JPH02287193A - Output control method for heavy water moderating light water cooled pressure pipe type nuclear reactor - Google Patents
Output control method for heavy water moderating light water cooled pressure pipe type nuclear reactorInfo
- Publication number
- JPH02287193A JPH02287193A JP1108948A JP10894889A JPH02287193A JP H02287193 A JPH02287193 A JP H02287193A JP 1108948 A JP1108948 A JP 1108948A JP 10894889 A JP10894889 A JP 10894889A JP H02287193 A JPH02287193 A JP H02287193A
- Authority
- JP
- Japan
- Prior art keywords
- heavy water
- poison
- filter
- particles
- heavy
- 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
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 title claims abstract description 146
- 238000000034 method Methods 0.000 title claims abstract description 12
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title description 5
- 239000002574 poison Substances 0.000 claims abstract description 48
- 231100000614 poison Toxicity 0.000 claims abstract description 48
- 239000002245 particle Substances 0.000 claims abstract description 22
- 229910052805 deuterium Inorganic materials 0.000 abstract description 7
- -1 deuterium peroxide Chemical class 0.000 abstract description 7
- 238000000354 decomposition reaction Methods 0.000 abstract description 5
- 239000002699 waste material Substances 0.000 abstract description 5
- 238000004140 cleaning Methods 0.000 abstract description 4
- 238000001816 cooling Methods 0.000 abstract description 4
- 238000005342 ion exchange Methods 0.000 abstract description 4
- 238000011001 backwashing Methods 0.000 abstract description 3
- 239000007788 liquid Substances 0.000 abstract description 2
- 238000011084 recovery Methods 0.000 abstract description 2
- 238000000746 purification Methods 0.000 description 7
- 239000003456 ion exchange resin Substances 0.000 description 6
- 229920003303 ion-exchange polymer Polymers 0.000 description 6
- NWUYHJFMYQTDRP-UHFFFAOYSA-N 1,2-bis(ethenyl)benzene;1-ethenyl-2-ethylbenzene;styrene Chemical compound C=CC1=CC=CC=C1.CCC1=CC=CC=C1C=C.C=CC1=CC=CC=C1C=C NWUYHJFMYQTDRP-UHFFFAOYSA-N 0.000 description 5
- 238000010586 diagram Methods 0.000 description 5
- 150000002500 ions Chemical class 0.000 description 4
- 238000002485 combustion reaction Methods 0.000 description 3
- 239000000446 fuel Substances 0.000 description 3
- 230000009257 reactivity Effects 0.000 description 3
- 239000000243 solution Substances 0.000 description 3
- 238000007796 conventional method Methods 0.000 description 2
- 238000002347 injection Methods 0.000 description 2
- 239000007924 injection Substances 0.000 description 2
- 239000000126 substance Substances 0.000 description 2
- 239000002253 acid Substances 0.000 description 1
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 description 1
- 239000004327 boric acid Substances 0.000 description 1
- 238000005341 cation exchange Methods 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000001914 filtration Methods 0.000 description 1
- 239000010419 fine particle Substances 0.000 description 1
- CMIHHWBVHJVIGI-UHFFFAOYSA-N gadolinium(III) oxide Inorganic materials [O-2].[O-2].[O-2].[Gd+3].[Gd+3] CMIHHWBVHJVIGI-UHFFFAOYSA-N 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 238000011068 loading method Methods 0.000 description 1
- 230000004807 localization Effects 0.000 description 1
- 238000001556 precipitation Methods 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000008929 regeneration Effects 0.000 description 1
- 238000011069 regeneration method Methods 0.000 description 1
- 239000011347 resin Substances 0.000 description 1
- 229920005989 resin Polymers 0.000 description 1
- 238000000926 separation method Methods 0.000 description 1
- 238000001179 sorption measurement Methods 0.000 description 1
- 239000000829 suppository 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
- Treatment Of Water By Ion Exchange (AREA)
- Treatment Of Water By Oxidation Or Reduction (AREA)
Abstract
Description
この発明は、重水減速材中のポイズンの濃度を制御する
ことにより重水減速軽水冷却圧力管型原子炉の出力を制
御する方法に関するものである。The present invention relates to a method for controlling the output of a heavy water-moderated, light-water-cooled, pressure tube type nuclear reactor by controlling the concentration of poison in the heavy water moderator.
