JPH01199191A - Nuclear reactor - Google Patents
Nuclear reactorInfo
- Publication number
- JPH01199191A JPH01199191A JP63024170A JP2417088A JPH01199191A JP H01199191 A JPH01199191 A JP H01199191A JP 63024170 A JP63024170 A JP 63024170A JP 2417088 A JP2417088 A JP 2417088A JP H01199191 A JPH01199191 A JP H01199191A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- control rods
- control rod
- rods
- control
- 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
- 239000011358 absorbing material Substances 0.000 claims abstract description 13
- 229910052735 hafnium Inorganic materials 0.000 claims abstract description 6
- VBJZVLUMGGDVMO-UHFFFAOYSA-N hafnium atom Chemical compound [Hf] VBJZVLUMGGDVMO-UHFFFAOYSA-N 0.000 claims abstract description 6
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 claims abstract description 3
- 229910052796 boron Inorganic materials 0.000 claims abstract description 3
- 239000000446 fuel Substances 0.000 claims description 63
- 230000000712 assembly Effects 0.000 claims description 18
- 238000000429 assembly Methods 0.000 claims description 18
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 abstract description 3
- 229910052580 B4C Inorganic materials 0.000 abstract description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 21
- 238000009835 boiling Methods 0.000 description 14
- 238000002485 combustion reaction Methods 0.000 description 8
- 230000007423 decrease Effects 0.000 description 7
- 238000001228 spectrum Methods 0.000 description 6
- 229910052770 Uranium Inorganic materials 0.000 description 3
- 239000002826 coolant Substances 0.000 description 3
- 238000001816 cooling Methods 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 239000002901 radioactive waste Substances 0.000 description 3
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 3
- 239000000463 material Substances 0.000 description 2
- 239000006096 absorbing agent Substances 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000003780 insertion Methods 0.000 description 1
- 230000037431 insertion Effects 0.000 description 1
- 229920006395 saturated elastomer Polymers 0.000 description 1
- 230000005514 two-phase flow Effects 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
Description
【発明の詳細な説明】
［ａ業上の利用分野］
本発明は、原子炉に係り、特に高燃焼度の沸騰水型原子
炉として好適な原子炉に関する。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a nuclear reactor, and particularly to a nuclear reactor suitable as a high burnup boiling water reactor.
［従来の技術］
沸騰水型原子炉においては、減速材と冷却材の働きをす
る水が、チャンネルボックス内側の２相流部分と、チャ
ンネルボックス外側の飽和水部分の２つの領域に分かれ
て存在する。現行の限られた空間の中で、これら２つの
領域の面積割合に対する最適値は、評価する対象により
異なる。[Prior art] In a boiling water reactor, water that acts as a moderator and coolant exists in two regions: a two-phase flow region inside the channel box and a saturated water region outside the channel box. do. In the current limited space, the optimal value for the area ratio of these two regions varies depending on the target to be evaluated.
沸騰水型原子炉において、燃料の高燃焼度化を図り燃料
の寿命延長、省クラン等の対策を通じて燃料経済性を向
上させるには、燃料集合体の中に非沸騰領域つまり多数
本のクォータロッドを配置する方法（この−例として特
開昭６１−１１８６８９号公報は、燃料集合体内のクォ
ータロッドの本数を増加させ、また、制御棒を燃料集合
体の１つのコーナ部にのみ直接隣接するように配置した
沸騰水型原子炉を開示している。）、燃料集合体内のウ
ラン装荷量を従来より増加させる方法、格子の構成数を
増加させる方法などが考えられる。In a boiling water reactor, in order to improve fuel economy through measures such as increasing the burnup of the fuel, extending the fuel life, and reducing combustion, it is necessary to create a non-boiling region in the fuel assembly, that is, a large number of quarter rods. (For example, Japanese Patent Application Laid-Open No. 118689/1989 discloses a method of arranging control rods by increasing the number of quarter rods in the fuel assembly and placing the control rods directly adjacent to only one corner of the fuel assembly. ), a method of increasing the amount of uranium loaded in the fuel assembly compared to the conventional method, a method of increasing the number of lattice structures, etc. can be considered.
