JPS6385400A - Fast breeder reactor - Google Patents
Fast breeder reactorInfo
- Publication number
- JPS6385400A JPS6385400A JP61231724A JP23172486A JPS6385400A JP S6385400 A JPS6385400 A JP S6385400A JP 61231724 A JP61231724 A JP 61231724A JP 23172486 A JP23172486 A JP 23172486A JP S6385400 A JPS6385400 A JP S6385400A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- fuel
- fuel storage
- damaged
- damaged fuel
- 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.)
- Pending
Links
- 239000000446 fuel Substances 0.000 claims description 72
- 239000002826 coolant Substances 0.000 claims description 13
- 239000003758 nuclear fuel Substances 0.000 claims description 6
- 238000009792 diffusion process Methods 0.000 description 9
- 230000002265 prevention Effects 0.000 description 9
- 238000001816 cooling Methods 0.000 description 4
- 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 3
- 230000004992 fission Effects 0.000 description 3
- 229910052708 sodium Inorganic materials 0.000 description 3
- 239000011734 sodium Substances 0.000 description 3
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 2
- 230000004308 accommodation Effects 0.000 description 2
- 239000011261 inert gas Substances 0.000 description 2
- 229910052786 argon Inorganic materials 0.000 description 1
- 230000002238 attenuated effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 229910001338 liquidmetal Inorganic materials 0.000 description 1
- 230000029058 respiratory gaseous exchange Effects 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Abstract] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
［発明の目的］
（産業上の利用分野）
本発明は高速増殖炉に係り、特に高速増殖炉の炉内燃料
貯蔵設備の溝造に関する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Field of Application) The present invention relates to a fast breeder reactor, and more particularly to the trench structure of an in-core fuel storage facility of a fast breeder reactor.
（従来の技術）
一般に高速増殖炉はナトリウム等の液体金属を冷却材と
して使用するため、原子炉容器内を密閉した状態で燃料
交換を行う。従来の高速増殖炉における燃料交換は、第
７図に示すように交換しようとする燃料を燃料交換機３
の操作により炉心２から炉心２の周囲に設けられた炉内
燃料貯蔵ラック４に移し、ここで崩壊熱レベルを低下さ
せ、次回の燃料交換まで貯蔵する。一方、前回の燃料交
換時に炉内燃料貯蔵ラック４に貯蔵された燃料は、燃料
出入れ１ｆ１５により原子炉容器１内から取出され、炉
外中継槽６へ移される。そして、付着ナトリウムの反応
を防ぐために直ちにドライセル（不活性ガス雰囲気に保
持された小室）７内に設けられたインセルクレーン８に
よって図示しない使用済燃料貯蔵設備へ移送される。ま
た、燃料交換中に炉内で破損燃料が検出された場合は燃
料出入れ機５により直ちに原子炉容器１内から取出し、
ドライセルフ内の破損燃料貯蔵槽９に貯蔵される。(Prior Art) Since fast breeder reactors generally use liquid metal such as sodium as a coolant, fuel exchange is performed with the inside of the reactor vessel sealed. In conventional fast breeder reactor fuel exchange, the fuel to be exchanged is transferred to a fuel exchanger 3 as shown in FIG.
Through this operation, the fuel is transferred from the reactor core 2 to the in-core fuel storage rack 4 provided around the reactor core 2, where the decay heat level is lowered and stored until the next fuel exchange. On the other hand, the fuel stored in the in-core fuel storage rack 4 at the time of the previous fuel exchange is taken out from inside the reactor vessel 1 by the fuel inlet/output 1f15 and transferred to the out-of-core relay tank 6. Then, in order to prevent the adhering sodium from reacting, it is immediately transferred to a spent fuel storage facility (not shown) by an in-cell crane 8 installed in a dry cell (a small chamber maintained in an inert gas atmosphere) 7. In addition, if damaged fuel is detected in the reactor during fuel exchange, it is immediately removed from the reactor vessel 1 by the fuel loading/unloading machine 5.
The damaged fuel is stored in the damaged fuel storage tank 9 in the dry cell.
このように従来の高速増殖炉では破損燃料からの核分裂
生成物が炉内に拡散されるおそれがあるため、破損燃料
を検出すると直ちに原子炉容器１内から取出し、炉外に
設けられた専用の貯蔵設備に貯蔵していた。このため、
燃料取扱設備の物量及び配置スペースが増大するという
欠点があった。As described above, in conventional fast breeder reactors, there is a risk that fission products from the damaged fuel will diffuse into the reactor. It was stored in a storage facility. For this reason,
This has the disadvantage that the quantity and space for the fuel handling equipment increases.