重水減速軽水冷却圧力管型原子炉においては、燃料の燃
焼による反応度補償は重水中にイオンとして解離してい
るポイズンの濃度を制御することにより行っている。こ
の重水系の系統図を第２図に示し、簡単に説明すると、
反応度を抑制したい場合にはポイズン調整槽１内の濃縮
ホウ酸溶液をポイズン注入ポンプ２によりカランドリア
タンク３に供給される重水に加えることで、カランドリ
アタンク３内の１０Ｂ３＋濃度を増加し、逆に反応度を
促進したい場合には重水冷却系の重水循環ポンプ４、重
水冷却器５からカランドリアタンク３に向かう重水を分
岐して、重水浄化系の過酸化重水素分解塔６、低温化熱
交換器７、重水浄化用ポンプ８、重水浄化塔９を経たの
ち、ポイズン濃度制御系のポイズン除去用陽イオン交換
塔１０を経由させた後、再びカランドリアタンク３に向
かう重水に合流させて、カランドリアタンク３内のＩＯ
Ｂ ３４濃度を減少させている。なお、劣化した重水は
重水化基１１を経て劣化重水貯槽１２に一旦貯えられた
後、重水精製系１３で精製され、重水貯槽１４から重水
補給ポンプ１５によりカランドリアタンク３に向かう重
水に合流させて再利用できるようにしている。In heavy water-moderated, light-water-cooled pressure tube reactors, reactivity compensation due to fuel combustion is performed by controlling the concentration of poison dissociated as ions in heavy water. The system diagram of this heavy water system is shown in Figure 2, and briefly explained as follows.
If it is desired to suppress the reactivity, the concentration of 10B3+ in the calandria tank 3 is increased by adding the concentrated boric acid solution in the poison adjustment tank 1 to the heavy water supplied to the calandria tank 3 by the poison injection pump 2. On the other hand, if it is desired to promote the reactivity, the heavy water flowing from the heavy water circulation pump 4 and heavy water cooler 5 of the heavy water cooling system to the calandria tank 3 is branched, and the heavy water is sent to the deuterium peroxide decomposition tower 6 of the heavy water purification system to lower the temperature. After passing through a heat exchanger 7, a heavy water purification pump 8, and a heavy water purification tower 9, the water passes through a cation exchange tower 10 for removing poison in a poison concentration control system, and then joins with heavy water headed for the calandria tank 3 again. , IO in Calandria Tank 3
B34 concentration is decreased. Note that the degraded heavy water is temporarily stored in the degraded heavy water storage tank 12 via the heavy water converting group 11, and then purified in the heavy water purification system 13, and is merged with the heavy water heading from the heavy water storage tank 14 to the calandria tank 3 by the heavy water replenishment pump 15. and can be reused.
上記の如く、重水中にイオンとして解離しているポイズ
ンの濃度をイオン交換樹脂による吸着で制御する方式で
は、イオン交換樹脂は高温では使用できないから低温化
熱交換器７で重水温度を下げざるを得す、これは熱経済
上大きな損失であった。またイオン交換樹脂は過酸化重
水素により性能が劣化するので、過酸化重水素分解塔６
の設置を余儀なくされた。更にイオン交換樹脂は放射線
により破壊されて微細化するため、充填しているイオン
交換樹脂を交換する必要が生じ、反復利用には限界があ
った。また、イオン交換塔１０（ポイズン除去塔）を再
生するには酸、塩基の洗浄液を使うし、新樹脂の塔内へ
の装荷時における重水化のためにも多くの時間と廃薬液
、廃重水を生じることになった。
この発明の目的とするところは、１０３３をイオンの形
としてポイズン濃度制御していたことによって派生した
上記従来の欠点を解消する新規な出力制御法を提供する
ことにある。As mentioned above, in the method of controlling the concentration of poisons dissociated as ions in heavy water by adsorption by ion exchange resin, the temperature of the heavy water must be lowered by the low temperature heat exchanger 7 because the ion exchange resin cannot be used at high temperatures. Unfortunately, this was a big loss in terms of thermoeconomics. In addition, since the performance of ion exchange resin deteriorates due to deuterium peroxide, the deuterium peroxide decomposition tower 6
was forced to install. Furthermore, since the ion exchange resin is destroyed by radiation and becomes fine, it becomes necessary to replace the filled ion exchange resin, which limits its repeated use. In addition, acid and base cleaning solutions are used to regenerate the ion exchange tower 10 (poison removal tower), and it takes a lot of time and waste chemical solution and waste heavy water to convert into heavy water when loading new resin into the tower. This resulted in the occurrence of An object of the present invention is to provide a novel output control method that eliminates the above-mentioned drawbacks of the conventional method resulting from controlling the poison concentration using 1033 in the form of ions.
上記目的を達成するこの発明の重水減速軽水冷却圧力管
型原子炉の出力制御法は、重水中でイオン化しない化学
的に安定なポイズン微粒子を重水減速材中に分散して供
給し、この減速材中のポイズン粒子をフィルターで除去
して重水減速材中のポイズン濃度をＩＩＩａｌｉｌする
ようにしたものである。The power control method for a heavy water-moderated, light-water-cooled pressure tube nuclear reactor according to the present invention, which achieves the above object, supplies chemically stable poison particles that do not ionize in heavy water dispersed in a heavy water moderator. The poison particles in the heavy water moderator are removed by a filter to reduce the poison concentration in the heavy water moderator.
