JPH0141957B2 - - Google Patents
Info
- Publication number
- JPH0141957B2 JPH0141957B2 JP59106625A JP10662584A JPH0141957B2 JP H0141957 B2 JPH0141957 B2 JP H0141957B2 JP 59106625 A JP59106625 A JP 59106625A JP 10662584 A JP10662584 A JP 10662584A JP H0141957 B2 JPH0141957 B2 JP H0141957B2
- Authority
- JP
- Japan
- Prior art keywords
- duct
- pool
- operating floor
- floor
- air
- 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
- 238000009423 ventilation Methods 0.000 claims description 17
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 6
- 230000002285 radioactive effect Effects 0.000 description 17
- 239000007789 gas Substances 0.000 description 13
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 13
- 238000002955 isolation Methods 0.000 description 6
- 238000011109 contamination Methods 0.000 description 4
- 239000000446 fuel Substances 0.000 description 4
- 238000009835 boiling Methods 0.000 description 3
- 238000010586 diagram Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 238000007689 inspection Methods 0.000 description 3
- 230000000737 periodic effect Effects 0.000 description 3
- 238000010248 power generation Methods 0.000 description 3
- 230000002787 reinforcement Effects 0.000 description 3
- 238000010276 construction Methods 0.000 description 2
- 238000007796 conventional method Methods 0.000 description 2
- 230000008030 elimination Effects 0.000 description 2
- 238000003379 elimination reaction Methods 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 230000000630 rising effect Effects 0.000 description 2
- 238000012546 transfer Methods 0.000 description 2
- 230000004913 activation Effects 0.000 description 1
- 238000004378 air conditioning Methods 0.000 description 1
- 238000004140 cleaning Methods 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- PNDPGZBMCMUPRI-UHFFFAOYSA-N iodine Chemical compound II PNDPGZBMCMUPRI-UHFFFAOYSA-N 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000012545 processing Methods 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
- Ventilation (AREA)
- Sink And Installation For Waste Water (AREA)
Description
【発明の詳細な説明】
〔発明の利用分野〕
本発明は原子炉運転階燃料取替時の換気方式に
おいてプールから発生する放射性気体の捕集に運
転階換気方式を用いることに係り、特に高効率の
放射性気体捕集に好適な沸騰水型原子力発電設備
の原子炉運転階換気方式に関する。[Detailed Description of the Invention] [Field of Application of the Invention] The present invention relates to the use of an operating floor ventilation system to collect radioactive gas generated from a pool in the ventilation system at the time of refueling on the operating floor of a nuclear reactor. This invention relates to a reactor operating floor ventilation system for boiling water nuclear power generation equipment suitable for efficient radioactive gas collection.
従来の沸騰水型原子力発電設備における原子炉
運転階および燃料プール（使用済燃料貯蔵プー
ル／原子炉キヤビテイ原子炉ウエル／ドライヤ・
セパレータ機器仮置プール）の換気空調系ダクト
設備の系統図を第１図および第２図に示す。第１
図は、原子炉運転階全体の給気および排気ダクト
の系統を示し、特に燃料プール廻りの排気ダクト
（プール埋込ダクト）の系統を第２図に示す。第
３図は、運転階におけるダクト配置を示し、その
断面図を第４図に示す。又、第５図に燃料交換時
および定検時の運転階の風の流れを示す。
Reactor operating floor and fuel pool (spent fuel storage pool/reactor cavity reactor well/dryer) in conventional boiling water nuclear power generation equipment
Figures 1 and 2 show system diagrams of the ventilation and air conditioning duct equipment for the separator equipment (temporary storage pool). 1st
The figure shows the supply air and exhaust duct systems for the entire reactor operating floor, and in particular, the exhaust duct system around the fuel pool (pool-embedded duct) is shown in FIG. FIG. 3 shows the duct arrangement on the operating floor, and FIG. 4 shows a cross-sectional view thereof. Furthermore, Fig. 5 shows the flow of wind on the operating floor during fuel exchange and periodic inspection.