［発明が解決しようとする課題］
しかしながら、従来のチャンネルボックスの大きさで燃
料集合体の中に多数本のクォータロッドを配置すると、
ぬれぶち面積の増加と冷却材流路面積の減少で、圧損が
大幅に上昇するとともに、燃料棒間隔接近により、冷却
能力が低下する問題がある。また、従来のチャンネルボ
ックスの大きさでウラン装荷量を増加させると、冷却材
による圧損の増加と冷却能力の低下を招くことになる。[Problem to be solved by the invention] However, when a large number of quarter rods are arranged in a fuel assembly with the size of a conventional channel box,
An increase in the wetted area and a decrease in the area of the coolant flow path causes a significant increase in pressure loss, and there is a problem in that the cooling capacity decreases due to the closer spacing of the fuel rods. In addition, increasing the amount of uranium loaded with the conventional channel box size will result in an increase in pressure loss due to the coolant and a decrease in cooling capacity.
また、従来のチャンネルボックスの大きさで格子の構成
数を増加させると、やはり圧損の増加と冷却能力の低下
は避けられなかった。Furthermore, when increasing the number of grids in a conventional channel box, an increase in pressure loss and a decrease in cooling capacity were unavoidable.
特開昭８１−１１８６８９号公報に示された沸騰水型原
子炉は、ある程度の燃料経済性の向上及び高燃焼度化を
図ることができるが、しかし、現時点においては、燃焼
度が７０ＧＷｄ／を程度に達する高燃焼度の原子炉（高
燃焼炉）が要求されており、上記の従来技術を適用して
もこの課題の達成は不可能である。The boiling water reactor disclosed in Japanese Patent Application Laid-open No. 81-118689 can improve fuel economy to some extent and achieve a high burnup, but at present, the burnup is less than 70 GWd/. There is a need for a nuclear reactor (high burnup reactor) with a high burnup that can reach a certain level, and it is impossible to achieve this goal even by applying the above-mentioned conventional technology.
高燃焼炉を実現するためには、燃料集合体中のウォータ
ロッド領域をさらに増加させ中性子スペクトルを一層ソ
フト（熱中性子の平均速度を遅くする）にする必要があ
る。従来の燃料集合体の大きさのままで、ウォータロッ
ド領域を増加する場合には、その分だけ燃料集合体当り
のウラン装荷量が減少してしまい、燃料経済性の向上が
あまり期待できないと言う問題があった。特開昭６１−
１１８８１３９号公報の沸騰水型原子炉も、燃料集合体
内のつオータロラドを増して中性子スペクトルのソフト
化を図るものであるが、達成できる燃焼度は約４０ Ｇ
Ｗｄ／を程度が限界となる
また、高燃焼炉では、燃料集合体の濃縮度がさらに高く
なるので中性子スペクトルが従来よりも硬化する。従っ
て、特開昭６１−１１８６８９号公報の構造を高燃焼炉
に適用した場合には、制御棒価値が不足する。高燃焼炉
の実現のためには、核***性物質の濃縮度の増大に伴う
中性子スペクトルの硬化による制御棒価値の低下に対す
る対策及び硬化した中性子スペクトルのソフト化に対す
る対策が必要である。In order to realize a high combustion reactor, it is necessary to further increase the water rod area in the fuel assembly and to soften the neutron spectrum (lower the average velocity of thermal neutrons). If the water rod area is increased while the size of the conventional fuel assembly remains the same, the amount of uranium loaded per fuel assembly will decrease by that amount, making it difficult to expect much improvement in fuel economy. was there. Unexamined Japanese Patent Publication 1986-
The boiling water reactor disclosed in Publication No. 1188139 also aims to soften the neutron spectrum by increasing the number of autororads in the fuel assembly, but the burnup that can be achieved is approximately 40 G.
