JPH06123789A - Fast breeder reactor core - Google Patents
Fast breeder reactor coreInfo
- Publication number
- JPH06123789A JPH06123789A JP4271301A JP27130192A JPH06123789A JP H06123789 A JPH06123789 A JP H06123789A JP 4271301 A JP4271301 A JP 4271301A JP 27130192 A JP27130192 A JP 27130192A JP H06123789 A JPH06123789 A JP H06123789A
- Authority
- JP
- Japan
- Prior art keywords
- core
- breeder reactor
- fuel
- fast breeder
- trumpet tube
- 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
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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
(57)【要約】
【目的】 本発明の目的は、高燃焼度を達成し、かつス
クラム失敗時の予知過渡事象時の炉心燃料部の膨脹量を
増大させることができ、高速増殖炉の固有の安全性の向
上を図ることのできる高速増殖炉の炉心を提供しようと
するものである。
【構成】 本発明は、断面六角形状の筒状に形成され、
少なくとも炉心燃料部上端近傍に位置する部位の外側に
荷重パッド8が設けられたラッパ管7を有し、このラッ
パ管7をフェライト鋼にて形成して成る燃料集合体6が
配設された高速増殖炉の炉心1において、炉心1の最外
周に位置する燃料集合体5のラッパ管をオーステナイト
鋼にて形成して成ることを特徴とする。
(57) [Summary] [Objective] The object of the present invention is to achieve a high burnup and to increase the expansion amount of the core fuel portion at the time of a predictive transient event at the time of scrum failure, which is an inherent feature of a fast breeder reactor. It is intended to provide a core of a fast breeder reactor capable of improving the safety of the. [Configuration] The present invention is formed in a tubular shape having a hexagonal cross section,
A high-speed fuel cell having a trumpet tube 7 provided with a load pad 8 at least outside a portion located near the upper end of the core fuel part, and having a fuel assembly 6 made of ferritic steel. In the core 1 of the breeder reactor, the trumpet tube of the fuel assembly 5 located at the outermost periphery of the core 1 is formed of austenitic steel.
Description
【0001】[0001]
【産業上の利用分野】本発明は、高速増殖炉の炉心に関
する。TECHNICAL FIELD The present invention relates to a core of a fast breeder reactor.
【0002】[0002]
【従来の技術】一般に、高速増殖炉の炉心は、ほぼ円柱
状に構成されており、その中心部には炉心燃料部、炉心
燃料部の上下部には上部ブランケット部および下部ブラ
ンケット部、炉心燃料部の周囲には径方向ブランケット
部が形成されている。なお、炉心燃料部にもいくつかの
層状のブランケット部を設けたものもある。また、この
ような高速増殖炉の炉心は、次のように構成された多数
の高速増殖炉用燃料集合体によって構成されている。2. Description of the Related Art Generally, the core of a fast breeder reactor is formed into a substantially cylindrical shape, with a core fuel part in the center thereof, an upper blanket part and a lower blanket part in the upper and lower parts of the core fuel part, and a core fuel part. A radial blanket portion is formed around the portion. Some core fuel parts are also provided with several layered blanket parts. Further, the core of such a fast breeder reactor is composed of a large number of fuel assemblies for the fast breeder reactor configured as follows.
【0003】すなわち、炉心燃料要素およびブランケッ
ト燃料要素を燃料被覆管内に封入してなる燃料棒は、六
方格子状に規則正しく配列されて束ねられ、断面六角形
の筒状に形成されたラッパ管内に収容されている。ま
た、このラッパ管の外側には、上端部近傍に上部荷重パ
ッド(URP)が設けられており、上部荷重パッドの下
方であって炉心燃料部の上端部近傍(上部ブランケット
部下端近傍)に位置する部位には下部荷重パッド(LR
P)が設けられている。That is, fuel rods in which a core fuel element and a blanket fuel element are enclosed in a fuel cladding tube are regularly arranged in a hexagonal lattice and bundled, and housed in a trumpet tube formed in a tubular shape having a hexagonal cross section. Has been done. An upper load pad (URP) is provided near the upper end on the outside of the trumpet pipe, and is located below the upper load pad and near the upper end of the core fuel part (near the lower end of the upper blanket part). Lower load pad (LR
P) is provided.