従来方式の場合、第１図〜第４図に示すように
原子炉運転階１の換気システムは、運転階壁面の
給気ダクト５より給気し、反対側壁面の排気ダク
ト６より排気を行なつている。また、燃料交換時
および定検時には、プール（原子炉キヤビテイ原
子炉ウエル２／使用済燃料貯蔵プール３／ドライ
ヤ・セパレータ機器仮置プール４）からの放射性
気体（放射性ヨウ素等の揮発性の放射化された分
子）の捕集を目的として、プール水面上のプール
壁面に埋込まれた排気ダクト（埋込ダクト８）よ
り排気するようになつている。又、第１図７は、
プール専用の実在のダクトではなく、運転階給気
ダクト５により運転階に給気された空気が運転階
を通して移送されていることを示している。した
がつて、運転階に給気された空気は、運転階の排
気ダクトおよび３つのプール２〜４の埋込ダクト
によつて排気される。第２図は、埋込ダクトのシ
ステムを示すものであるが、本示に如す１２，１
３，１４，１５は各々、グローブ弁、ドレン受
口、ダクト隔離弁、ドレン配管を示す。プールよ
り発生する放射性気体は、埋込ダクトにより排気
されるが、本ダクトはプール水面上、約12mmのと
ころに開口があるため地震等の影響によるプール
水の波立ちによりダクト内に水の流入する可能性
がある。このため、本ダクトには、隔離弁、ドレ
ン配管等が設けられている。ダクトに、水が流入
した場合、第１ドレン配管（ダクト開口と隔離弁
との間に得らけられている配管）によつて水の流
入が防がれるが、一部の水はダクト先へ流れてい
く可能性があるため、ダクトに隔離弁１４が設け
られている。又、完全に隔離されない場合を想定
して、その先にもドレン配管が設けられており、
これらの弁１２，１４開閉のための電気信号も必
要であるため、非常に複雑な構造となつている。
又、ダクトは運転床下に埋込まれているため、建
屋配筋・他系統配管等との干渉が多く、施工には
多大な工数を要す。 In the case of the conventional system, as shown in Figures 1 to 4, the ventilation system on the reactor operating floor 1 supplies air through an air supply duct 5 on the wall of the operating floor and exhausts air through an exhaust duct 6 on the opposite wall. It's summery. In addition, during fuel exchange and periodic inspections, radioactive gases (volatile activation such as radioactive iodine, In order to collect the trapped molecules, the air is exhausted from an exhaust duct (embedded duct 8) embedded in the pool wall above the pool water surface. Also, Fig. 1 7 shows that
It is shown that the air supplied to the driving floor is transported through the driving floor by the driving floor air supply duct 5, rather than the actual duct dedicated to the pool. Therefore, the air supplied to the operating floor is exhausted by the exhaust duct of the operating floor and the embedded ducts of the three pools 2-4. FIG. 2 shows a system of embedded ducts.
3, 14, and 15 indicate a globe valve, a drain port, a duct isolation valve, and a drain pipe, respectively. Radioactive gas generated from the pool is exhausted through an embedded duct, but since this duct has an opening approximately 12 mm above the pool water surface, water may flow into the duct due to ripples in the pool water caused by earthquakes, etc. there is a possibility. For this reason, this duct is provided with an isolation valve, drain piping, etc. If water flows into the duct, the first drain pipe (the pipe provided between the duct opening and the isolation valve) will prevent the water from flowing into the duct, but some of the water will flow into the duct. Therefore, an isolation valve 14 is provided in the duct. In addition, in case it is not completely isolated, a drain pipe is also installed beyond that.
Since electrical signals are also required to open and close these valves 12 and 14, the structure is extremely complicated.
In addition, since the duct is buried under the operating floor, there is a lot of interference with building reinforcement, other system piping, etc., and construction requires a large amount of man-hours.