In addition, in a high combustion furnace, the enrichment degree of the fuel assembly becomes even higher, so that the neutron spectrum becomes harder than in the past. Therefore, when the structure of JP-A-61-118689 is applied to a high combustion reactor, the control rod value is insufficient. In order to realize a high combustion reactor, it is necessary to take measures against the decrease in the value of control rods due to the hardening of the neutron spectrum due to the increase in the enrichment of fissile material, and against the softening of the hardened neutron spectrum.
さらに、高燃焼炉においては、各サイクルでの運転日数
として現行沸騰水型原子炉の１２ケ月の１．５倍の１８
ケ月運転が考えられている。そのため、放射性廃棄物と
なる使用済み制御棒の発生本数を低減させる必要がある
。Furthermore, high combustion reactors require 18 days of operation in each cycle, which is 1.5 times the 12 months of current boiling water reactors.
Monthly driving is being considered. Therefore, it is necessary to reduce the number of used control rods that become radioactive waste.
本発明の目的は、十分な制御棒価値を有し、且つ、使用
済制御棒の発生本数を低減させ且高燃焼化を可能にした
原子炉を提供することにある。An object of the present invention is to provide a nuclear reactor that has sufficient control rod value, reduces the number of spent control rods, and enables high burnup.
［課題を解決するための手段］
本発明は、複数の燃料集合体が装荷されてなる炉心と、
前記炉心内の前記燃料集合体間に挿入される複数の断面
十字型の制御棒とを有し、前記夫々の燃料集合体の対角
線方向に対向する２つのコーナ部に直接隣接するように
前記制御棒がそれぞれ配置され、夫々４体の前記燃料集
合体の上端部が挿入される大きさの升目を有する格子状
の上部炉心支持部材を設けた原子炉において、前記燃料
集合体に直接隣接する前記制御棒のうち、自身の上方に
前記上部炉心支持部材が存在する制御棒を原子炉停止用
制御棒とし、その中性子吸収材としてホウ素を用い、他
方、自身の上方に前記上部炉心支持部材が存在しない制
御棒を原子炉出力調節用制御棒とし、その中性子吸収材
としてハフニウムを用いたことを特徴とする。[Means for Solving the Problems] The present invention provides a reactor core loaded with a plurality of fuel assemblies,
a plurality of control rods having a cross-shaped cross section inserted between the fuel assemblies in the reactor core, and the control rods are arranged so as to be directly adjacent to two diagonally opposite corners of each of the fuel assemblies. In a nuclear reactor provided with a lattice-like upper core support member in which rods are arranged and each has a grid-like square having a size into which the upper end portions of the four fuel assemblies are inserted, Among the control rods, the control rod in which the upper core support member exists above itself is used as a control rod for reactor shutdown, boron is used as its neutron absorbing material, and on the other hand, the above-mentioned upper core support member exists above itself. The main feature of this system is that the control rods used in this system are used as control rods for adjusting the reactor output, and hafnium is used as the neutron absorbing material.
［作 用］
燃料集合体の対角線方向に対向する２つのコーナ部に直
接隣接するように断面十字型の制御棒がそれぞれ配置さ
れるので、この十字型の制御棒を構成するブレードの翼
長を長くでき、制御棒価値を増加できる。[Function] Since control rods each having a cross-shaped cross section are arranged directly adjacent to two diagonally opposite corners of the fuel assembly, the wing length of the blades constituting this cross-shaped control rod can be It can be lengthened and the control rod value can be increased.
中性子照射量の多い原子炉出力調節用制御棒には、交換
が容易にできる上部炉心支持部材下にない制御棒を用い
る。この制御棒の中性子吸収材はＨｅ （ハフニウム
）なので、従来の８４Ｇ制御棒に比較して、約３〜５倍
の寿命を持ち、従って、運転期間の長い高燃焼炉におい
ても使用済み制御棒（放射性廃棄物）の発生本数を低減
できる。Control rods that are not located under the upper core support member and can be easily replaced are used as control rods for adjusting reactor power that receive a large amount of neutron irradiation. Since the neutron absorbing material of this control rod is He (hafnium), it has a lifespan approximately 3 to 5 times longer than that of a conventional 84G control rod. It is possible to reduce the number of radioactive waste (radioactive waste) generated.