【0004】ところで、上記構成の高速増殖炉用燃料集
合体によって構成された高速増殖炉の炉心においては、
縦軸を温度、横軸を炉心中心からの径方向距離とした図
4の特性図に示すように、炉心燃料部中心で温度が高
く、炉心燃料部の外周付近から温度が下降を開始するよ
うな炉内径方向温度分布を示す。このような径方向温度
分布により、特に温度変化の大きい炉心燃料部の外周付
近の高速増殖炉用燃料集合体は、図5に示すような彎曲
を起こすことになる。By the way, in the core of the fast breeder reactor constituted by the fuel assembly for the fast breeder reactor having the above-mentioned structure,
As shown in the characteristic diagram of FIG. 4 in which the vertical axis is temperature and the horizontal axis is radial distance from the core center, the temperature is high at the center of the core fuel part and the temperature starts to drop near the outer periphery of the core fuel part. 3 shows a temperature distribution in the furnace inner diameter direction. Due to such radial temperature distribution, the fuel assembly for a fast breeder reactor near the outer periphery of the core fuel portion, which has a large temperature change, causes a curve as shown in FIG.
【0005】すなわち、定格運転時には、図5(A)に
示すように、炉心燃料部で内側へ向かうような彎曲を起
こす。ここで、出力上昇事故(TOP)あるいは冷却材
流量減少事故(LOF)が起こった場合(ATWS時:
スクラム失敗時の予知過渡事象)は、集合体出力と流量
の比(P/F)が増大して炉内温度径方向分布がさらに
大きくなり、図5(B)に示すように、炉心燃料部で外
側へ向かうような彎曲を起こす。図5(C)は、図5
(A)の場合と図5(B)の場合との差を示すもので、
このように、ATWS時には、定格運転時に較べて炉心
燃料部が実質的に膨脹したことになり、負の反応度が挿
入される。このような効果は、炉の固有の安全性を高め
る上で重要な因子となっている。That is, during the rated operation, as shown in FIG. 5 (A), the core fuel portion is bent toward the inside. Here, when an output increase accident (TOP) or a coolant flow rate decrease accident (LOF) occurs (at ATWS:
In the predictive transient event at the time of scrum failure), the ratio of the assembly output to the flow rate (P / F) increases and the temperature distribution in the in-core temperature direction further increases, and as shown in FIG. 5 (B), the core fuel part Causes a curve that goes to the outside. FIG. 5C is the same as FIG.
The difference between the case of (A) and the case of FIG. 5 (B) is shown.
As described above, during ATWS, the core fuel portion is substantially expanded as compared with during rated operation, and a negative reactivity is inserted. Such effects are important factors in enhancing the intrinsic safety of the furnace.
【0006】一般に、ラッパ管材料の熱膨脹率が大きい
程炉心彎曲は大きくなるので、このATWS時の負の反
応度挿入量も、熱膨脹率の大きな材料からなるラッパ管
で構成された炉心の方が有利である。Generally, the greater the coefficient of thermal expansion of the trumpet tube material, the greater the core curvature. Therefore, the negative reactivity insertion amount at the ATWS is also the core composed of the trumpet tube made of the material having a large coefficient of thermal expansion. It is advantageous.
【0007】一方、高燃焼度を目指した高速増殖炉炉心
においては、ラッパ管は低スウェリング材料で作る必要
がある。このことから一般に従来の高速増殖炉炉心のラ
ッパ管で使用されていたオーステナイト鋼に変わって耐
スウェリング性能にすぐれたフェライト鋼が使用される
方向にある。On the other hand, in a fast breeder reactor core aiming at high burnup, the trumpet tube must be made of a low swelling material. For this reason, ferritic steels having excellent swelling resistance are generally used in place of the austenitic steels used in the conventional trumpet tubes of fast breeder reactor cores.
