JPS6239918B2 - - Google Patents
Info
- Publication number
- JPS6239918B2 JPS6239918B2 JP55121099A JP12109980A JPS6239918B2 JP S6239918 B2 JPS6239918 B2 JP S6239918B2 JP 55121099 A JP55121099 A JP 55121099A JP 12109980 A JP12109980 A JP 12109980A JP S6239918 B2 JPS6239918 B2 JP S6239918B2
- Authority
- JP
- Japan
- Prior art keywords
- demineralizer
- shield
- filter element
- decontamination
- height
- 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
Links
- 238000005202 decontamination Methods 0.000 claims description 11
- 230000003588 decontaminative effect Effects 0.000 claims description 11
- 238000010612 desalination reaction Methods 0.000 description 4
- 238000010248 power generation Methods 0.000 description 2
- 238000000746 purification Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 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
Landscapes
- Filtering Of Dispersed Particles In Gases (AREA)
Description
【発明の詳細な説明】
本発明は、原子力発電施設における脱塩器収納
室の改良に関するものである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to an improvement of a desalination chamber in a nuclear power generation facility.
原子力発電施設における脱塩器収納室の従来例
を、第1図および第2図に示す。同図において、
符号1は脱塩器収納室全体を示しており、脱塩器
収納室1には、脱塩器2および3がそれぞれコン
クリート遮蔽体4を介して隔離状に配設されてい
る。5は遮蔽体4を介して脱塩器収納室1に隣接
した除染室で、除染室5には、除染槽6が配設さ
れている。7は遮蔽体4の天井壁4aに着脱自在
に装着した、ユニツト遮蔽体を構成するハツチ、
8は除染室5の天井に設けたモノレール、9はモ
ノレールホイスト、10はホイスト9に吊持され
た脱塩器2のフイルターエレメントを示す。 A conventional example of a desalination storage room in a nuclear power generation facility is shown in FIGS. 1 and 2. In the same figure,
Reference numeral 1 indicates the entire demineralizer storage chamber, and in the demineralizer storage chamber 1, demineralizers 2 and 3 are respectively arranged in an isolated manner with a concrete shield 4 interposed therebetween. A decontamination chamber 5 is adjacent to the demineralizer storage chamber 1 via a shield 4, and a decontamination tank 6 is disposed in the decontamination chamber 5. 7 is a hatch forming a unit shield, which is detachably attached to the ceiling wall 4a of the shield 4;
Reference numeral 8 indicates a monorail installed on the ceiling of the decontamination room 5, 9 indicates a monorail hoist, and 10 indicates a filter element of the demineralizer 2 suspended by the hoist 9.
以上の構成において、原子炉浄化系もしくは使
用済燃料プール水浄化系に使用される脱塩器2お
よび3は、そのいずれか一方の脱塩器のフイルタ
ーエレメントの除染中であつても、他方の脱塩器
が運転を続行するように構成されている。そして
フイルターエレメント10の除染は、除染室5に
配設された除染槽6内でおこなわれる。また、フ
イルターエレメント10の搬出入は、モノレール
ホイスト9によりおこなわれ、上記フイルターエ
レメント10の搬出入に際しては、遮蔽体4の天
井壁4aに装着されたハツチ7が取り外される。 In the above configuration, the demineralizers 2 and 3 used in the reactor purification system or the spent fuel pool water purification system can be used even when the filter element of one of the demineralizers is being decontaminated, The demineralizer is configured to continue operating. The filter element 10 is decontaminated in a decontamination tank 6 provided in the decontamination chamber 5. Further, the filter element 10 is carried in and out by a monorail hoist 9, and when the filter element 10 is carried in and out, the hatch 7 attached to the ceiling wall 4a of the shielding body 4 is removed.
ところで、上記した脱塩器収納室1の高さは、
脱塩器2および3の配置高さ、遮蔽体4の高さ、
フイルターエレメント10の高さ、さらにはモノ
レールホイスト9の吊上高さなどを考慮にいれる
必要がある。したがつて、脱塩器収納室の高さを
高くしなければならなかつた。 By the way, the height of the demineralizer storage chamber 1 mentioned above is
Arrangement height of desalinators 2 and 3, height of shield 4,
It is necessary to take into account the height of the filter element 10 and the lifting height of the monorail hoist 9. Therefore, it was necessary to increase the height of the desalination chamber.
