JPH0242389A - Pressurized water reactor - Google Patents
Pressurized water reactorInfo
- Publication number
- JPH0242389A JPH0242389A JP63193271A JP19327188A JPH0242389A JP H0242389 A JPH0242389 A JP H0242389A JP 63193271 A JP63193271 A JP 63193271A JP 19327188 A JP19327188 A JP 19327188A JP H0242389 A JPH0242389 A JP H0242389A
- Authority
- JP
- Japan
- Prior art keywords
- control
- control rod
- neutron absorption
- rod assembly
- output
- 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
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims description 6
- 238000010521 absorption reaction Methods 0.000 claims description 48
- 230000000712 assembly Effects 0.000 claims description 21
- 238000000429 assembly Methods 0.000 claims description 21
- 238000009826 distribution Methods 0.000 abstract description 13
- 229910001220 stainless steel Inorganic materials 0.000 description 11
- 239000010935 stainless steel Substances 0.000 description 11
- 238000010586 diagram Methods 0.000 description 7
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 description 4
- 239000004327 boric acid Substances 0.000 description 4
- 230000009257 reactivity Effects 0.000 description 4
- 230000001939 inductive effect Effects 0.000 description 3
- 230000007423 decrease Effects 0.000 description 2
- 238000003780 insertion Methods 0.000 description 2
- 230000037431 insertion Effects 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 239000011358 absorbing material Substances 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 238000007865 diluting Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 238000004519 manufacturing process 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
- Monitoring And Testing Of 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、出力分布の歪を誘発することなく速い出力変
化に対応できるようにした加圧水型原子炉（以下ＰＷＲ
という）に関するものである。[Detailed Description of the Invention] [Industrial Application Field] The present invention provides a pressurized water reactor (hereinafter referred to as PWR) capable of responding to rapid power changes without inducing distortion in the power distribution.
).
ＰＷＲの出力制御に使用される制御棒は、Ａｇ−Ｉｎ−
Ｃｄ等の中性子吸収材をステンレス鋼等からなる被覆管
内に充填し、中性子吸収能力を軸方向均等に設定して構
成されており、１６本〜２４本の制御棒が制御棒集合体
（制御棒クラスタともいう）として制御棒駆動装置によ
り炉心内へ上方から挿入されるようになっている。この
ような制御棒を炉心内に挿入すると、炉心の軸方向出力
分布が変化し、所定の制限範囲内から逸脱することにな
る。このため、従来では一次冷却材中のホウ酸濃度を調
整するとともに制御棒クラスタの挿入位置を調整して出
力分布の歪を修正しているが、ホウ酸濃度の調整は時間
がかかるため、速い出力変化には対応できないという問
題があった。The control rods used for PWR output control are Ag-In-
A neutron absorbing material such as Cd is filled in a cladding tube made of stainless steel, etc., and the neutron absorption capacity is set evenly in the axial direction. The control rod drive device inserts the control rods into the reactor core from above as a cluster. When such a control rod is inserted into the core, the axial power distribution of the core changes and deviates from within a predetermined limit range. For this reason, conventionally, the distortion in the power distribution has been corrected by adjusting the boric acid concentration in the primary coolant and the insertion position of the control rod cluster, but since adjusting the boric acid concentration takes time, it is not possible to There was a problem that it could not respond to changes in output.
そこで、この問題を解決する手段として、中性子吸収能
力を軸方向均等に設定した制御棒集合体群と、中性子吸
収能力を下方が小さく上方が太きく設定した出力制御用
制御棒集合体群とを用いて出力制御及び出力分布制御を
行う方法が提案されている（特開昭５９−１９６４９７
号）。この方法によれば、たとえば第７図に示す如く中
性子吸収能力を下方が小さく上方が大きく設定した出力
制御用制御棒集合体群Ｇｌ、Ｇ２を炉心内に全挿入して
出力つまり炉心の反応度を制御するため、速い出力変化
に対応できるが、出力制御用制御棒集合体群Ｇｌ、Ｇ２
の挿入に伴い下式で表されるアキシャルφオフセット（
Ａ、０．）が第８図の曲線ａで示すように変化し、マイ
ナス側に２つの極大値を持つことになる。Therefore, as a means to solve this problem, we have created a group of control rod assemblies whose neutron absorption capacity is set evenly in the axial direction, and a group of control rod assemblies for output control whose neutron absorption capacity is set to be small at the bottom and thick at the top. A method has been proposed to perform output control and output distribution control using
issue). According to this method, for example, as shown in FIG. 7, power control control rod assemblies Gl and G2, whose neutron absorption capacities are set to be small at the bottom and large at the top, are fully inserted into the reactor core to increase the output power, that is, the reactivity of the reactor core. control rod assembly groups Gl and G2 for output control.