【0008】但し、フェライト鋼の熱膨脹率はオーステ
ナイト鋼のそれよりも4割程小さく、前記のATWS時
の炉心彎曲による負の反応度挿入量の大きさについて
は、オーステナイト鋼ラッパ管からなる炉心よりも小さ
くなってしまい、炉の固有安全性を高める観点からは望
ましくない。However, the coefficient of thermal expansion of ferritic steel is about 40% smaller than that of austenitic steel, and regarding the magnitude of the negative reactivity insertion amount due to the bending of the core during ATWS, the core of an austenitic steel wrapper tube is used. Becomes smaller, which is not desirable from the viewpoint of increasing the intrinsic safety of the furnace.
【0009】[0009]
【発明が解決しようとする課題】上述のように、高燃焼
度を目指して、ラッパ管材料として耐スウェリング性能
にすぐれたフェライト鋼を採用した高速増殖炉炉心に於
いては、ATWS時の炉心彎曲による負の反応度挿入量
の大きさが、オーステナイト鋼ラッパ管からなる炉心よ
りも小さくなってしまい、炉の固有安全性を高める観点
からは望ましくない。As described above, in the fast breeder reactor core which uses ferritic steel excellent in swelling resistance as the material of the trumpet tube in order to achieve high burnup, the core of the ATWS is used. The amount of insertion of the negative reactivity due to bending becomes smaller than that of the core made of austenitic steel trumpet tube, which is not desirable from the viewpoint of increasing the intrinsic safety of the furnace.
【0010】本発明は、かかる従来の事情に対処してな
されたもので、高燃焼度を達成し、かつ、ATWS時の
炉心燃料部の膨脹量を増大させることができ、高速増殖
炉の固有の安全性の向上を図ることのできる高速増殖炉
炉心を提供しようとするものである。The present invention has been made in consideration of the above-mentioned conventional circumstances, and it is possible to achieve a high burnup and increase the expansion amount of the core fuel portion during ATWS. It aims to provide a fast breeder reactor core capable of improving the safety of
【0011】[0011]
【課題を解決するための手段】すなわち本発明は、断面
六角形状の筒状に形成され、少なくとも炉心燃料部上端
近傍に位置する部位の外側に荷重パッドが設けられたラ
ッパ管を有し、このラッパ管をフェライト鋼にて形成し
て成る燃料集合体が配設された高速増殖炉の炉心におい
て、炉心最外周に位置する燃料集合体のラッパ管をオー
ステナイト鋼にて形成して成ることを特徴とする。That is, the present invention has a trumpet tube which is formed in a tubular shape having a hexagonal cross section and which is provided with a load pad at least outside a portion located near the upper end of the core fuel section. In the core of a fast breeder reactor in which a fuel assembly made of a ferritic steel is provided, the fuel assembly wrapping pipe located at the outermost periphery of the core is made of austenitic steel. And
【0012】[0012]
【作用】上記構成の本発明の高速増殖炉の炉心では、ラ
ッパ管のスウェリング膨脹を促進する原因となる中性子
束の大きな炉心中央部には、耐スウェリング性能に優れ
たフェライト鋼ラッパ管からなる炉心燃料集合体が装荷
されることにより高燃焼度が達成される。一方、ATW
S時の炉心彎曲による炉心燃料部の実質的膨脹を促進す
る原因となるラッパ管の径方向の温度勾配が大きな炉心
最外周部には、熱膨脹率の大きなオーステナイト鋼から
成るラッパ管が配設された炉心燃料集合体が装荷される
ことにより、固有の安全性の向上を図ることができる。
尚、この炉心最外周部では、中性子束は炉心中央部に比
較して小さいので、耐スウェリング性能に劣るオーステ
ナイト鋼ラッパ管からなる炉心燃料集合体でも、炉の高
燃焼度達成を阻害することはない。したがって、本発明
の高速増殖炉炉心では、高燃焼度達成と固有の安全性の
向上を共に満足できる。In the core of the fast breeder reactor of the present invention having the above-mentioned structure, the core of the core having a large neutron flux that promotes the swelling expansion of the trumpet tube is provided with a ferrite steel trumpet tube excellent in swelling resistance. A high burnup is achieved by loading the core fuel assembly. On the other hand, ATW
A wrapper pipe made of austenitic steel having a large coefficient of thermal expansion is provided at the outermost periphery of the core where the temperature gradient in the radial direction of the wrapper pipe, which causes the substantial expansion of the core fuel portion due to the bending of the core during S, is large. The inherent safety can be improved by loading the core fuel assembly.