上部炉心支持部材下にある制御棒は交換しにくいので、
出力運転時に使用しないで炉停止用にのみ使用する制御
棒とする。従って、原子炉が寿命（３０〜４０年）にな
るまで使用しても、この制御棒の受ける中性子照射量は
、出力調節用制御棒が寿命中に受ける照射量より約２相
手さい。この制御棒としては、冷温時でも十分大きな制
御棒価値を与える８４Ｃ（ボロンカーバイト）制御棒が
適している。更に、８４Ｇ制御棒は、Ｈｅ制御棒に比べ
、吸収材のコストが安く、さらに、重量も軽いので、制
御棒駆動系に対する負担も少さく、制御棒駆動系を単純
化できる可能性もある。The control rods under the upper core support member are difficult to replace, so
The control rod is not used during power operation and is used only for reactor shutdown. Therefore, even if the reactor is used until the end of its lifespan (30 to 40 years), the amount of neutron irradiation received by the control rods is about 2 times the amount of irradiation received by the power adjustment control rods during their lifespan. As this control rod, an 84C (boron carbide) control rod is suitable as it provides a sufficiently large control rod value even in cold temperatures. Furthermore, compared to He control rods, 84G control rods have lower absorption material costs and are also lighter in weight, so there is less burden on the control rod drive system, and there is a possibility that the control rod drive system can be simplified.
［実施例］
沸騰水型原子炉に適用した本発明の好適な一実施例を図
面に基づいて説明する。[Embodiment] A preferred embodiment of the present invention applied to a boiling water reactor will be described based on the drawings.
本実施例の沸騰水型原子炉は、第２図に示すように、原
子炉圧力容器１０、燃料集合体ＩＡを装荷してなる炉心
１１及びインターナルポンプ１６を有している。炉心シ
ュラウド１２が、原子炉圧力容器１０内に配置されて原
子炉圧力容器１０に取付けられている。インターナルポ
ンプ１６は原子炉圧力容器１０と炉心シュラウド１２と
の間に配置され、原子炉圧力容器１０の底部に設置され
る。炉心下部支持板１３は、炉心シュラウド１２の下端
部に取付けられ、しかも炉心シュラウド１２内に配置さ
れる。複数の燃料支持金具１５が炉心下部支持板１３を
貫通して炉心下部支持板１３に設置される。他方、上部
格子板１４が炉心シュラウド１２内に配置され、炉心シ
ュラウド１２に取付けられる。炉心下部支持板１３より
下方の下部ブレナム１７内に、多数の制御棒案内管１８
が設置されている。制御棒駆動装置ハウジング１９が、
原子炉圧力容器１０の底部に取付けられている。制御棒
５Ａ、５Ｂは、該当する制御棒案内管１８内に設置され
、制御棒駆動装置ハウジング１９内に設置された制御棒
駆動装置（図示せず）に連絡されている。２０は気水分
離器、２１はドライヤである。As shown in FIG. 2, the boiling water reactor of this embodiment includes a reactor pressure vessel 10, a reactor core 11 loaded with fuel assemblies IA, and an internal pump 16. A core shroud 12 is disposed within and attached to the reactor pressure vessel 10 . Internal pump 16 is disposed between reactor pressure vessel 10 and reactor core shroud 12 and installed at the bottom of reactor pressure vessel 10 . The core lower support plate 13 is attached to the lower end of the core shroud 12 and is disposed within the core shroud 12 . A plurality of fuel support fittings 15 pass through the core lower support plate 13 and are installed on the core lower support plate 13 . On the other hand, an upper grid plate 14 is disposed within and attached to core shroud 12 . A large number of control rod guide tubes 18 are installed in the lower brenum 17 below the core lower support plate 13.
is installed. The control rod drive housing 19 is
It is attached to the bottom of the reactor pressure vessel 10. The control rods 5A, 5B are installed in the corresponding control rod guide tubes 18 and communicated with a control rod drive (not shown) installed in the control rod drive housing 19. 20 is a steam/water separator, and 21 is a dryer.
