining molten metal fuel reactor of the present invention is not simply used as a nuclear reactor, but constitutes a recycling closed system including recycling of spent fuel. It is of particular significance in its use as a nuclear reactor. Since the spent fuel after being taken out from the furnace can be remotely controlled in the cell, it does not necessarily require purification with a high decontamination coefficient.
〈発明の効果〉 この発明は上述したごとき構成の自己精製溶融金属燃料
炉であるから、炉特性として次のような利点がある。<Effects of the Invention> Since the present invention is a self-refining molten metal fuel furnace having the above-described configuration, it has the following advantages as furnace characteristics.
i)燃料は溶融状態で燃焼するため、ペレット燃料でみら
れるようなペレット−被覆機械的相互作用（ＰＣＭＩ）
や燃料溶融の問題がない。i) Pellet-clad mechanical interactions (PCMI), as seen in pellet fuels, because the fuel burns in the molten state.
There is no problem of fuel melting.
ii)炉心内の液体ナトリウム中でボイドが発生する前
に、燃料要素内の溶融合金燃料相中でボイドが発生する
ため、負の反応度を有する。ii) It has a negative reactivity because the voids are generated in the molten alloy fuel phase in the fuel element before the voids are generated in the liquid sodium in the core.
iii)燃料は溶融状態の液体であるため温度に対する膨張
が大きく、出力上昇に対して負の反応度を有する。iii) Since the fuel is a liquid in a molten state, it expands greatly with respect to temperature and has a negative reactivity with respect to an increase in output.
iv)燃料が液体であるため熱伝導性がよく、その結果過
度に高温になる危険がない。iv) Since the fuel is liquid, it has good thermal conductivity, and as a result, there is no danger of excessively high temperatures.
v)燃料が液体であるため、燃料物質が常に均一になり反
応度の偏在を考えなくてよい。v) Since the fuel is a liquid, the fuel substance is always uniform and it is not necessary to consider uneven distribution of reactivity.
一方、この発明の原子炉で使用した使用済燃料の再処理
の観点からは次のような利点がある。On the other hand, from the viewpoint of reprocessing spent fuel used in the nuclear reactor of the present invention, there are the following advantages.
i)希土類，アルカリ土類，アルカリ金属のＦＰを、燃焼
中に合金燃料相から溶融塩相へ抽出，除去するため、炉
から使用済燃料要素を取り出したのち、塩相を切り離す
だけで、これらのＦＰを合金燃料相から除去することが
できる。i) In order to extract and remove FPs of rare earths, alkaline earths and alkali metals from the alloy fuel phase to the molten salt phase during combustion, simply remove the spent fuel element from the furnace and then disconnect the salt phase. Of FP can be removed from the alloy fuel phase.
ii)蒸気のように、大部分のＦＰが合金燃料相から除去
されているため、燃料再処理プロセスを簡略化できる。ii) Most of the FP, like steam, has been removed from the alloy fuel phase, thus simplifying the fuel reprocessing process.
iii)白金属ＦＰは合金燃料相に残るので、この合金燃料
相から白金属金属を回収することも可能である。iii) Since the white metal FP remains in the alloy fuel phase, it is also possible to recover the white metal from this alloy fuel phase.
iv)燃料の燃焼中に精製する核分裂ガスは、燃料要素内
のガスプレナムに全て集められているため、再処理プロ
セスでは核分裂ガスの処理が簡略化できる。iv) The fission gas that is purified during the combustion of the fuel is all collected in the gas plenum within the fuel element, so the reprocessing process can simplify the treatment of the fission gas.
v)燃料再処理プロセスにおいて溶融処理が必要な場合に
は、炉の高温液体ナトリウムの熱を利用すればエネルギ
ーの有効利用が図れ、第９図のごときリサイクリング・
クローズド・システムも可能となる。v) When the melting process is required in the fuel reprocessing process, the heat of the high temperature liquid sodium in the furnace can be used to effectively use the energy.
A closed system is also possible.