重水減速材中のポイズン微粒子を増加すると燃料の燃焼
反応が抑制され、原子炉の出力が低下する。逆にポイズ
ン微粒子をフィルターで除去して重水減速材中のポイズ
ン微粒子を減少すると燃料の燃焼反応が促進され、原子
炉の出力が上がる。ポイズン微粒子は物理的な捕獲手段
であるフィルターで除去するので、高温重水を冷却した
りする必要は全くない。Increasing the amount of poison particles in the heavy water moderator suppresses the combustion reaction of the fuel and reduces the output of the reactor. Conversely, if the poison particles in the heavy water moderator are reduced by removing them with a filter, the combustion reaction of the fuel will be accelerated and the output of the reactor will increase. Poison particles are removed by a filter, which is a physical capture means, so there is no need to cool the high-temperature heavy water.
第１図に示したこの発明の重水減速軽水冷却圧力管型原
子炉の出力制御法に係る重水系統図に基ずいて説明する
と、この重水系には重水中でイオン化しない化学的に安
定なポイズン微粒子が分散混入されている。かかるポイ
ズン微粒子は１０Ｂ又はＧｄの化学的に安定な形の例え
ば１０８Ｎ、”’８４ Ｃ，Ｇｄ２Ｏ３等の微粒状をな
すものである。
一般に重水減速軽水冷却圧力管型原子炉では高々数ｐｐ
ｍ程度の１０Ｂ濃度であるから、混入したポイズン微粒
子の沈澱、局所化等は差したる問題とはならないが、重
水の比重に近いものが好ましいといえる。
ポイズン濃度を増すためポイズン微粒子を重水中に供給
するには、ポイズン調整槽１の液をポイズン注入ポンプ
２によりカランドリアタンク３に供給される重水に加え
る。この点では従来と格別変りはない。しかし、ポイズ
ン濃度を減すためポイズン微粒子を重水中から除去する
には、重水冷却系から分岐して重水浄化系の重水浄化用
ポンプ８、重水浄化塔９を経たものを、ポイズン濃度制
御系のフィルター１６を通した後、再びカランドリアタ
ンク３に向かう重水に合流させるのである。これを第２
図の場合と対比すると、過酸化重水素分解塔６、低温化
熱交換器７は削除され、ポイズン除去用のイオン交換塔
１０の代りにフィルター１６を設置していて、重水を冷
却することなく高温のままでポイズン微粒子を除去して
いる点が顕著な相違点となっている。
フィルター１６の再生並びにフィルター１６で捕集され
たポイズン微粒子の回収は重水にょる逆洗によって可能
であり、再生のための廃重水発生量は僅かである。再生
されたフィルター１６および回収したポイズン微粒子が
繰返し再利用されることについてはいうまでもない。To explain based on the heavy water system diagram related to the output control method of the heavy water moderated light water cooled pressure tube reactor of the present invention shown in Fig. 1, this heavy water system contains chemically stable poisons that do not ionize in heavy water. Fine particles are dispersed and mixed. Such poison particles are chemically stable forms of 10B or Gd, such as 108N, '84C, Gd2O3, etc. Generally, in a heavy water-moderated light water-cooled pressure tube reactor, the amount of poison is at most several ppm.
Since the concentration of 10B is approximately 100 m, precipitation and localization of mixed poison particles will not be a major problem, but it can be said that a specific gravity close to that of heavy water is preferable. To supply poison particles into heavy water to increase the poison concentration, the liquid in the poison adjustment tank 1 is added to the heavy water supplied to the calandria tank 3 by the poison injection pump 2. In this respect, there is no particular difference from the conventional method. However, in order to remove poison particulates from heavy water in order to reduce the poison concentration, the heavy water that branches off from the heavy water cooling system and passes through the heavy water purification pump 8 and the heavy water purification tower 9 of the heavy water purification system is transferred to the poison concentration control system. After passing through the filter 16, it is made to join the heavy water heading towards the calandria tank 3 again. This is the second
In contrast to the case shown in the figure, the deuterium peroxide decomposition tower 6 and the low-temperature heat exchanger 7 are removed, and a filter 16 is installed in place of the ion exchange tower 10 for removing poison, so that heavy water is not cooled. A notable difference is that poison particles are removed while the temperature remains high. The filter 16 can be regenerated and the poison particles collected by the filter 16 can be recovered by backwashing with heavy water, and the amount of waste heavy water generated for regeneration is small. It goes without saying that the regenerated filter 16 and the collected poison particles are repeatedly reused.