炉心１１内における燃料集合体ＩＡ及び制御棒５Ａ及び
５Ｂの配置関係を第３図により説明する。第３図に示す
ように、燃料集合体ＩＡの対向する一対のコーナ部に面
した位置に２本の十字型の制御棒５Ａ及び５Ｂが挿入さ
れる。すべての制御棒５Ａ及び５Ｂが炉心１１内に挿入
された時、炉心１１内の燃料集合体ＩＡは、２本の制御
棒５Ａ及び５Ｂによって直接挟まれる形となる。The arrangement relationship of the fuel assembly IA and the control rods 5A and 5B in the reactor core 11 will be explained with reference to FIG. As shown in FIG. 3, two cross-shaped control rods 5A and 5B are inserted at positions facing a pair of opposing corners of the fuel assembly IA. When all the control rods 5A and 5B are inserted into the reactor core 11, the fuel assembly IA in the reactor core 11 is directly sandwiched between the two control rods 5A and 5B.
燃料集合体ＩＡは、特開昭６１−１１１１６８９号公報
の沸騰水型原子炉で使用される燃料集合体６（破線で表
示）に対して一辺の長さで約ｆｆ倍、横断面積で２倍に
大型化されている。本実施例での制御棒の配列ピッチは
、特開昭６１−１１８６８９号公報の沸騰水型原子炉の
制御棒７（破線）の配列ピッチと同一である。しかし、
燃料集合体ＩＡならびに制御棒５Ａ及び５Ｂの配置角度
は、従来の燃料集合体６および制御棒７に対して４５°
回転させている。The fuel assembly IA is approximately ff times the length of one side and twice the cross-sectional area of the fuel assembly 6 (indicated by a broken line) used in the boiling water reactor of JP-A No. 61-1111689. It has been enlarged to. The arrangement pitch of the control rods in this embodiment is the same as the arrangement pitch of the control rods 7 (broken line) of a boiling water reactor disclosed in Japanese Patent Application Laid-open No. 118689/1989. but,
The arrangement angle of the fuel assembly IA and control rods 5A and 5B is 45° with respect to the conventional fuel assembly 6 and control rods 7.
It's rotating.
次に、本実施例に用いられる燃料集合体ＩＡの詳細構造
を第４図により説明する。燃料集合体ＩＡは横断面が正
方形状をしている角筒であるチャンネルボックス４内に
多数の燃料棒３及び９木の大径のクォータロッド２を配
置することによ？て構成される。燃料集合体ＩＡは、図
示されていないが上部タイブレート及び下部タイプレー
トを有している。燃料棒３及びウォータロッド２の両端
部は、上部及び下部タイブレートに保持される。チャン
ネルボックス４は、上部タイブレートに取付けられる。Next, the detailed structure of the fuel assembly IA used in this embodiment will be explained with reference to FIG. The fuel assembly IA is constructed by arranging a large number of fuel rods 3 and nine large-diameter quarter rods 2 in a channel box 4, which is a rectangular tube with a square cross section. It consists of Although not shown, the fuel assembly IA has an upper tie plate and a lower tie plate. Both ends of the fuel rod 3 and water rod 2 are held by upper and lower tie plates. Channel box 4 is attached to the upper tie plate.
燃料棒３は、１４行１４列に等間隔で配置されている。The fuel rods 3 are arranged at equal intervals in 14 rows and 14 columns.