第５図は、従来のダクトシステムによる運転階
の風の流れを示すものである。図に示すように、
プール２〜４にて発生する放射性気体の捕集は、
ダクト開口に近いところだけでしか行なわれな
い。そして、プール中心付近の放射性気体はその
温度が高い（50〜65℃）ため、運転階に放出さ
れ、建屋上部へと上昇して運転階の放射能汚染を
広げる。一方、給気ダクト５より給気された新鮮
な空気は、その温度が低い（16℃）ため、しだい
に床面へと下降してゆく。しかし、プール上空で
はプールからの高温の汚染空気が上昇してくるた
め、両空気は混合し、原子炉ウエル２付近で建屋
上方へ上昇してしまい、使用済燃料貯蔵プール３
付近へは低温の新鮮な空気は流れない。このた
め、給気ダクト下から原子炉ウエルにかけての床
面は比較的放射能汚染が低いが、原子炉ウエルか
ら排気ダクト下までの床面は汚染率が高い。 FIG. 5 shows the flow of air on the driving floor by a conventional duct system. As shown in the figure,
Collection of radioactive gas generated in pools 2 to 4 is as follows:
This is only done near the duct opening. Since the temperature of the radioactive gas near the center of the pool is high (50 to 65 degrees Celsius), it is released onto the operating floor, rises to the upper part of the building, and spreads radioactive contamination on the operating floor. On the other hand, since the fresh air supplied from the air supply duct 5 has a low temperature (16° C.), it gradually descends to the floor surface. However, as the high-temperature contaminated air from the pool rises above the pool, the two airs mix and rise above the building near reactor well 2, causing the spent fuel storage pool 3
No cold fresh air flows into the area. Therefore, the floor surface from the bottom of the air supply duct to the reactor well has relatively low radioactive contamination, but the floor surface from the reactor well to the bottom of the exhaust duct has a high contamination rate.
以上のように、従来の沸騰水型原子力発電設備
の原子炉運転階換気システムには、次に示す欠点
があつた。 As described above, the conventional reactor operating floor ventilation system for boiling water nuclear power generation equipment has the following drawbacks.
(1) 運転階の空気の流れは第５図に示すようにな
つているため、プールにて発生する放射性気体
の捕集効果があまりない。(1) Since the air flow on the operating floor is as shown in Figure 5, it is not very effective in capturing radioactive gas generated in the pool.
(2) 地震等によるプール水面の波立ちによりダク
ト内に水の流入する恐れがある。また、それを
完全に防止するために非常に複雑な構造となつ
ている。(2) Water may flow into the duct due to ripples on the pool water surface due to earthquakes, etc. In addition, it has a very complex structure to completely prevent this.
(3) プール廻り埋込ダクトは、ダクトが床下に埋
込まれているため、建屋配節・他系統配管等と
の干渉が多く、施工に多大な工数を要してい
る。(3) Because the duct is buried under the floor, it often interferes with building connections and other system piping, and requires a large amount of man-hours to construct.
本発明の目的は、原子炉運転階の放射性気体を
効率良く捕集できる換気システムを提供すること
にある。
An object of the present invention is to provide a ventilation system that can efficiently collect radioactive gas on the operating floor of a nuclear reactor.
本発明の換気システムは、ドライヤセパレータ
プール、原子炉ウエルおよび使用済燃料棒貯蔵プ
ールを備えた原子炉運転階に、給気ダクトおよび
排気ダクトを設けてなる原子炉運転階の換気シス
テムにおいて、前記運転階のプール両側の各壁面
に給気ダクトを設け、かつ前記運転階のプール上
方の天井部分に排気ダクトを設けたことを特徴と
する。
The ventilation system of the present invention is a ventilation system for a reactor operating floor, which comprises a reactor operating floor equipped with a dryer separator pool, a reactor well, and a spent fuel rod storage pool, and is provided with an air supply duct and an exhaust duct. The present invention is characterized in that an air supply duct is provided on each wall on both sides of the pool on the operating floor, and an exhaust duct is provided on the ceiling above the pool on the operating floor.
以下、本発明の一実施例を第６図〜第９図によ
り説明する。
An embodiment of the present invention will be described below with reference to FIGS. 6 to 9.