With the insertion of , the axial φ offset (
A, 0. ) changes as shown by curve a in FIG. 8, and has two maximum values on the negative side.
ＰＴ：炉心上半分の出力、ＰＢ：炉心下半分の出力。PT: power of the upper half of the core, PB: power of the lower half of the core.
ところで、原子炉出力が定格出力以下になると、曲線す
で示すようにＡ、０．が出力低下に伴ってプラス側に増
大する。これは原子炉の減速材温度係数が負であるため
、出力低下に伴い炉心上部に正の反応度が添加されるた
めである。従って、出力制御用制御棒集合体群Ｇｌ、Ｇ
２を炉心内へ挿入すると、Ａ、Ｏ，は実際には曲線Ｃで
示すように変化し、直線ｄで示すＡ、０．の制御目標値
より一時的に負側となる。このため、この部分ではホウ
酸の希釈でなく濃縮の信号が発信され、次にホウ酸の濃
縮によって与えられた反応度を補償するために、制御棒
の中性子吸収能力を上下軸方向均等に設定した制御棒集
合体群が炉心内から引抜かれることになる。このように
制御棒の中性子吸収能力を上下軸方向均等に設定した制
御棒集合体群が炉心内から引抜かれると、それ以降の軸
方向出力分布の制御および反応度の微調整が困難となる
可能性があった。By the way, when the reactor output falls below the rated output, the curve A, 0. increases to the positive side as the output decreases. This is because the moderator temperature coefficient of the nuclear reactor is negative, so positive reactivity is added to the upper part of the reactor core as the power decreases. Therefore, the control rod assembly groups Gl, G for output control
2 into the core, A, O, actually change as shown by curve C, and A, 0.2 shown by straight line d. temporarily becomes negative than the control target value. Therefore, a signal for concentrating boric acid instead of diluting it is transmitted in this part, and then, to compensate for the reactivity given by concentrating boric acid, the neutron absorption capacity of the control rod is set equally in the upper and lower directions. The control rod assemblies that have been removed will be pulled out from within the reactor core. If a group of control rods in which the neutron absorption capacity of the control rods is set equally in the upper and lower axial directions is pulled out of the reactor core, it may become difficult to control the axial power distribution and fine-tune the reactivity after that. There was sex.
本発明の目的はこのような問題点を解決し、出力分布の
歪を誘発することなく出力制御を行うことができるＰＷ
Ｒを提供しようとするものである。The purpose of the present invention is to solve such problems and to provide a PW that can perform output control without inducing distortion of output distribution.
It is intended to provide R.
上記課題を解決するために本発明は、中性子吸収能力を
軸方向均等に設定した複数の制御棒集合体と、前記中性
子吸収能力を下方が小さく上方が大きく設定した複数の
出力制御用制御棒集合体とを備えた加圧水型原子炉にお
いて、前記出力制御用１ｉ！ｒ御棒集合体を複数群に分
割し、各出力制御用制御棒集合体群をその一部をオーバ
ーラツプさせて炉心内へ挿入引抜するようにし、かつオ
ーバーラツプ部分の中性子吸収能力がオーバーラツプし
ない下方部分の中性子吸収能力より大きくオーバーラツ
プしない上方部分の中性子吸収能力より小さくなるよう
に各出力制御用制御棒集合体群の中性子吸収能力を設定
したことを特徴とするものである。In order to solve the above problems, the present invention provides a plurality of control rod assemblies in which the neutron absorption capacity is set equally in the axial direction, and a plurality of control rod assemblies for output control in which the neutron absorption capacity is set to be small in the lower part and large in the upper part. In the pressurized water reactor equipped with the power control 1i! r The control rod assembly is divided into a plurality of groups, and each output control control rod assembly group is inserted into and withdrawn from the reactor core with a portion of the control rod assembly group overlapping, and the neutron absorption capacity of the overlapped portions is a lower portion that does not overlap. The neutron absorption capacity of each output control control rod assembly group is set so as to be larger than the neutron absorption capacity and smaller than the neutron absorption capacity of the upper portion that does not overlap.