９本のウォータロッド２の各々の横断面積は４本の燃料
棒３内の横断面積を合計したものよりも大きい。本実施
例の燃料集合体ＩＡのチャンネルボックス４の内側の幅
は２０１ｍｍであり、特開昭６１−１１８６８９号公報
の燃料集合体のそれ（１３４ｍｍ）の約７丁倍になって
いる。The cross-sectional area of each of the nine water rods 2 is larger than the sum of the cross-sectional areas within the four fuel rods 3. The inner width of the channel box 4 of the fuel assembly IA of this embodiment is 201 mm, which is approximately seven times as wide as that (134 mm) of the fuel assembly disclosed in Japanese Patent Application Laid-Open No. 118689/1989.
本実施例の燃料集合体ＩＡは、現行の沸騰水型原子炉の
標準仕様である制御棒の配列ピッチ内に納まる程度の大
きさにすることができる。従って、現行の沸騰水型原子
炉の制御棒ピッチを変えることなく、燃料集合体ＩＡを
特開昭６１−１１８６８９号公報に示す従来の燃料集合
体の約２体分の大きさにすることができる。この燃料集
合体ＩＡを用いることにより、従来の燃料集合体が炉心
に配置された時に生ずる燃料集合体相互間の水領域の一
部分の面積を燃料集合体ＩＡ内に取込むことができ、そ
の取り込んだ分をクォータロッド領域の増加として使用
できるので、従来に比べて高燃焼度化を実現し得る。The fuel assembly IA of this embodiment can be made large enough to fit within the control rod array pitch that is the standard specification for current boiling water reactors. Therefore, without changing the control rod pitch of the current boiling water reactor, it is possible to make the fuel assembly IA approximately twice the size of the conventional fuel assembly shown in JP-A-61-118689. can. By using this fuel assembly IA, it is possible to incorporate into the fuel assembly IA a part of the water area that occurs between the fuel assemblies when conventional fuel assemblies are placed in the reactor core. Since the surplus can be used to increase the quarter rod area, it is possible to achieve higher burnup than in the past.
現行の沸騰水型原子炉の炉心の制御棒ピッチは、約３０
５ｍｍ〜３１０ｍｍである。この寸法に制御棒挿入に必
要な燃料集合体Ｉ人相互間に形成される間隙の幅約１３
ａ＋ｍとチャンネルボックスの肉厚的２ｍｍ〜３ｍｍを
考慮すると、チャンネルボックス４の内側の幅は約１９
６ｍｍ 〜２０２ｍ＋ａとなる。The control rod pitch of the core of current boiling water reactors is approximately 30
The length is 5 mm to 310 mm. With this dimension, the width of the gap formed between fuel assemblies I required for control rod insertion is approximately 13
Considering a + m and the wall thickness of the channel box of 2 mm to 3 mm, the inner width of the channel box 4 is approximately 19
6mm to 202m+a.
本実施例における制御棒５Ａ及び５Ｂと前記の上部格子
板１４（第２図）との位置関係を第１図に示す、上部格
子板１４は、多数の升目２５を形成している。この各升
目２５内に、隣接する４体の燃料集合体ＩＡの上端部が
挿入される。制御棒５Ｂは、１つの升目２５内に挿入さ
れた４体の燃料集合体ＩＡ間に配置され、制御棒駆動装
置にて下方よりこれらの燃料集合体ＩＡ間に挿入される
。制御棒５Ｂの上方には上部格子板１４が存在しない。The positional relationship between the control rods 5A and 5B and the above-mentioned upper grid plate 14 (FIG. 2) in this embodiment is shown in FIG. 1. The upper grid plate 14 forms a large number of squares 25. The upper ends of four adjacent fuel assemblies IA are inserted into each square 25. The control rod 5B is arranged between four fuel assemblies IA inserted into one square 25, and is inserted between these fuel assemblies IA from below by a control rod drive device. There is no upper grid plate 14 above the control rod 5B.