（発明が解決しようとする問題点）
従来の高速増殖炉は上述したように破損燃料に対する専
用の貯蔵設備や崩壊熱冷却系設備を必要するため、燃料
取扱設備の物量及び配置スペースが増大するという欠点
があった。(Problems to be Solved by the Invention) As mentioned above, conventional fast breeder reactors require dedicated storage equipment for damaged fuel and decay heat cooling system equipment, which increases the amount and installation space of fuel handling equipment. There were drawbacks.
本発明の目的はかかる問題点を解決し、燃料取扱設備の
簡素化を図るとともに、破損燃料を炉内に貯蔵しても核
分裂生成物が炉内に拡散されるおそれのない高速増殖炉
を提供することにある。The purpose of the present invention is to solve such problems, simplify fuel handling equipment, and provide a fast breeder reactor in which there is no risk of fission products being diffused into the reactor even if damaged fuel is stored in the reactor. It's about doing.
［発明の構成］
（問題点を解決するための手段）
上記目的を達成するために本発明は、炉内燃料貯蔵ラッ
クの一部に破損燃料収容ポットを着脱可能に設置し、こ
の破損燃料収容ポットの周囲に中性子遮蔽体を設けると
ともに、中性子遮蔽体と破損燃料収容ポットとの間に冷
却材流路を形成したことを特徴としている。[Structure of the Invention] (Means for Solving the Problems) In order to achieve the above object, the present invention includes a damaged fuel storage pot that is removably installed in a part of the in-reactor fuel storage rack. It is characterized in that a neutron shield is provided around the pot, and a coolant flow path is formed between the neutron shield and the damaged fuel storage pot.
（作 用）
すなわち、本発明では前記冷却材流路を流れる冷却材に
よって破損燃料収容ポットを強制冷却することにより破
損燃料収容ポット内に収容された破損燃料の崩壊熱を除
去することができる。(Function) That is, in the present invention, the decay heat of the damaged fuel accommodated in the damaged fuel accommodation pot can be removed by forcibly cooling the damaged fuel accommodation pot with the coolant flowing through the coolant flow path.
（実 施 例）
以下、第１図乃至第５図を参照して本発明の一実施例に
ついて説明する。第１図は本発明による高速増殖炉の断
面図で、図中符号１０１は原子炉容器である。この原子
炉容器１０１の内部には炉心１０２が設けられ、冷却材
１０３中に浸漬されている。そして、原子炉容器１０１
の上部開口は遮蔽プラグ１０４によって閉塞され、この
遮蔽プラグ１０４と冷却材１０３液面との間に形成され
た空間部にはアルゴンガス等の不活性ガスが封入されて
いる。前記遮蔽プラグ１０４は固定プラグ１０５と回転
プラグ１０６からなり、固定プラグ１０５には中間熱交
換器１０７および循環ボン′ブ１０８が搭載されている
。また回転プラグ１０６には制御棒駆動機構１０９およ
び燃料交換機（図示せず）等が搭載され、上記制御棒駆
動機構１０９で制御棒（図示せず）を上下動させて炉心
１０２の出力を制御するように構成されている。(Embodiment) An embodiment of the present invention will be described below with reference to FIGS. 1 to 5. FIG. 1 is a sectional view of a fast breeder reactor according to the present invention, and reference numeral 101 in the figure is a reactor vessel. A reactor core 102 is provided inside this reactor vessel 101 and is immersed in a coolant 103 . And reactor vessel 101
The upper opening of the coolant 103 is closed by a shielding plug 104, and an inert gas such as argon gas is filled in a space formed between the shielding plug 104 and the liquid level of the coolant 103. The shielding plug 104 consists of a fixed plug 105 and a rotating plug 106, and the fixed plug 105 is equipped with an intermediate heat exchanger 107 and a circulation bomb 108. The rotary plug 106 is also equipped with a control rod drive mechanism 109, a fuel exchanger (not shown), etc., and the control rod drive mechanism 109 moves the control rods (not shown) up and down to control the output of the reactor core 102. It is configured as follows.
なお、図中１１０は原子炉容器１０１を保護するための
ガードベッセル、１１１は循環ポンプ１０８より吐出さ
れた冷却材１０３を炉心１０２の下方に設けられた高圧
プレナムへ供給するための炉内配管である。In the figure, 110 is a guard vessel for protecting the reactor vessel 101, and 111 is in-reactor piping for supplying the coolant 103 discharged from the circulation pump 108 to the high-pressure plenum provided below the reactor core 102. be.
