JPH02147996A - Gas storage facility of spent nuclear fuel - Google Patents
Gas storage facility of spent nuclear fuelInfo
- Publication number
- JPH02147996A JPH02147996A JP63300709A JP30070988A JPH02147996A JP H02147996 A JPH02147996 A JP H02147996A JP 63300709 A JP63300709 A JP 63300709A JP 30070988 A JP30070988 A JP 30070988A JP H02147996 A JPH02147996 A JP H02147996A
- Authority
- JP
- Japan
- Prior art keywords
- nuclear fuel
- spent nuclear
- porous body
- storage
- gas
- 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
- 239000002915 spent fuel radioactive waste Substances 0.000 title claims abstract description 22
- 239000007789 gas Substances 0.000 claims abstract description 20
- 239000000112 cooling gas Substances 0.000 claims abstract description 7
- 239000011800 void material Substances 0.000 abstract description 6
- 230000000712 assembly Effects 0.000 description 6
- 238000000429 assembly Methods 0.000 description 6
- 238000001816 cooling Methods 0.000 description 6
- 238000010586 diagram Methods 0.000 description 6
- 239000000446 fuel Substances 0.000 description 6
- 238000000034 method Methods 0.000 description 5
- 239000011148 porous material Substances 0.000 description 5
- 210000000352 storage cell Anatomy 0.000 description 4
- 230000000694 effects Effects 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- 238000005192 partition Methods 0.000 description 3
- 239000000428 dust Substances 0.000 description 2
- 230000004907 flux Effects 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 210000004027 cell Anatomy 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 239000011261 inert gas Substances 0.000 description 1
- 229910001338 liquidmetal Inorganic materials 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 230000001737 promoting effect Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 230000000630 rising effect Effects 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-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
- Fuel Cell (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
（産業上の利用分野）
本発明は使用済み原子燃料のガス中貯蔵設備、特に原子
燃料からの崩壊熱除去に関するものである。DETAILED DESCRIPTION OF THE INVENTION Field of the Invention The present invention relates to a spent nuclear fuel storage facility in gas, and in particular to the removal of decay heat from nuclear fuel.
（従来技術とその問題点）
再処理までの使用済み燃料の貯蔵方式として、使用済み
原子燃料集合物を除熱性の高い水、或いは液体金属中に
浸漬する方法が従来一般的に行われているが、最近これ
に代るものとして不活性ガス、空気などのガス中に貯蔵
する方法が提案されている。(Prior art and its problems) As a method of storing spent fuel until reprocessing, the conventional method of immersing spent nuclear fuel assemblies in water or liquid metal with high heat removal properties has been commonly used. However, recently, as an alternative to this, a method of storing it in a gas such as inert gas or air has been proposed.
これは例えば第１図に示すように所要厚のコンクリート
により形成された燃料貯蔵セル（１）中に通ずる、放射
性塵の除去フィルタ（２）、ガス冷却器（３）、循環用
プロア（４）などからなるガス冷却循環系を設けて、移
送機（５）によりセル（１）内の貯蔵ラック（６）、即
ち第２図に示す部分図のようにガス流路（６ａ）をそれ
ぞれ有する上下支持板（６ｂ）（６ｃ）および仕切板（
６ｄ）とからなる貯蔵ラック（６）に保持された原子燃
料（７）の周囲に、共通ガス通路（６ｅ）を介して下方
から上方に冷却ガス（８）を循環させる。そしてこの冷
却ガス流により使用済み原子燃料集合体（７）内に生じ
た崩壊熱をセル（１）外に運び去って安全に保管しよう
とするものである。For example, as shown in Figure 1, this includes a radioactive dust removal filter (2), a gas cooler (3), and a circulation proa (4) that lead into a fuel storage cell (1) made of concrete of a required thickness. A gas cooling circulation system consisting of a gas cooling circulation system such as Support plates (6b) (6c) and partition plates (
A cooling gas (8) is circulated from below to above via a common gas passageway (6e) around the nuclear fuel (7) held in a storage rack (6) consisting of 6d). The purpose is to transport the decay heat generated within the spent nuclear fuel assembly (7) out of the cell (1) by this cooling gas flow and safely store it.