本発明の目的は、以上の点を考慮し、高さを低
くすることのできる構造の脱塩器収納室を提供し
ようとするものである。 An object of the present invention is to provide a demineralizer storage chamber having a structure that allows the height to be reduced in consideration of the above points.
上記目的を達成するため、本発明は、遮蔽体を
介して除染室を隣設してなる脱塩器収納室におい
て、上記遮蔽体の天井壁および側壁に、その両壁
にわたつて連続する開口部を設け、この開口部
に、ユニツト遮蔽体を着脱自在に装着してなるこ
とを特徴とするものである。 In order to achieve the above object, the present invention provides a demineralizer storage room in which a decontamination room is placed adjacent to the decontamination room through a shield, in which a demineralizer is provided that is continuous with the ceiling wall and side wall of the shield, and extends across both walls. The device is characterized in that an opening is provided, and a unit shield is detachably attached to the opening.
以下、本発明を、第3図および第4図の一実施
例にもとづいて説明する。第3図および第4図に
おいて、第1図および第2図と同一符号は同一部
分、11は遮蔽体4の側壁4bに着脱自在に装着
した、ユニツト遮蔽体を構成するスロツトプラグ
を示し、このスロツトプラグ11は、遮蔽体4の
天井壁4aに着脱自在に装着されたハツチ7に隣
接して設けられている。すなわち、本発明におい
ては、遮蔽体4の天井壁4aおよび側壁4bに、
その両壁4a,4bにわたつて連続する開口部を
設け、この開口部に、それぞれハツチおよびスロ
ツトプラグなどからなるユニツト遮蔽体7および
11を装着してなることを要旨とするものであ
る。 The present invention will be explained below based on an embodiment shown in FIGS. 3 and 4. 3 and 4, the same reference numerals as in FIGS. 1 and 2 indicate the same parts, and 11 indicates a slot plug that is detachably attached to the side wall 4b of the shield 4 and constitutes the unit shield. 11 is provided adjacent to the hatch 7 which is detachably attached to the ceiling wall 4a of the shielding body 4. That is, in the present invention, the ceiling wall 4a and side wall 4b of the shielding body 4 are provided with
The gist is that continuous openings are provided across both walls 4a and 4b, and unit shields 7 and 11, each consisting of a hatch and a slot plug, are attached to these openings.
したがつて、第3図および第4図の実施例にお
いて、脱塩器2のフイルターエレメント10を搬
出入するにあたつては、ハツチ7およびスロツト
プラグ11を取り外せば、その両ユニツト遮蔽体
7および11を取り外して得られた連続開口部を
利用してフイルターエレメント10の出し入れ操
作をおこなうことができるから、フイルターエレ
メント10の出し入れに要する高さ寸法を、従来
よりも大幅に縮小することができる。 Therefore, in the embodiments of FIGS. 3 and 4, when carrying in and out the filter element 10 of the demineralizer 2, the hatch 7 and the slot plug 11 are removed, and the shield 7 and the Since the continuous opening obtained by removing the filter element 11 can be used to take in and take out the filter element 10, the height required for taking in and taking out the filter element 10 can be significantly reduced compared to the conventional one.
以上、記述したように、本発明によれば、脱塩
器2のフイルターエレメント10を搬出入するに
あたり、フイルターエレメント10の吊上高さを
従来よりも低く抑えることができるため、脱塩器
収納室の高さを著しく低くすることができるとい
う顕著な効果が得られる。 As described above, according to the present invention, when carrying in and out the filter element 10 of the demineralizer 2, the lifting height of the filter element 10 can be suppressed lower than before, so that the demineralizer is stored A remarkable effect is obtained in that the height of the chamber can be significantly reduced.
第1図は原子力発電施設における脱塩器収納室
の従来例を示す平面図、第2図は第1図のA−A
断面図、第3図は本発明に係る脱塩器収納室の一
実施例を示す平面図、第4図は第3図のB−B断
面図である。
1……脱塩器収納室、2,3……脱塩器、4…
…遮蔽体、4a……天井壁、4b……側壁、5…
…除染室、6……除染槽、7……ハツチ(ユニツ
ト遮蔽体)、8……モノレール、9……モノレー
ルホイスト、10……フイルターエレメント、1
1……スロツトプラグ(ユニツト遮蔽体)。
Figure 1 is a plan view showing a conventional example of a desalination storage room in a nuclear power facility, and Figure 2 is A-A in Figure 1.