また、前記炉心１０２の周囲には炉内燃料貯蔵ラック１
１２が設けられている。この炉内燃料貯蔵ラック１１２
は、第２図に示すように燃料交換時に炉心１０２から取
出された燃料１１３を一時的に貯蔵しておくためのもの
で、高圧プレナム１１４から減圧装置１１５を介してサ
ブプレナム１１６に流入した冷却材１０３によって燃料
１１３の崩壊熱を除去する構造となっている。まま
た、炉内燃料貯蔵ラック１１牛の外側には破損燃料１１
７を収容するための破損燃料収容ポット１１８が着脱可
能に設置されている。この破損燃料収容ポット１１８は
周囲を中性子遮蔽体１１９で囲まれており、中性子遮蔽
体１１９と破損燃料収容ポット１１８との間には同ポッ
ト１１８を強制冷却するための冷却材流路が形成されて
いる。Further, an in-core fuel storage rack 1 is provided around the core 102.
12 are provided. This in-core fuel storage rack 112
As shown in FIG. 2, this is for temporarily storing the fuel 113 taken out from the core 102 during fuel exchange, and coolant flowing from the high-pressure plenum 114 to the sub-plenum 116 via the pressure reducing device 115. 103 removes the decay heat of the fuel 113. Also, there is damaged fuel 11 on the outside of the fuel storage rack 11 inside the reactor.
A damaged fuel storage pot 118 for accommodating 7 is removably installed. This damaged fuel storage pot 118 is surrounded by a neutron shield 119, and a coolant flow path is formed between the neutron shield 119 and the damaged fuel storage pot 118 to forcibly cool the pot 118. ing.
前記破損燃料収容ポット１１８は第３図乃至第５図に示
すように有底円筒状のポット本体１２０と拡散防止１１
２１より構成され、ポット本体１２０の上端部には破損
燃料収容ポット１１８を燃料交換機のグリッパでつかむ
ためのハンドリングヘッド１２２が設けられている。ま
た、拡散防止蓋１２１には拡散防止蓋１２１を開閉させ
るための開閉突起１２３とナトリウム呼吸孔１２４が設
けられている。なお、前記ハンドリングヘッド１２２に
は拡散防止蓋１２１を開くときに拡散防止蓋１２１が破
損燃料収容ポット１１８の外筒に干渉しないように切欠
部１２５が設けられている。As shown in FIGS. 3 to 5, the damaged fuel storage pot 118 has a bottomed cylindrical pot body 120 and a diffusion prevention 11.
21, and a handling head 122 is provided at the upper end of the pot body 120 for gripping the damaged fuel storage pot 118 with a gripper of the fuel exchanger. Further, the diffusion prevention lid 121 is provided with an opening/closing protrusion 123 and a sodium breathing hole 124 for opening and closing the diffusion prevention lid 121. Note that a notch 125 is provided in the handling head 122 so that the diffusion prevention lid 121 does not interfere with the outer cylinder of the damaged fuel storage pot 118 when the diffusion prevention lid 121 is opened.
次にこのように構成された本実施例の作用について説明
する。燃料交換中に破損燃料１１７を検出した場合は、
先ず図示しない燃料交換纏のグリッパを破損燃料収容ポ
ット１１８のハンドリングヘッド１２２に位胃決めし、
グリッパを切欠部１２５の方向に水平移動させてグリッ
パの先端で開閉突起１２３を介して拡散防止蓋１２１を
第３図の点線で示すように開放させる。次に破損燃料１
１７を燃料交換機のグリッパでつかみ、破損燃料収容ポ
ット１１８内に収容する。そして、上記と逆の手順で拡
散防止蓋１２１を閉じ、破損燃料１１７を次回の燃料交
換まで破損燃料収容ポット１１８内に貯蔵する。Next, the operation of this embodiment configured as described above will be explained. If damaged fuel 117 is detected during fuel exchange,
First, the gripper of the fuel exchange bag (not shown) is placed on the handling head 122 of the damaged fuel storage pot 118, and
The gripper is moved horizontally in the direction of the notch 125, and the diffusion prevention lid 121 is opened at the tip of the gripper via the opening/closing protrusion 123 as shown by the dotted line in FIG. Next, damaged fuel 1
17 with the gripper of the refueling machine and accommodated in the damaged fuel storage pot 118. Then, the diffusion prevention lid 121 is closed in the reverse order to the above, and the damaged fuel 117 is stored in the damaged fuel storage pot 118 until the next fuel exchange.