第６図は、本発明による原子炉運転階の換気シ
ステムを示すものである。本方式の最大の特徴
は、従来の磨菌ダクトを廃止し、プールより発生
する放射性気体の捕集を、運転階排気ダクトによ
り排気する運転階換気方式としていることであ
る。これは、図中９で示されている。第７図およ
び第８図は本方式による運転階のダクト配置の平
面図および段面図を示す。本方式ではプール両側
の運転階壁面に設置された２つの給気ダクト５に
より給気し、プール上方にある天井排気ダクト６
により排気を行なつている。３つのプール２〜４
の放射性気体の発散濃度が違うため、給排気ダク
トはこれらのプールに平行に設置し、放射能濃度
の一番高い使用済燃料貯蔵プール３付近での換気
を良くするため、給排気フアンからのダクトを本
プール側に継ぎ、換気量を他プールに比べ大きく
している。したがつて、ダクトの大きさも本プー
ル側が一番大きくなつており、給排気量が大きく
なるようにしており、運転階全体の放射能汚染が
一定となるようにしている。又、天井排気ダクト
は、運転階天上にある建屋配筋１０に載せるよう
な形で設置することにより耐震性を良くし、プー
ルへの落下を防いでいる。又、左右方向は、ダク
トをサポート材により直接建屋配筋に固定するこ
とにより、左右方向の移動を防いでいる。 FIG. 6 shows a ventilation system for a nuclear reactor operating floor according to the present invention. The biggest feature of this system is that the conventional cleaning duct is abolished, and radioactive gases generated from the pool are collected and exhausted by a driving floor ventilation system, which is exhausted through the driving floor exhaust duct. This is indicated by 9 in the figure. FIGS. 7 and 8 show a plan view and a step view of the duct arrangement of the driving floor according to this method. In this system, air is supplied through two air supply ducts 5 installed on the walls of the operating floor on both sides of the pool, and a ceiling exhaust duct 6 above the pool.
Exhaust is performed by 3 pools 2-4
Because the concentration of radioactive gas emitted by the pools is different, the supply and exhaust ducts are installed parallel to these pools, and in order to improve ventilation near the spent fuel storage pool 3, where the radioactivity concentration is highest, the supply and exhaust ducts are installed from the supply and exhaust fan. The duct is connected to the main pool side, increasing the amount of ventilation compared to other pools. Therefore, the size of the duct is the largest on the main pool side, increasing the amount of air supply and exhaust, so that the radioactive contamination of the entire operating floor remains constant. In addition, the ceiling exhaust duct is installed so as to rest on the building reinforcement 10 above the operating floor to improve earthquake resistance and prevent it from falling into the pool. In addition, the duct is fixed directly to the building reinforcement using support materials to prevent movement in the left and right direction.
第９図は、本換気方式による運転階の風の流れ
を示すものである。運転階壁面の給気ダクト５よ
り給気された空気は、その温度が低い（16℃）た
め建屋下方へと向かい、床面を換気した後、プー
ル上空でプールより発生す高温（50〜65℃）の汚
染空気（放射性気体）と混合し、温度が上がつて
建屋上方へと上昇する。上昇した汚染空気は、プ
ール上空に設置されている天井排気ダクトにより
排気される。上昇空気の一部は建屋上方にて循環
するが、その温度が給気空気より高いため、下方
へは下りて来ない。又、前述のように給排気ダク
トが３つのプールに平行に設置されているため、
どのプールにおいても、本図に示すような風の流
れとなつている。 Figure 9 shows the flow of wind on the operating floor using this ventilation method. The air supplied from the air supply duct 5 on the wall of the operating floor has a low temperature (16°C), so it heads towards the lower part of the building, ventilates the floor, and then reaches the high temperature (50-65°C) generated by the pool in the air above the pool. It mixes with contaminated air (radioactive gas) at 30°F (°C), rises in temperature, and rises toward the top of the building. The rising contaminated air is exhausted through a ceiling exhaust duct installed above the pool. Some of the rising air circulates above the building, but because its temperature is higher than the supply air, it does not come down. Also, as mentioned above, the supply and exhaust ducts are installed parallel to the three pools, so
In every pool, the wind flows as shown in this diagram.
以上のように本実施例によれば、従来の方式に
比べ、プールから発生する放射性気体の捕集効果
が大幅に改善される。 As described above, according to this embodiment, the effect of collecting radioactive gas generated from the pool is significantly improved compared to the conventional method.
本実施例では、さらに、プールへの処理ダクト
の廃止により次のような各利点が得られる。 In this embodiment, the following advantages can be obtained by eliminating the processing duct to the pool.
(1) 埋込ダクト廃止に伴い、設計の簡素化・建設
工数及びコストの大幅な低減となり、合理化が
図れる。(1) Eliminating buried ducts will simplify the design and significantly reduce construction man-hours and costs, resulting in rationalization.
(2) 埋込ダクト廃止に伴い、地震等によりプール
の水がダクトに流入するという問題が無くな
る。(2) With the elimination of buried ducts, the problem of pool water flowing into the ducts due to earthquakes, etc. will be eliminated.
(3) 埋込ダクト廃止に伴い、それに付随する隔離
弁・グローブ弁等、開閉に遠隔操作を必要とす
るものが無くなるので、運転が容易になる。(3) With the elimination of buried ducts, there will be no need for associated isolation valves, globe valves, etc. that require remote control to open and close, making operation easier.