本発明においては、中性子吸収能力を下方が小さく上方
が大きく設定した複数の出力制御用制御棒集合体を複数
群に分割し、各出力制御用制御棒集合体群をその一部を
オーバーラツプさせて炉心内へ挿入引抜するようにし、
かつオーバーラツプ部分の中性子吸収能力がオーバーラ
ツプしない下方部分の中性子吸収能力より大きくオーバ
ーラツプしない上方部分の中性子吸収能力より小さくな
るように各出力制御用制御棒集合体群の中性子吸収能力
を設定することにより、出力分布の歪を誘発することな
く出力制御を行うことができる。In the present invention, a plurality of output control control rod assemblies whose neutron absorption capacity is set to be small in the lower part and large in the upper part are divided into a plurality of groups, and each output control control rod assembly group is made to partially overlap. Insert it into the reactor core and pull it out.
And by setting the neutron absorption capacity of each power control control rod assembly group so that the neutron absorption capacity of the overlapping part is greater than the neutron absorption capacity of the lower part that does not overlap and is smaller than the neutron absorption capacity of the upper part that does not overlap, Output control can be performed without inducing distortion of output distribution.
第１図は本発明の一実施例を示し、この実施例では１９
３体の燃料集合体によって炉心１が構成されている。上
記炉心１には中性子吸収能力を軸方向均等に設定した４
５体の制御棒集合体２・・・と、中性子吸収能力を下方
が小さく上方が大きく設定した８体の出力制御用制御棒
集合体３・・・がそれぞれ所定位置に配置され、４５体
の制御棒集合体２・・・は使用目的に応じて制御グルー
プバンクＡ、Ｂ。FIG. 1 shows an embodiment of the present invention, in which 19
A reactor core 1 is composed of three fuel assemblies. The above core 1 has neutron absorption capacity set equally in the axial direction.
Five control rod assemblies 2... and eight output control control rod assemblies 3... whose neutron absorption capacity is set to be small at the bottom and large at the top are placed at predetermined positions, and the 45 control rod assemblies 3... Control rod assembly 2... is divided into control group banks A and B depending on the purpose of use.
Ｃ，Ｄおよび停止グループバンクＳＡ、ＳＢ。C, D and stop group banks SA, SB.
ＳＣに分割されている。また、前記８体の出力制御用制
御棒集合体３・・・は第１の出力制御用制御棒集合体群
Ｇ１と第２の出力制御用制御棒集合体群Ｇ２とに分割さ
れている。これらの第１及び第２の出力制御用制御棒集
合体群Ｇｌ、Ｇ２は第２図に示すように互い５０％オー
バーラツプして炉心１内へ挿入・引抜されるようになっ
ており、ジかもオーバーラツプ部分Ａの中性子吸収能力
がオーバーラツプしない下方部分Ｂの中性子吸収能力よ
り大きくかつオーバーラツプしない上方部分Ｃの中性子
吸収能力より小さくなるようになっている。It is divided into SC. Further, the eight control rod assemblies 3 for output control are divided into a first control rod assembly group for output control G1 and a second control rod assembly group for output control G2. As shown in Fig. 2, these first and second power control control rod assembly groups Gl and G2 are inserted into and withdrawn from the core 1 with 50% overlap. The neutron absorption capacity of the overlapping part A is greater than the neutron absorption capacity of the non-overlapping lower part B and smaller than the neutron absorption capacity of the non-overlapping upper part C.