第１Ａ図および第１Ｂ図は、この発明で使用する燃料要
素の第１実施例を示す斜視図および炉心配置例の平面
図、第２Ａ図および第２Ｂ図は燃料要素の第２実施例を
示す斜視図および炉心配置例の平面図、第３図は燃料要
素の第３実施例を示す斜視図、第４Ａ図および第４Ｂ図
は燃料要素の第４実施例を示す斜視図および炉心配置例
の平面図、第４Ｃ図は第４Ａ図に示す燃料要素内の溶融
状態を示す断面図、第５図はこの発明の原子炉の概念を
示す説明図、第６図，第７図および第８図は使用済燃料
要素からのＰｕ回収法の第１実施例，第２実施例をおよ
び第３実施例を示す説明図、第９図はこの発明の原子炉
と使用済燃料要素再処理とを組み合せたシステムの一例
を示す説明図である。 １，１ａ，１ｂ，１ｃ，１ｄ…燃料要素、３…合金燃料
相、４…塩相、５…ガスプレナム、２０…炉心容器、２
１…液体ナトリウム。1A and 1B are a perspective view showing a first embodiment of a fuel element used in the present invention and a plan view of a core arrangement example, and FIGS. 2A and 2B show a second embodiment of the fuel element. FIG. 3 is a perspective view showing a plan view of an example of core arrangement, FIG. 3 is a perspective view showing a third example of a fuel element, and FIGS. 4A and 4B are perspective views showing a fourth example of fuel elements and an example of core arrangement. FIG. 4C is a plan view, FIG. 4C is a cross-sectional view showing a molten state in the fuel element shown in FIG. 4A, and FIG. 5 is an explanatory view showing the concept of the nuclear reactor of the present invention, FIG. 6, FIG. 7, and FIG. Is an explanatory view showing the first embodiment, the second embodiment and the third embodiment of the Pu recovery method from the spent fuel element, and FIG. 9 shows the combination of the reactor of the present invention and the spent fuel element reprocessing. It is explanatory drawing which shows an example of the system. 1, 1a, 1b, 1c, 1d ... Fuel element, 3 ... Alloy fuel phase, 4 ... Salt phase, 5 ... Gas plenum, 20 ... Core vessel, 2
1 ... Liquid sodium.
───────────────────────────────────────────────────── フロントページの続き 特許法第30条第１項適用申請有り 「原子力産業新 聞」，昭和62年７月16日，社団法人原子力産業会議 (72)発明者 鈴木 惣十 茨城県東茨城郡大洗町成田町4002番地 動 力炉・核燃料開発事業団大洗工学センター 内 ─────────────────────────────────────────────────── ─── Continuation of the front page Application for application of Article 30 (1) of the Patent Act “Nuclear Industry News,” July 16, 1987, Nuclear Industry Conference (72) Inventor Sōju Suzuki Ibaraki Higashi Ibaraki 4002 Narita-cho, Oarai-gun, Gunma Oarai Engineering Center, Reactor and Nuclear Fuel Development Corporation
Claims (1)
の燃料要素を配設してなる原子炉において、各燃料要素
の内部には、原子炉運転温度で溶融する低融点プルトニ
ウムおよび／またはウラン合金燃料相と低融点塩相とガ
スプレナムとがこの順で下層から上層へ向けて形成され
ており、これによって原子炉運転中は溶融状態で該合金
燃料相が燃焼し、このとき発生する核分裂ガスは該ガス
プレナムに集められ、また核分裂生成物の一部は溶融状
態の塩相へ移行し、もって該燃料要素内の合金燃料に自
己精製機能をもたせるようにしたことを特徴とする自己
精製溶融金属燃料炉。1. A nuclear reactor having a plurality of fuel elements arranged in a core, using liquid metal as a coolant, wherein each fuel element has a low melting point plutonium and / or a melting point which melts at a reactor operating temperature. A uranium alloy fuel phase, a low melting point salt phase, and a gas plenum are formed in this order from the lower layer to the upper layer, which causes the alloy fuel phase to burn in a molten state during the reactor operation, and the fission that occurs at this time The gas is collected in the gas plenum, and a part of the fission products is transferred to a salt phase in a molten state, so that the alloy fuel in the fuel element has a self-refining function. Metal fuel furnace.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62189546A JPH067179B2 (en) | 1987-07-29 | 1987-07-29 | Self-refining molten metal fuel furnace |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP62189546A JPH067179B2 (en) | 1987-07-29 | 1987-07-29 | Self-refining molten metal fuel furnace |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6432189A JPS6432189A (en) | 1989-02-02 |
| JPH067179B2 true JPH067179B2 (en) | 1994-01-26 |
Family
ID=16243123