3 is a plan view showing an embodiment of the demineralizer storage chamber according to the present invention, and FIG. 4 is a sectional view taken along line BB in FIG. 3. 1...Demineralizer storage room, 2, 3...Demineralizer, 4...
...shielding body, 4a...ceiling wall, 4b...side wall, 5...
... Decontamination room, 6 ... Decontamination tank, 7 ... Hutch (unit shield), 8 ... Monorail, 9 ... Monorail hoist, 10 ... Filter element, 1
1...Slot plug (unit shield).
Claims (1)
収納室において、上記遮蔽体の天井壁および側壁
に、その両壁にわたつて連続する開口部を設け、
この開口部に、ユニツト遮蔽体を着脱自在に装着
してなることを特徴とする脱塩器収納室。1. In a demineralizer storage room with a decontamination room adjacent to it via a shield, an opening is provided in the ceiling wall and side wall of the shield that continues across both walls,
A demineralizer storage chamber characterized in that a unit shield is detachably attached to the opening.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP55121099A JPS5745493A (en) | 1980-09-03 | 1980-09-03 | Desalter storage room |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP55121099A JPS5745493A (en) | 1980-09-03 | 1980-09-03 | Desalter storage room |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS5745493A JPS5745493A (en) | 1982-03-15 |
JPS6239918B2 true JPS6239918B2 (en) | 1987-08-25 |
Family
ID=14802845
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP55121099A Granted JPS5745493A (en) | 1980-09-03 | 1980-09-03 | Desalter storage room |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS5745493A (en) |
-
1980
- 1980-09-03 JP JP55121099A patent/JPS5745493A/en active Granted
Also Published As
Publication number | Publication date |
---|---|
JPS5745493A (en) | 1982-03-15 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
DE3367136D1 (en) | Nuclear fuel assembly for a boiling water nuclear reactor | |
GB2011697A (en) | Method for the recovery of actinide elements from nuclear reactor waste | |
EP0083026A3 (en) | Dry storage for burned nuclear reactor fuel elements | |
ZA811783B (en) | Fuel assemblies for nuclear reactors | |
BR7707273A (en) | PROCESS FOR FIXING RADIOACTIVE SUBSTANCES, PARTICULARLY OF HIGH LEVEL RADIOACTIVE WASTE, SEPARATE DURING THE REPROCESSING OF NUCLEAR FUEL, IN A BODY RESISTANT TO LIXIVIATION BY WATER | |
GR920300066T1 (en) | Process for removing radioactive burden from spent nuclear reactor decontamination solutions using electrochemical ion exchange | |
GB9312416D0 (en) | Combined cooling and purification system for nuclear reactor spent fuel pit,refueling cavity and refueling water storage tank | |
ZA829070B (en) | Nuclear reactor fuel assemblies | |
DE69312615D1 (en) | Fission zone for boiling water nuclear reactor | |
DE3172188D1 (en) | Monitoring system for monitoring the state of nuclear reactor core | |
EG14893A (en) | Arrangement for storing spent nuclear fuel rods at a reactor site | |
JPS6239918B2 (en) | ||
FR2603130B1 (en) | RADIATOR FOR NUCLEAR REACTOR CONTAINMENT ENCLOSURE | |
ES506413A0 (en) | MANUFACTURING PROCEDURE FOR A NUCLEAR REACTOR TANK BOLT | |
GB2085642B (en) | Nuclear reactor shutdown system | |
YU178284A (en) | Prefabricated construction assembly for storage especially for fuel elements of nuclear reactors | |
GB2003310B (en) | Process for the disposal of spent fuel elements and/or highly active waste from nuclear power plants | |
GB2052349B (en) | Storage vessel for irradiated nuclear fuel elements | |
ES477286A1 (en) | Confinement vessel,in particular for nuclear reactor. | |
JPS62228988A (en) | Condensate purifying facility | |
JPS6024496A (en) | Structure of storage pool for used fuel of housing for reactor | |
JPS57104889A (en) | Fuel refilling of light water system boiling water type nuclear reactor | |
JPS5713084A (en) | Controller for nuclear reactor housing crane | |
JPS6137596B2 (en) | ||
FR2545637B1 (en) | TANK FOR CLOSING THE TANK OF A FAST NEUTRAL NUCLEAR REACTOR |