この方式は液体による貯蔵方式と比較して設備の簡素化
を図りうろことなどから、合理的な貯蔵方式として注目
され、将来の導入が検討されている。This method has attracted attention as a rational storage method because it requires simpler equipment and scales compared to liquid storage methods, and its introduction in the future is being considered.
しかし周知のようにガスは液体に比較して除熱性能が劣
るため、使用済み原子燃料集合体（１）を貯蔵に安全な
温度に保つためには、それだけ容量の大きいガス冷却系
統を設けるか、冷却系統の容量に合わせて貯蔵すべき燃
料集合体（７）の数を少なくするなどの手段をとる必要
があり、それだけ貯蔵コストの増大を招く。However, as is well known, gas has inferior heat removal performance compared to liquid, so in order to keep the spent nuclear fuel assembly (1) at a safe temperature for storage, it is necessary to install a gas cooling system with a large capacity. Therefore, it is necessary to take measures such as reducing the number of fuel assemblies (7) to be stored in accordance with the capacity of the cooling system, which increases storage costs accordingly.
（発明の目的）
本発明は貯蔵セル内に簡単な手段を設けるのみで、貯蔵
能力の増大を図りうる使用済み原子燃料の貯蔵設備を提
供し、液体貯蔵に対するガス貯蔵性の優位性を更に向上
しうるようにしたものである。(Objective of the Invention) The present invention provides a spent nuclear fuel storage facility that can increase the storage capacity by simply providing a simple means in the storage cell, and further improves the superiority of gas storage over liquid storage. It was made so that it could be done.
（問題点を解決するための本発明の手段）本発明の特徴
とするところは次の点にある。即ち一実施例を示す第３
図（ａ）およびら）の縦断面図及び断面平面図（第１図
、第２図と同一符号部分は同等部分を示す）のように、
使用済み原子燃料集合体（７）のそれより径が大きく両
端に開口部（９ａ）（９ｂ）を持つ筒状の高空隙多孔質
体、例えば空隙率が９０％或いはそれ以上の多孔質体ま
たは層状に金網を重ねた筒状の多孔質体（９）を、貯蔵
ラック（６）の上下支持板（６ｂ） （６ｃ）により支
持して各貯蔵部の冷却ガス通路内に設ける。そしてその
内部に間隔をおいて貯蔵すべき使用済み原子燃料集合体
（７）を差し込んで周面を包みこむようにして、第４図
に示す伝熱メカニズムが形成されるようにした点にある
。(Means of the present invention for solving the problems) The present invention is characterized by the following points. That is, the third example shows one embodiment.
As shown in the longitudinal cross-sectional view and cross-sectional plan view of Figures (a) and (a) (the same reference numerals as in Figures 1 and 2 indicate the same parts),
A cylindrical high-porosity porous body having a diameter larger than that of the spent nuclear fuel assembly (7) and having openings (9a) and (9b) at both ends, for example, a porous body with a porosity of 90% or more, or A cylindrical porous body (9) made of layered wire mesh is supported by upper and lower support plates (6b) (6c) of a storage rack (6) and provided in the cooling gas passage of each storage section. Spent nuclear fuel assemblies (7) to be stored at intervals are inserted into the inside of the spent nuclear fuel assemblies (7) so as to wrap around the circumferential surface, so that the heat transfer mechanism shown in FIG. 4 is formed.