Since the neutron flux at the outermost periphery of the core is smaller than that at the center of the core, even in a core fuel assembly consisting of an austenitic steel trumpet tube with poor swelling resistance, it is difficult to achieve high burnup of the reactor. There is no. Therefore, in the fast breeder reactor core of the present invention, both achievement of high burnup and improvement of inherent safety can be satisfied.
【0013】[0013]
【実施例】以下、本発明の高速増殖炉炉心を図面を参照
して実施例について説明する。EXAMPLES Examples of the fast breeder reactor core of the present invention will be described below with reference to the drawings.
【0014】図1は、本発明の一実施例の高速増殖炉の
炉心の構成を示すもので、その中心部には炉心燃料領域
1が、その周囲には径方向ブランケット領域2、中性子
遮蔽体領域3が配置され、前記炉心燃料領域1内には制
御棒集合体4が装荷されている。炉心燃料領域1の中の
最外周部に配置された最外周炉心燃料集合体5のラッパ
管はオーステナイト鋼で、それ以外の炉心燃料領域1の
燃料集合体6のラッパ管はフェライト鋼で構成されてい
る。FIG. 1 shows the structure of a core of a fast breeder reactor according to an embodiment of the present invention. A core fuel region 1 is provided at the center of the core, and a radial blanket region 2 and a neutron shield are provided around the core fuel region 1. A region 3 is arranged, and a control rod assembly 4 is loaded in the core fuel region 1. The trumpet tubes of the outermost peripheral core fuel assemblies 5 arranged in the outermost peripheral portion of the core fuel region 1 are made of austenitic steel, and the other wrapper pipes of the fuel assemblies 6 of the core fuel region 1 are made of ferritic steel. ing.
【0015】図2のグラフは高速増殖炉用燃料集合体に
彎曲を起こさせる原因である炉中心側と外側のラッパ管
7の温度差の軸方向変化を示したものである。なお、こ
のグラフにおいて、縦軸は軸方向位置、横軸は温度差で
あり、実線はP/F=1.0 (定格運転時)、点線はP/
F>1.0 (ATWS時)をしめしている。このグラフに
示されるように、温度差は、発熱部分である炉心燃料部
下端部から次第に増加し、炉心燃料部上端部付近(下部
荷重パッド9付近)で最大となり、ラッパ管の上端部の
上部荷重パッド8部までほぼこの温度差が続く。The graph of FIG. 2 shows the axial change in the temperature difference between the trumpet tube 7 on the furnace center side and the outer trumpet tube 7, which causes the bending of the fuel assembly for a fast breeder reactor. In this graph, the vertical axis is the axial position, the horizontal axis is the temperature difference, the solid line is P / F = 1.0 (during rated operation), and the dotted line is P / F.
It shows F> 1.0 (at ATWS). As shown in this graph, the temperature difference gradually increases from the lower end of the core fuel part, which is the heat generating part, reaches its maximum near the upper end of the core fuel part (near lower load pad 9), and reaches the upper part of the upper part of the trumpet tube. This temperature difference continues up to the load pad 8.