すなわち、第１の出力制御用制御棒集合体群Ｇ１に属す
る４体の出力制御用制御棒集合体３・・・は、第２図に
示す如くたとえば上半分が中性子吸収棒４本、ステンレ
ス棒２０本で構成され、下半分が中性子吸収棒０本、ス
テンレス棒２４本で構成されている。また、第２の出力
制御用制御棒集合体群Ｇ２に属する４体の出力制御用制
御棒集合体３・・・は、上半分が中性子吸収棒２４本、
ステンレス棒０本で構成され、下半分が中性子吸収棒４
本、ステンレス棒２０本で構成されている。That is, the four output control control rod assemblies 3 belonging to the first output control control rod assembly group G1 have, for example, four neutron absorption rods and a stainless steel rod in the upper half, as shown in FIG. The lower half consists of 0 neutron absorption rods and 24 stainless steel rods. In addition, the four output control rod assemblies 3 belonging to the second output control control rod assembly group G2 have 24 neutron absorption rods in the upper half,
Consists of 0 stainless steel rods, and the lower half has 4 neutron absorption rods.
It consists of a book and 20 stainless steel rods.
このようにオーバーラツプ部分Ａの中性子吸収能力がオ
ーバーラツプしない下方部分Ｂの中性子吸収能力より大
きくかつオーバーラツプしない上方部分Ｃの中性子吸収
能力より小さくなるように制御棒の中性子吸収能力を設
定した第１の出力制御用制御棒集合体群Ｇ１及び第２の
出力制御用制御棒集合体群Ｇ２を炉心１内へ互いに５０
％オーバーラツプさせて挿入すると、第３図に示す曲線
ａのようにＡ、Ｏ，が前記第１及び第２の出力制御用制
御棒集合体群Ｇｌ、Ｇ２の挿入に伴い負の方向へ単調に
増加するので、制御棒の中性子吸収能力を軸方向均等に
設定した出力分布制御用の制御棒集合体群（制御グルー
プＤ）が炉心内から全引抜きされることがな（、出力制
御と出力分布制御を良好に行うことができる。なお、前
記第１及び第２の出力制御用制御棒集合体群Ｇｌ、Ｇ２
を炉心１内へ５０％オーバーラツプさせて挿入したとき
の各種パラメータの変化を第４図に示す。In this way, the neutron absorption capacity of the control rod is set so that the neutron absorption capacity of the overlapping part A is greater than the neutron absorption capacity of the non-overlapping lower part B and smaller than the neutron absorption capacity of the non-overlapping upper part C. The control rod assembly group G1 for control and the second control rod assembly group G2 for power control are inserted into the reactor core 1 by 50° to each other.
When inserted with % overlap, A and O become monotonous in the negative direction as the first and second output control control rod assemblies Gl and G2 are inserted, as shown in curve a shown in Fig. 3. As a result, the control rod assembly group (control group D) for power distribution control, in which the neutron absorption capacity of the control rods is set equally in the axial direction, is not completely withdrawn from the reactor core (power control and power distribution Control can be performed satisfactorily.It should be noted that the first and second output control control rod assembly groups Gl, G2
FIG. 4 shows changes in various parameters when the two were inserted into the reactor core 1 with 50% overlap.
また、本発明は上記実施例に限定されるものでは゛ない
。たとえば、第５図に示すように第１の出力制御用制御
棒集合体？ｆｆＧ１に属する制御棒集合体を、下方部分
をステンレス棒２４本、中間部分をステンレス棒２０本
、中性子吸収棒４本、上方部分をステンレス棒１６本、
中性子吸収棒８本て構成し、第２の出力制御用制御棒集
合体群Ｇ２に属する制御棒集合体を、下方部分をステン
レス棒２４本、中性子吸収棒４本、中間部分をステンレ
ス棒１６本、中性子吸収棒８本、上方部分をステンレス
棒０本、中性子吸収棒２４本で構成してもよい。さらに
、第６図に示すように複数の出力制御用制御棒集合体を
３つの出力制御用制御棒集合体群Ｇｌ、Ｇ２．Ｇ３に分
割し、オーバーラツプ部分の中性子吸収能力がオーバー
ラツプしない下方部分の中性子吸収能力より大きくかつ
オーバーラツプしない上方部分の中性子吸収能力より小
さくなるように構成してもよい。Further, the present invention is not limited to the above embodiments. For example, the first output control control rod assembly as shown in FIG. The control rod assembly belonging to ffG1 has 24 stainless steel rods in the lower part, 20 stainless steel rods in the middle part, 4 neutron absorption rods in the upper part, and 16 stainless steel rods in the upper part.