以上の説明から明らかなように、この発明の方法は、重
水中でイオン化しない化学的に安定なポイズン粒子を重
水減速材中に分散して供給し、この減速材中のポイズン
粒子をフィルターで除去して重水減速材中のポイズン濃
度を制御するようにしたから、重水が高温でも何の支障
もなくポイズン除去が行え、低温化熱交換器は省略でき
、熱損失をなくせる。また、フィルターの捕獲分離性能
は過酸化重水素によって左右されないから過酸化重水素
分解塔も省略できる。
更にフィルターの再生は重水で逆洗すればよく、格別の
薬液を必要としないから座薬液、廃重水はなくなるし、
ポイズン微粒子の回収がほぼ完全にでき、それは繰返し
再利用できるから、交換補充の必要は、殆ど考えなくて
よい。加えてイオン交換樹脂の場合は低イオン濃度にな
るとイオン交換ができなくなったが、フィルターによる
濾過回収では低ポイズン濃度でも良好な除去効率をもっ
てポイズン微粒子の除去を行える。As is clear from the above explanation, the method of the present invention involves dispersing and supplying chemically stable poison particles that do not ionize in heavy water into a heavy water moderator, and removing the poison particles in the moderator with a filter. Since the concentration of poison in the heavy water moderator is controlled by using this method, poison can be removed without any problem even if the heavy water is at a high temperature, a low temperature heat exchanger can be omitted, and heat loss can be eliminated. Furthermore, since the capture and separation performance of the filter is not influenced by deuterium peroxide, a deuterium peroxide decomposition column can also be omitted. Furthermore, the filter can be regenerated by simply backwashing it with heavy water, and no special chemicals are required, so there is no need for suppositories or waste heavy water.
Since the poison particles can be almost completely recovered and can be reused repeatedly, there is almost no need for replacement and replenishment. In addition, in the case of ion exchange resins, ion exchange becomes impossible when the ion concentration is low, but with filtration and recovery using a filter, poison particles can be removed with good removal efficiency even at low poison concentrations.
第１図は、この発明の重水減速軽水冷却圧力管型原子炉
の出力制御法に係る重水系統図、第２図は、従来の重水
減速軽水冷却圧力管型原子炉の出力制御法に係る重水系
統図である。Figure 1 is a heavy water system diagram related to the power control method for a heavy water moderated, light water cooled pressure tube reactor of the present invention, and Figure 2 is a heavy water system diagram related to the power control method for a conventional heavy water moderated, light water cooled pressure tube reactor. It is a system diagram.
Claims (1)
子を重水減速材中に分散して供給し、この減速材中のポ
イズン粒子をフィルターで除去して重水減速材中のポイ
ズン濃度を制御することを特徴とする重水減速軽水冷却
圧力管型原子炉の出力制御法。1. Controlling the poison concentration in the heavy water moderator by dispersing and supplying chemically stable poison particles that do not ionize in heavy water and removing the poison particles in the moderator with a filter. A power control method for a heavy water-moderated, light-water-cooled pressure tube reactor characterized by:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1108948A JPH0795107B2 (en) | 1989-04-27 | 1989-04-27 | Power Control Method for Heavy Water Moderated Light Water Cooled Pressure Tube Reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1108948A JPH0795107B2 (en) | 1989-04-27 | 1989-04-27 | Power Control Method for Heavy Water Moderated Light Water Cooled Pressure Tube Reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH02287193A true JPH02287193A (en) | 1990-11-27 |
| JPH0795107B2 JPH0795107B2 (en) | 1995-10-11 |
Family
ID=14497706
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1108948A Expired - Fee Related JPH0795107B2 (en) | 1989-04-27 | 1989-04-27 | Power Control Method for Heavy Water Moderated Light Water Cooled Pressure Tube Reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0795107B2 (en) |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS57141595A (en) * | 1981-02-25 | 1982-09-01 | Tokyo Shibaura Electric Co | Nuclear reactor control device |
| JPS58100791A (en) * | 1981-12-11 | 1983-06-15 | 株式会社日立製作所 | Moderator cleaning system of heavy water reactor |
-
1989
- 1989-04-27 JP JP1108948A patent/JPH0795107B2/en not_active Expired - Fee Related
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS57141595A (en) * | 1981-02-25 | 1982-09-01 | Tokyo Shibaura Electric Co | Nuclear reactor control device |
| JPS58100791A (en) * | 1981-12-11 | 1983-06-15 | 株式会社日立製作所 | Moderator cleaning system of heavy water reactor |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0795107B2 (en) | 1995-10-11 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| LAPS | Cancellation because of no payment of annual fees |