【0016】上記構成のこの実施例の高速増殖炉炉心で
は、上述したように、炉中心側と外側のラッパ管7の温
度差が大きくなる最外周炉心燃料集合体5のラッパ管が
フェライト鋼よりも熱膨脹の大きな材料で構成されてい
る。したがって、上記温度差に基づく曲げモーメントを
増加させることができる。このため、図3(B)に実線
で示すように、ATWS時のラッパ管7のS字型の彎曲
量を点線で示す従来の場合(フェライト鋼)に較べて大
きくすることができ、炉心燃料部の膨脹量を増大させて
負の反応度挿入量を高めることができる。なお、前述の
図5と同様に、図3(A)は定格運転時、図3(C)は
定格運転時とATWS時の差を示している。In the fast breeder reactor core of this embodiment having the above-described structure, as described above, the trumpet tube of the outermost peripheral fuel assembly 5 in which the temperature difference between the trumpet tube 7 on the core side and the trumpet tube 7 on the outer side is large is made of ferritic steel. Is also made of a material having a large thermal expansion. Therefore, the bending moment based on the temperature difference can be increased. Therefore, as shown by the solid line in FIG. 3 (B), the amount of S-shaped curve of the trumpet pipe 7 during ATWS can be made larger than in the conventional case (ferrite steel) shown by the dotted line, and the core fuel The amount of expansion of the part can be increased to increase the amount of negative reactivity insertion. Like FIG. 5 described above, FIG. 3A shows the difference between the rated operation and FIG. 3C shows the difference between the rated operation and the ATWS.
【0017】すなわち、この実施例の高速増殖炉の炉心
では、ATWS時の最外周燃料集合体5のラッパ管7の
S字型の彎曲量を従来の場合に較べて大きくすることが
でき、炉心燃料部の膨脹量を増大させて負の反応度挿入
量を高めることができるので、従来に較べて高速増殖炉
の固有の安全性の向上を図ることができる。That is, in the core of the fast breeder reactor of this embodiment, the S-shaped curve amount of the trumpet tube 7 of the outermost peripheral fuel assembly 5 during ATWS can be made larger than that of the conventional case, and the core Since the expansion amount of the fuel portion can be increased to increase the negative reactivity insertion amount, it is possible to improve the inherent safety of the fast breeder reactor as compared with the conventional case.
【0018】[0018]
【発明の効果】以上述べたように、本発明の高速増殖炉
炉心によれば、高燃焼度を達成しながら、従来に較べて
さらにATWS時の炉心燃料部の膨脹量を増大させるこ
とができ、高速増殖炉の固有の安全性の向上を図ること
ができる。As described above, according to the fast breeder reactor core of the present invention, it is possible to further increase the expansion amount of the core fuel portion at the time of ATWS while achieving high burnup. Therefore, the inherent safety of the fast breeder reactor can be improved.
【図1】本発明の一実施例の高速増殖炉炉心の構成を示
す概略平面図。FIG. 1 is a schematic plan view showing the structure of a fast breeder reactor core according to an embodiment of the present invention.
【図2】炉中心側と外側のラッパ管の温度差の軸方向変
化を示す特性図。FIG. 2 is a characteristic diagram showing an axial change in temperature difference between a trumpet tube on the center side and an outer trumpet tube.
【図3】図1に示す高速増殖炉の炉心の燃料集合体の変
形の様子を(A)は定格運転時、(B)はATWS時、
(C)はその差として説明するための特性図。3A and 3B show a state of deformation of a fuel assembly of a core of the fast breeder reactor shown in FIG. 1, (A) during rated operation, (B) during ATWS,
(C) is a characteristic diagram for explaining the difference.
【図4】炉内径方向温度分布を示す特性図。FIG. 4 is a characteristic diagram showing a temperature distribution in a furnace inner diameter direction.