このように破損燃料１１７を次回の燃料交換まで破損燃
料収容ポット１１８内に貯蔵することにより、破損燃料
収容ポット１１８と中性子遮蔽体１１７との間に形成さ
れた冷却材流路を流れる冷却材１０３が破損燃料収容ポ
ット１１８を強制冷却する役割を果たし、破損燃料１１
７の崩壊熱を除去することができる。従って、破損燃料
収容ポット１１８内に一定期間貯蔵された破損燃料１１
７を炉外より取出す際には十分に崩壊熱が減衰している
ので、破損燃料１１７に対する専用の貯蔵設備や崩壊熱
冷却系設備を省略することができる。また、本実施例で
は破損燃料１１７を破損燃料収容ポット１１８ごと炉外
へ取出すことができるので、炉内に核分裂生成物が拡散
されるおそれもない。なお、上記実施例では破損燃料収
容ポット１１８の上部に開閉自在な拡散防止Ｍ１２１を
設けたが、第６図に示すようにボールラッチ機構１２７
を有する拡散防止プラグ１２６を設けてもよい。By storing the damaged fuel 117 in the damaged fuel storage pot 118 until the next fuel exchange, the coolant 103 flows through the coolant flow path formed between the damaged fuel storage pot 118 and the neutron shield 117. plays the role of forcibly cooling the damaged fuel storage pot 118, and the damaged fuel storage pot 11
7 decay heat can be removed. Therefore, the damaged fuel 11 stored in the damaged fuel storage pot 118 for a certain period of time
Since the decay heat is sufficiently attenuated when fuel 117 is taken out from the outside of the furnace, it is possible to omit dedicated storage equipment and decay heat cooling system equipment for the damaged fuel 117. Further, in this embodiment, since the damaged fuel 117 can be taken out of the reactor together with the damaged fuel storage pot 118, there is no fear that fission products will be diffused into the reactor. In the above embodiment, a diffusion prevention M121 that can be opened and closed is provided on the upper part of the damaged fuel storage pot 118, but as shown in FIG.
A diffusion prevention plug 126 may be provided.
［発明の効果］
以上のように本発明によれば、破損燃料を炉内に安全に
貯蔵することができるので、燃料取扱設備の簡素化を図
ることができる。[Effects of the Invention] As described above, according to the present invention, damaged fuel can be safely stored in the furnace, and therefore fuel handling equipment can be simplified.
第１図乃至第５図は本発明の一実施例を示し、第１図は
高速増殖炉の断面図、第２図は炉内燃料貯蔵ラックの構
造を示す断面図、第３図は破損燃料収容ポットの構造を
示す断面図、第４図は同ポットの平面図、第５図は第３
図のｖ−■断面図、第６図は本発明の他の実施例を示す
破損燃料収容ポットの断面図、第７図は従来例を示す図
である。
１０１・・・原子炉容器、１０２・・・炉心、１０４・
・・遮蔽プラグ、１１２・・・炉内燃料貯蔵ラック、１
１８・・・破損燃料収容ポット。
出願人代理人 弁理士 鈴江武彦
第１図
第２図
第３図
第４図
第５図
第６図Figures 1 to 5 show an embodiment of the present invention, in which Figure 1 is a sectional view of a fast breeder reactor, Figure 2 is a sectional view showing the structure of an in-reactor fuel storage rack, and Figure 3 is a diagram showing damaged fuel. A sectional view showing the structure of the storage pot, Fig. 4 is a plan view of the pot, and Fig. 5 is a sectional view showing the structure of the storage pot.
FIG. 6 is a cross-sectional view of a damaged fuel storage pot showing another embodiment of the present invention, and FIG. 7 is a view showing a conventional example. 101... Reactor vessel, 102... Reactor core, 104...
... Shielding plug, 112 ... In-reactor fuel storage rack, 1
18...Damaged fuel storage pot. Applicant's Representative Patent Attorney Takehiko Suzue Figure 1 Figure 2 Figure 3 Figure 4 Figure 5 Figure 6
Claims (1)
前記原子炉容器の上部開口を閉塞する遮蔽プラグと、前
記炉心の周囲に設けられた炉内燃料貯蔵ラックと、この
炉内燃料貯蔵ラックの一部に着脱可能に設置された破損
燃料収容ポットと、この破損燃料収容ポットの周囲に設
けられた中性子遮蔽体と、この中性子遮蔽体と前記破損
燃料収容ポットとの間に形成された冷却材流路とを具備
したことを特徴とする高速増殖炉。A nuclear reactor vessel, a reactor core provided within this reactor vessel,
A shielding plug that closes an upper opening of the reactor vessel, an in-reactor fuel storage rack provided around the reactor core, and a damaged fuel storage pot that is removably installed in a part of the in-reactor fuel storage rack. A fast breeder reactor comprising: a neutron shield provided around the damaged fuel storage pot; and a coolant flow path formed between the neutron shield and the damaged fuel storage pot. .
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61231724A JPS6385400A (en) | 1986-09-30 | 1986-09-30 | Fast breeder reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61231724A JPS6385400A (en) | 1986-09-30 | 1986-09-30 | Fast breeder reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS6385400A true JPS6385400A (en) | 1988-04-15 |
Family
ID=16928030
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61231724A Pending JPS6385400A (en) | 1986-09-30 | 1986-09-30 | Fast breeder reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6385400A (en) |
-
1986
- 1986-09-30 JP JP61231724A patent/JPS6385400A/en active Pending
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