本発明によれば、放射性気体の補修効果が従来
になく向上するため、定期点検時の人体への影響
が低減される。
According to the present invention, the repair effect of radioactive gas is improved more than ever before, so the influence on the human body during periodic inspections is reduced.
第１図〜第５図は従来方式、第６図〜第９図は
本発明による原子炉運転階の換気方式に関するも
ので、第１図、第６図は運転階換気方式のブロツ
ク図、第２図は埋込ダクトのシステム構成図、第
３図、第７図は運転階平面図、第４図、第８図は
前図のＡ−Ａ線およびＢ−Ｂ線断面図、第５図、
第９図は、それぞれ前図Ｂ−Ｂ線断面図およびＡ
−Ａ線断面図における風の流れを示す説明図であ
る。
１……原子炉運転階、３……使用済燃料貯蔵プ
ール、５……運転階給気ダクト、６……運転階排
気ダクト、７……給気空気の移送、８……プール
廻り埋込ダクト、９……排気空気の移送、１２…
…ドレン配管グローブ弁、１３……ドレン受口、
１４……ダクト隔離弁。
Figures 1 to 5 relate to the conventional method, and Figures 6 to 9 relate to the ventilation system for the operating floor of the reactor according to the present invention. Figure 2 is a system configuration diagram of the embedded duct, Figures 3 and 7 are plan views of the operating floor, Figures 4 and 8 are cross-sectional views taken along lines A-A and B-B in the previous figure, and Figure 5. ,
FIG. 9 is a sectional view taken along line B-B in the previous figure and A
It is an explanatory view showing the flow of wind in a cross-sectional view taken along the line -A. 1... Reactor operating floor, 3... Spent fuel storage pool, 5... Operating floor air supply duct, 6... Operating floor exhaust duct, 7... Supply air transfer, 8... Buried around the pool. Duct, 9... Transfer of exhaust air, 12...
...Drain piping globe valve, 13...Drain socket,
14...Duct isolation valve.
Claims (1)
よび使用済燃料棒貯蔵プールを備えた原子炉運転
階に、給気ダクトおよび排気ダクトを設けてなる
原子炉運転階の換気システムにおいて、前記各プ
ールよりも高い位置で対向しあう前記運転階の両
側壁沿いに前記給気ダクトを設け、前記各プール
の上方であつて前記運転階の天井沿いに前記排気
ダクトを設けたことを特徴とする原子炉運転階の
換気システム。1. In a ventilation system for a reactor operating floor that is equipped with an air supply duct and an exhaust duct on a reactor operating floor that is equipped with a dryer separator pool, a reactor well, and a spent fuel rod storage pool, a location higher than each of the pools. The supply air duct is provided along both side walls of the operating floor facing each other, and the exhaust duct is provided above each of the pools and along the ceiling of the operating floor. ventilation system.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59106625A JPS60250296A (en) | 1984-05-28 | 1984-05-28 | Ventilation system of reactor operating stair of boiling-water type nuclear power facility |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59106625A JPS60250296A (en) | 1984-05-28 | 1984-05-28 | Ventilation system of reactor operating stair of boiling-water type nuclear power facility |
Related Child Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2206884A Division JPH0373889A (en) | 1990-08-06 | 1990-08-06 | Ventilation system for reactor operation stage |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS60250296A JPS60250296A (en) | 1985-12-10 |
| JPH0141957B2 true JPH0141957B2 (en) | 1989-09-08 |
Family
ID=14438288
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59106625A Granted JPS60250296A (en) | 1984-05-28 | 1984-05-28 | Ventilation system of reactor operating stair of boiling-water type nuclear power facility |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60250296A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2015087239A (en) * | 2013-10-30 | 2015-05-07 | 日立Ｇｅニュークリア・エナジー株式会社 | Spent nuclear fuel transportation method |
-
1984
- 1984-05-28 JP JP59106625A patent/JPS60250296A/en active Granted
Non-Patent Citations (2)
| Title |
|---|
| NUCLEAR ENGINEERING INTERNATIONAL=1978 * |
| SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 AND 2 FINAL SAFETY ANALYSIS REPORT REV35=1984 * |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS60250296A (en) | 1985-12-10 |
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