The control rod assembly, which is composed of 8 neutron absorption rods and belongs to the second control rod assembly group G2 for output control, has 24 stainless steel rods and 4 neutron absorption rods in the lower part, and 16 stainless steel rods in the middle part. , the upper part may be composed of 8 neutron absorption rods, 0 stainless steel rods, and 24 neutron absorption rods. Furthermore, as shown in FIG. 6, a plurality of control rod assemblies for output control are arranged into three control rod assemblies for output control Gl, G2. The neutron absorbing capacity of the overlapping part may be larger than the neutron absorbing capacity of the lower part that does not overlap and smaller than the neutron absorbing capacity of the upper part that does not overlap.
以上説明したように本発明は、中性子吸収能力を軸方向
均等に設定した複数の制御棒集合体と、前記中性子吸収
能力を下方が小さく上方が大きく設定した複数の出力制
御用制御棒集合体とを備えた加圧水型原子炉において、
前記出力制御用制御棒集合体を複数群に分割し、各出力
制御用制御棒集合体群をその一部をオーバーラツプさせ
て炉心内へ挿入引抜するようにし、かつオーバーラツプ
部分の中性子吸収能力がオーバーラツプしない下方部分
の中性子吸収能力より大きくオーバーラツプしない上方
部分の中性子吸収能力より小さくなるように各出力制御
用制御棒集合体群の中性子吸収能力を設定したので、出
力分布の歪を誘発することなく出力制御を行うことがで
きる。As explained above, the present invention includes a plurality of control rod assemblies in which the neutron absorption capacity is set equally in the axial direction, and a plurality of control rod assemblies for output control in which the neutron absorption capacity is set to be small in the lower part and large in the upper part. In a pressurized water reactor equipped with
The power control control rod assembly is divided into a plurality of groups, and each power control control rod assembly group is inserted into and withdrawn from the reactor core with a portion of the group overlapping, and the neutron absorption capacities of the overlapping portions are overlapped. The neutron absorption capacity of each power control control rod assembly group was set so that it was larger than the neutron absorption capacity of the lower part that did not overlap and was smaller than the neutron absorption capacity of the upper part that did not overlap. can be controlled.
第１図ないし第４図は本発明の一実施例を示し、第１図
は制御棒集合体群および出力制御用制御棒集合体群の配
置図、第２図は出力制御用制御棒集合体群の構成を示す
図、第３図は出力制御用制御棒集合体群を炉心内に挿入
したときの出力分布変化を示す線図、第４図は出力制御
用制御棒集合体群を炉心内に挿入したときの各種パラメ
ータの変化を示す線図、第５図及び第６図は出力制御用
制御棒集合体群の他の実施例を示す図、第７図は従来の
出力制御用制御棒集合体群を示す図、第８図は従来の出
力制御用制御棒集合体群を炉心内に挿入したときの出力
分布変化を示す線図である。
・・・炉心、
２・・・制御棒集合体、
３・・・出力制御用
制御棒集合体、
Ｇ２゜
・・・出力制御用
制御棒集合体群。1 to 4 show an embodiment of the present invention, FIG. 1 is a layout diagram of a control rod assembly group and a control rod assembly group for output control, and FIG. 2 is a layout diagram of a control rod assembly group for output control. Figure 3 is a diagram showing the power distribution change when the control rod assembly group for power control is inserted into the reactor core, and Figure 4 is a diagram showing the configuration of the control rod assembly group for power control in the reactor core. Figures 5 and 6 are diagrams showing other embodiments of the control rod assembly group for output control, and Figure 7 is a diagram showing the changes in various parameters when inserted into the control rod. FIG. 8 is a diagram showing a change in power distribution when a conventional power control control rod assembly group is inserted into a reactor core. ...Reactor core, 2...Control rod assembly, 3...Control rod assembly for output control, G2゜...Control rod assembly group for output control.