このようにすれば第４図のＡに示す、燃料集合体（７）
のチャンネルボックス或いはラッパー管（７ａ）の燃料
崩壊熱（ａ）による加熱より生ずる下方から上方への自
然対流の他に、図中Ｂに示すように燃料崩壊熱（ａ）に
もとづく輻射熱（ｂ）により加熱されて高温となる筒状
高空隙多孔質体（９）周面の活発な上昇自然対流を生ず
る。そしてこれらの熱は使用済み原子燃料集合体（７）
と高空隙多孔質体（９）間、および高空隙多孔質体（９
）と貯蔵ラックの仕切板（６ｄ）間をそれぞれ上昇する
ガス流（８）により貯蔵セル（１）外に運び去られる。In this way, the fuel assembly (7) shown in FIG.
In addition to the natural convection from below upwards caused by the heating of the channel box or wrapper tube (7a) by the fuel decay heat (a), as shown in B in the figure, there is radiant heat (b) based on the fuel decay heat (a). This generates active upward natural convection on the circumferential surface of the cylindrical high-pore porous body (9) which is heated to a high temperature. And this heat is transferred to spent nuclear fuel assemblies (7)
and the high-void porous body (9), and between the high-void porous body (9)
) and the partition plate (6d) of the storage rack, respectively, and are carried out of the storage cell (1) by a rising gas flow (8).
従って高空隙多孔質体（９）を設けることにより崩壊熱
の除熱機能を従来のものより増進させることが可能とな
る。Therefore, by providing the highly void porous body (9), it is possible to improve the decay heat removal function compared to the conventional one.
第５図は同一発熱量の使用済み原子燃料集合体を貯蔵時
の熱流束と燃料集合体（７）の表面温度との関係を筒状
高空隙多孔質体（９）の有無について実験的に求めた図
である。なおこの場合高空隙多孔質体（９）として住友
電気工業株式会社製セルメット（商品名）により作られ
たものを用いた。Figure 5 shows the relationship between the heat flux and the surface temperature of the fuel assembly (7) when storing spent nuclear fuel assemblies with the same calorific value, experimentally with and without the cylindrical high-porosity body (9). This is the diagram I found. In this case, as the highly voided porous body (9), one made by Celmet (trade name) manufactured by Sumitomo Electric Industries, Ltd. was used.
これから明らかなように代表的な使用済み原子燃料集合
体のガス貯蔵時の発熱量に相当する熱流束（８にＷ／ｅ
ｆｆｌ ）における使用済み原子燃料集合体の表面温度
は、高空隙多孔質体無設置の場合には図中のへ曲線から
約３７０°Ｃ５設置した場合には図中３曲線から約３２
０℃となり、高空隙多孔質体の使用によって貯蔵される
使用済み原子燃料集合体の表面温度を約５０°Ｃと大幅
に低くすることが可能となる。従ってそれだけガス冷却
容量の増大を少なくできる。また高空隙多孔質体は安価
軽量であって構造も簡単で実施が容易であるので、試算
によれば同一表面温度だけ低下させるに必要なガス冷却
容量の増大に比較して、要する費用は格段に安価である
。これに加えて高空隙多孔質体は駆動電力を全く必要と
しないため、高空隙多孔質体による表面温度の低下を冷
却ガスにより行う場合に比べて要する電力は少なくなり
、運転費の低減が可能となる。As is clear from this, the heat flux (W/e
The surface temperature of the spent nuclear fuel assembly at ffl) is approximately 370°C from the curve 3 in the figure when no high-porosity material is installed;
By using a highly pore porous material, the surface temperature of the spent nuclear fuel assembly to be stored can be significantly lowered to about 50°C. Therefore, the increase in gas cooling capacity can be reduced accordingly. In addition, high-porosity porous materials are cheap, lightweight, have a simple structure, and are easy to implement, so according to trial calculations, the cost is much lower than the increase in gas cooling capacity required to lower the same surface temperature. It is inexpensive. In addition, since high-porosity porous bodies do not require any driving power, less power is required compared to when cooling gas is used to lower the surface temperature of high-pore porous bodies, reducing operating costs. becomes.