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP62189546A Expired - Fee Related JPH067179B2 (en) | 1987-07-29 | 1987-07-29 | Self-refining molten metal fuel furnace |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH067179B2 (en) |
Families Citing this family (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP4625299B2 (en) * | 2004-09-28 | 2011-02-02 | 白川 利久 | Radiant heat type nuclear power plant |
| US20150228361A1 (en) * | 2011-12-21 | 2015-08-13 | Alexander Potemkin | Converter Reactor for Thermal Neutrons |
| JP2014010022A (en) * | 2012-06-29 | 2014-01-20 | Hitachi-Ge Nuclear Energy Ltd | Fuel assembly, and nuclear reactor core |
| GB201318470D0 (en) | 2013-02-25 | 2013-12-04 | Scott Ian R | A practical molten salt fission reactor |
| JP6409161B2 (en) * | 2013-11-26 | 2018-10-24 | 株式会社 トリウムテックソリューション | Molten salt nuclear fuel module |
| JP2016042090A (en) * | 2014-08-18 | 2016-03-31 | 株式会社 トリウムテックソリューション | Compact size molten salt reactor |
| CN107195350B (en) * | 2017-06-08 | 2023-03-28 | 兰州大学 | Device for capturing radioactive fission gas |
| JP6901388B2 (en) | 2017-12-13 | 2021-07-14 | 日立Ｇｅニュークリア・エナジー株式会社 | Fuel elements of fast reactors and cores of fast reactors |
| JP7138082B2 (en) * | 2019-06-12 | 2022-09-15 | 日立Ｇｅニュークリア・エナジー株式会社 | fast reactor fuel assembly and fast reactor core |
-
1987
- 1987-07-29 JP JP62189546A patent/JPH067179B2/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6432189A (en) | 1989-02-02 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Laidler et al. | Development of pyroprocessing technology | |
| KR102166205B1 (en) | A practical molten salt fission reactor | |
| Chang | The integral fast reactor | |
| US5774514A (en) | Energy amplifier for nuclear energy production driven by a particle beam accelerator | |
| JP6220329B2 (en) | Particulate metal fuel used in power generation, recycling system, and small modular reactor | |
| CN110444311A (en) | Method of Transmutation of Transuranic Elements in Liquid Molten Salt Reactor | |
| JPH067179B2 (en) | Self-refining molten metal fuel furnace | |
| Laidler et al. | Development of IFR pyroprocessing technology | |
| JPH03123896A (en) | Recovery of actinides | |
| WO1997047015A1 (en) | Accelerator-driven transmutation of spent fuel elements | |
| RU2173484C1 (en) | Fast reactor using heavy liquid-metal coolant | |
| JP3735392B2 (en) | Reprocessing of spent fuel | |
| RU2079909C1 (en) | Method of nuclear fuel pyrochemical regeneration | |
| RU2741330C1 (en) | Autonomous nuclear power plant | |
| Burris et al. | Proposed pyrometallurgical process for rapid recycle of discharged fuel materials from the integral fast reactor | |
| JPH08122487A (en) | Reprocessing method of spent fuel and elimination method of long half-life element | |
| Battles et al. | Pyrometallurgical processes for recovery of actinide elements | |
| JP7136449B2 (en) | Plutonium extinction molten salt reactor, power generation system using the same, and operation method of plutonium extinction molten salt reactor | |
| Till et al. | Evolution of the liquid metal reactor: the Integral Fast Reactor (IFR) concept | |
| RU2122750C1 (en) | Nuclear power system operating process | |
| Cheng | A flibe based actinide transmutation blanket | |
| Takano et al. | A concept of nitride fuel actinide recycle system based on pyrochemical reprocessing | |
| RU2344500C2 (en) | Nuclear reactor with fissible region representing salt melt | |
| Miller et al. | Choice of pyroprocess for integral fast reactor fuel | |
| RU97116939A (en) | METHOD FOR OPERATING A NUCLEAR ENERGY COMPLEX |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| LAPS | Cancellation because of no payment of annual fees |