炉心１１内に装荷された燃料集合体ＩＡ相互間の間隙の
幅は、前述したように約１３ｍｍである。このため、升
目２５内に挿入された燃料集合体ＩＡは、上部格子板１
４の側面に接触している。また、上部格子板１４の真下
には制御棒５Ａが配置される。この制御棒５Ａの周囲に
は、上部格子板１４の異なる４つの升目２５に挿入され
た画体の燃料集合体ＩＡが隣接する。制御棒５Ａ及び５
Ｂとも、断面十字型をしており、軸心から互いに直角の
角度で放射状に延びる４枚のブレードを有している。こ
れらのブレード内に中性子吸収材が設置されている。As described above, the width of the gap between the fuel assemblies IA loaded in the core 11 is about 13 mm. Therefore, the fuel assembly IA inserted into the square 25 is
It is in contact with the side of 4. Furthermore, a control rod 5A is arranged directly below the upper grid plate 14. The control rod 5A is surrounded by adjacent fuel assemblies IA inserted into four different squares 25 of the upper grid plate 14. Control rods 5A and 5
Both blades B have a cross-shaped cross section and have four blades extending radially from the axis at right angles to each other. Neutron absorbers are installed within these blades.
制御棒５Ｂは、その上方に上部格子板１４が存在しない
ので、新しい制御棒と容易に交換することができる。従
って、制御棒５Ｂは、中性子吸収材の消耗が激しい原子
炉出力調節用制御棒として用いられる。この原子炉出力
調節用制御棒は、運転時に炉心１１内に挿入されて原子
炉出力の調節制御のために引抜または挿入操作され、さ
らに原子炉を停止させる時に鎗炉心１１内に完全に挿入
される。この制御棒５Ｂの中性子吸収材として、ハフニ
ウム（Ｈｔ ）を用いる。Ｈｆを用いることにより制御
棒の長寿命化が可能となるため、高燃焼炉による運転日
数の増加によって問題となる使用済制御棒の増加を防ぐ
ことができる。Since the control rod 5B does not have the upper grid plate 14 above it, it can be easily replaced with a new control rod. Therefore, the control rod 5B is used as a control rod for adjusting the reactor power, in which the neutron absorbing material is severely consumed. These control rods for adjusting reactor power are inserted into the reactor core 11 during operation and are pulled out or inserted to control the adjustment of the reactor power, and are further inserted completely into the reactor core 11 when shutting down the reactor. Ru. Hafnium (Ht) is used as the neutron absorbing material for this control rod 5B. By using Hf, it is possible to extend the life of the control rods, so it is possible to prevent an increase in the number of spent control rods, which becomes a problem due to an increase in the number of operating days due to a high combustion furnace.
他方、制御棒５Ａは、その上方に上部格子板１４が存在
するので、炉心１１から取出して新しい制御棒と交換す
ることが困難である。このため、制御棒５Ａは、原子炉
が寿命になるまで使用される制御棒として用いる。従っ
て、制御棒５Ａは、原子炉を停止する時にのみ炉心１１
内に挿入される原子炉停止用制御棒として用いられる。On the other hand, since the upper grid plate 14 exists above the control rod 5A, it is difficult to take it out from the core 11 and replace it with a new control rod. For this reason, the control rod 5A is used as a control rod that is used until the reactor reaches the end of its life. Therefore, the control rods 5A are used in the core 11 only when stopping the reactor.
It is used as a control rod inserted into the reactor to shut down the reactor.
この制御棒５Ａの中性子吸収材として８４Ｃを用いる。84C is used as the neutron absorbing material for this control rod 5A.
Ｂ、Ｃを用いることにより、制御棒価値が大きく、十
分な炉停止余裕を有した高燃焼炉を実現できる。By using B and C, it is possible to realize a high combustion reactor with a large control rod value and sufficient reactor shutdown margin.
［発明の効果］
本発明によれば、高燃焼度化が可能で、しかも、高燃焼
度化による運転日数の長期化に伴う使用済み制御棒の発
生本数の増加を防ぎ、中性子スペクトルの硬化による制
御棒価値の低下にも十分対処できる原子炉が実現できる
。[Effects of the Invention] According to the present invention, it is possible to increase the burnup, prevent the increase in the number of spent control rods due to the increase in the number of operating days due to the increase in the burnup, and prevent the increase in the number of spent control rods due to hardening of the neutron spectrum. It is possible to create a nuclear reactor that can adequately cope with the decline in the value of control rods.