以上本発明を一実施例について説明したが、第３図中に
点線で示すように高空隙多孔質体（９）を複数段（図で
は２段）設けて除熱効果を増すことができる。Although the present invention has been described above with reference to one embodiment, the heat removal effect can be increased by providing a plurality of stages (two stages in the figure) of high-porosity porous bodies (9) as shown by dotted lines in FIG.
（発明の効果）
以上の説明から明らかなように本発明によれば、従来の
ものより貯蔵性能のすぐれたガス使用済み原子燃料貯蔵
設備を提供しうるすぐれた効果が得られる。(Effects of the Invention) As is clear from the above description, the present invention provides an excellent effect of providing a gas spent nuclear fuel storage facility with better storage performance than conventional ones.
第１図および第２図はガス使用済み原子燃料貯蔵設備の
説明図、第３図は本発明の一実施例図の説明図、第４図
はその伝熱メカニズム図、第５図は伝熱促進効果を示す
実験例図である。
（１）・・・貯蔵セル、 （２）・・・除塵フィルタ、
（３）・・・ガス冷却器、 （４）・・・循環用ブロア
、（５）・・・移送器、 （６）・・・貯蔵ランク、
（６ａ）・・・ガス流路、 （６ｂ） （６ｃ）・・・
支持板、 （６ｄ）・・・仕切板、 （６ｅ）・・・共
通ガス通路、 （７）・・・使用済み原子燃料集合体、
（７ａ）・・・チャンネルボックス。
ラッパー管等、 （８）・・・冷却ガス、 （９）・・
・筒状高空隙多孔質体、 （９ａ） （９ｂ）・・・開
口部。
代
理
人Figures 1 and 2 are explanatory diagrams of a gas spent nuclear fuel storage facility, Figure 3 is an explanatory diagram of an embodiment of the present invention, Figure 4 is a diagram of its heat transfer mechanism, and Figure 5 is a diagram of heat transfer. It is an experimental example diagram showing the promoting effect. (1)...storage cell, (2)...dust removal filter,
(3)...Gas cooler, (4)...Circulation blower, (5)...Transfer device, (6)...Storage rank,
(6a)...Gas flow path, (6b) (6c)...
Support plate, (6d)...Partition plate, (6e)...Common gas passage, (7)...Spent nuclear fuel assembly,
(7a)...Channel box. Wrapper tube, etc., (8)...Cooling gas, (9)...
- Cylindrical high-porosity porous body, (9a) (9b)...opening. agent
Claims (1)
状高空隙多孔質体を設けたことを特徴とする使用済み原
子燃料のガス中貯蔵設備。(1) Spent nuclear fuel storage equipment in gas, characterized in that a cylindrical high-porosity body is provided in the cooling gas passage around the spent nuclear fuel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63300709A JPH0687080B2 (en) | 1988-11-30 | 1988-11-30 | Storage facility for spent nuclear fuel in gas |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63300709A JPH0687080B2 (en) | 1988-11-30 | 1988-11-30 | Storage facility for spent nuclear fuel in gas |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH02147996A true JPH02147996A (en) | 1990-06-06 |
| JPH0687080B2 JPH0687080B2 (en) | 1994-11-02 |
Family
ID=17888147
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63300709A Expired - Lifetime JPH0687080B2 (en) | 1988-11-30 | 1988-11-30 | Storage facility for spent nuclear fuel in gas |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0687080B2 (en) |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6117996A (en) * | 1984-07-04 | 1986-01-25 | 株式会社日立製作所 | Method of storing heat-generating radioactive substance |
-
1988
- 1988-11-30 JP JP63300709A patent/JPH0687080B2/en not_active Expired - Lifetime
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6117996A (en) * | 1984-07-04 | 1986-01-25 | 株式会社日立製作所 | Method of storing heat-generating radioactive substance |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0687080B2 (en) | 1994-11-02 |
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