Claims (1)
合体と、前記中性子吸収能力を下方が小さく上方が大き
く設定した複数の出力制御用制御棒集合体とを備えた加
圧水型原子炉において、前記出力制御用制御棒集合体を
複数群に分割し、各出力制御用制御棒集合体群をその一
部をオーバーラップさせて炉心内へ挿入引抜するように
し、かつオーバーラップ部分の中性子吸収能力がオーバ
ーラップしない下方部分の中性子吸収能力より大きくオ
ーバーラップしない上方部分の中性子吸収能力より小さ
くなるように各出力制御用制御棒集合体群の中性子吸収
能力を設定したことを特徴とする加圧水型原子炉。In a pressurized water reactor equipped with a plurality of control rod assemblies whose neutron absorption capacities are set equally in the axial direction, and a plurality of power control control rod assemblies whose neutron absorption capacities are set to be small at the bottom and large at the top, The control rod assembly for power control is divided into a plurality of groups, each group of control rods for power control is inserted into and withdrawn from the reactor core with a portion of the group overlapping, and the neutron absorption capacity of the overlapped portion is A pressurized water type atom characterized in that the neutron absorption capacity of each power control control rod assembly group is set so that the neutron absorption capacity of the lower part that does not overlap is greater than the neutron absorption capacity of the upper part that does not overlap. Furnace.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63193271A JPH0242389A (en) | 1988-08-02 | 1988-08-02 | Pressurized water reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP63193271A JPH0242389A (en) | 1988-08-02 | 1988-08-02 | Pressurized water reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0242389A true JPH0242389A (en) | 1990-02-13 |
Family
ID=16305162
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP63193271A Pending JPH0242389A (en) | 1988-08-02 | 1988-08-02 | Pressurized water reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0242389A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2710778A1 (en) * | 1993-09-29 | 1995-04-07 | Framatome Sa | Control rod cluster for nuclear reactor and reactor making application thereof |
-
1988
- 1988-08-02 JP JP63193271A patent/JPH0242389A/en active Pending
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2710778A1 (en) * | 1993-09-29 | 1995-04-07 | Framatome Sa | Control rod cluster for nuclear reactor and reactor making application thereof |
| US5754608A (en) * | 1993-09-29 | 1998-05-19 | Compagnie Generale Des Matieres Nucleaires | Control cluster for a nuclear reactor |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JP2915200B2 (en) | Fuel loading method and reactor core | |
| SE8004485L (en) | KERNREAKTOR | |
| US4326919A (en) | Nuclear core arrangement | |
| GB915190A (en) | Improvements in nuclear reactors | |
| US3640844A (en) | Power-flattened seed-blanket reactor core | |
| US4894200A (en) | Method of operating a nuclear reactor | |
| JPH0242389A (en) | Pressurized water reactor | |
| JPS61102586A (en) | Blanket fuel aggregate | |
| JPS5858036B2 (en) | Light water reactor and its operation method | |
| JPS6228437B2 (en) | ||
| JPS61128185A (en) | Core for nuclear reactor | |
| JPS5928691A (en) | Fuel assembly | |
| JPS6013283A (en) | Boiling water reactor | |
| JPS60171494A (en) | Method of charging fuel | |
| JPH11109073A (en) | Fuel assembly for boiling water reactor | |
| JPS6166988A (en) | Method of charging fuel | |
| JPS5915888A (en) | Bwr type reactor core | |
| JPH04249794A (en) | Operation method of reactor initial charge core | |
| Paustian et al. | An in-core large scale demonstration of barrier fuel at Quad Cities 2 | |
| JPH01193693A (en) | Controlling of nuclear reactor | |
| JPS6263887A (en) | Fast breeder reactor | |
| JPS6158789B2 (en) | ||
| JPS6280585A (en) | Initial loading core for nuclear reactor | |
| JPS6153590A (en) | Fast brreder reactor | |
| JPH0650351B2 (en) | Reactor core |