第１図は本発明の好適な一実施例である原子炉内での燃
料集合体と制御棒および上部炉心支持部材の配置関係を
示す平面図であって第２図の■−■で見た図、第２図は
本発明の一実施例である原子炉の縦断面図、第３図は第
２図のＩ−Ｉ断面図、第４図は上記実施例における燃料
集合体の詳細横断面図である。
ＩＡ・・・燃料集合体、２・・・クォータロッド、３・
・・燃料棒、 １０・・・原子炉圧力容器、１１・
・・炉心、 １３・・・炉心下部支持板、１４・
・・上部格子板、５Ａ・・・８４Ｃ制御棒、５Ｂ・・・
Ｈｆ制御棒。FIG. 1 is a plan view showing the arrangement of fuel assemblies, control rods, and upper core support members in a nuclear reactor according to a preferred embodiment of the present invention, as viewed from ■-■ in FIG. 2 is a vertical cross-sectional view of a nuclear reactor that is an embodiment of the present invention, FIG. 3 is a cross-sectional view taken along the line II in FIG. 2, and FIG. 4 is a detailed cross-sectional view of a fuel assembly in the above embodiment. It is a diagram. IA...fuel assembly, 2...quarter rod, 3.
...Fuel rod, 10...Reactor pressure vessel, 11.
... Core, 13 ... Core lower support plate, 14.
...Upper grid plate, 5A...84C control rod, 5B...
Hf control rod.
Claims (1)
内の前記燃料集合体間に挿入される複数の断面十字型の
制御棒とを有し、前記夫々の燃料集合体の対角線方向に
対向する２つのコーナ部に直接隣接するように前記制御
棒がそれぞれ配置され、夫々４体の前記燃料集合体の上
端部が挿入される大きさの升目を有する格子状の上部炉
心支持部材を設けた原子炉において、前記燃料集合体に
直接隣接する前記制御棒のうち、自身の上方に前記上部
炉心支持部材が存在する制御棒を原子炉停止用制御棒と
し、その中性子吸収材としてホウ素を用い、他方、自身
の上方に前記上部炉心支持部材が存在しない制御棒を原
子炉出力調節用制御棒とし、その中性子吸収材としてハ
フニウムを用いたことを特徴とする原子炉。A reactor core loaded with a plurality of fuel assemblies, and a plurality of control rods each having a cross-shaped cross section and inserted between the fuel assemblies in the core, and facing diagonally to each of the fuel assemblies. The control rods are arranged directly adjacent to the two corner portions of the fuel assembly, and each of the control rods is provided with a lattice-shaped upper core support member having a square size into which the upper end portions of the four fuel assemblies are inserted. In the nuclear reactor, among the control rods directly adjacent to the fuel assembly, a control rod in which the upper core support member is present above the control rod is used as a reactor shutdown control rod, and boron is used as the neutron absorbing material, On the other hand, a nuclear reactor characterized in that a control rod above which the upper core support member does not exist is used as a control rod for adjusting reactor power, and hafnium is used as a neutron absorbing material for the control rod.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63024170A JPH01199191A (en) | 1988-02-04 | 1988-02-04 | Nuclear reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63024170A JPH01199191A (en) | 1988-02-04 | 1988-02-04 | Nuclear reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH01199191A true JPH01199191A (en) | 1989-08-10 |
Family
ID=12130871
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63024170A Pending JPH01199191A (en) | 1988-02-04 | 1988-02-04 | Nuclear reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH01199191A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2001201582A (en) * | 2000-01-19 | 2001-07-27 | General Electric Co <Ge> | Fuel bundle/control rod assembly for reactor |
-
1988
- 1988-02-04 JP JP63024170A patent/JPH01199191A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2001201582A (en) * | 2000-01-19 | 2001-07-27 | General Electric Co <Ge> | Fuel bundle/control rod assembly for reactor |
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