【図5】従来の高速増殖炉の炉心の燃料集合体の変形の
様子を(A)は定格運転時、(B)はATWS時、
(C)はその差として説明するための特性図。FIG. 5 shows the deformation of the fuel assembly of the core of the conventional fast breeder reactor (A) during rated operation, (B) during ATWS,
(C) is a characteristic diagram for explaining the difference.
1…炉心燃料領域 2…径方向ブランケット領域 3…中性子遮蔽体領域 4…制御棒集合体 5…炉心燃料集合体(オーステナイト鋼ラッパ管製) 6…炉心燃料集合体(フェライト鋼ラッパ管製) 7…ラッパ管 8…上部荷重パッド(URP) 9…下部荷重パッド(LRP) 1 ... Core fuel region 2 ... Radial blanket region 3 ... Neutron shield region 4 ... Control rod assembly 5 ... Core fuel assembly (made of austenitic steel wrapper pipe) 6 ... Core fuel assembly (made of ferrite steel wrapper pipe) 7 … Trumpet pipe 8… Upper load pad (URP) 9… Lower load pad (LRP)
Claims (1)
とも炉心燃料部上端近傍に位置する部位の外側に荷重パ
ッドが設けられたラッパ管を有し、このラッパ管をフェ
ライト鋼にて形成して成る燃料集合体が配設された高速
増殖炉の炉心において、炉心最外周に位置する燃料集合
体のラッパ管をオーステナイト鋼にて形成して成ること
を特徴とする高速増殖炉の炉心。1. A trumpet tube formed in a tubular shape having a hexagonal cross section and provided with a load pad outside at least a portion located near the upper end of the core fuel section, the trumpet tube being formed of ferritic steel. A core of a fast breeder reactor in which a fuel assembly located at the outermost periphery of the core is formed of austenitic steel in the core of the fast breeder reactor.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP04271301A JP3135705B2 (en) | 1992-10-09 | 1992-10-09 | Core of fast breeder reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP04271301A JP3135705B2 (en) | 1992-10-09 | 1992-10-09 | Core of fast breeder reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPH06123789A true JPH06123789A (en) | 1994-05-06 |
| JP3135705B2 JP3135705B2 (en) | 2001-02-19 |
Family
ID=17498138
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP04271301A Expired - Fee Related JP3135705B2 (en) | 1992-10-09 | 1992-10-09 | Core of fast breeder reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JP3135705B2 (en) |
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| CN109192331A (en) * | 2018-09-13 | 2019-01-11 | 中国核动力研究设计院 | Hexagon thimble tube fuel assembly nuclear design certificate authenticity reactor core and method of adjustment |
| CN109192333A (en) * | 2018-09-13 | 2019-01-11 | 中国核动力研究设计院 | Hexagon thimble tube fuel assembly nuclear design certificate authenticity reactor core and verification method |
| CN109273108A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | Hexagon thimble tube fuel assembly core bore road nuclear design examines reactor core and test method |
| CN114446496A (en) * | 2022-02-17 | 2022-05-06 | 中国核动力研究设计院 | Ultra-high flux reactor core based on annular fuel element |
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| US12606066B2 (en) * | 2023-03-13 | 2026-04-21 | Ford Global Technologies, Llc | Vehicle seating system having inductive powered cover |
-
1992
- 1992-10-09 JP JP04271301A patent/JP3135705B2/en not_active Expired - Fee Related
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109192331A (en) * | 2018-09-13 | 2019-01-11 | 中国核动力研究设计院 | Hexagon thimble tube fuel assembly nuclear design certificate authenticity reactor core and method of adjustment |
| CN109192333A (en) * | 2018-09-13 | 2019-01-11 | 中国核动力研究设计院 | Hexagon thimble tube fuel assembly nuclear design certificate authenticity reactor core and verification method |
| CN109273108A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | Hexagon thimble tube fuel assembly core bore road nuclear design examines reactor core and test method |
| CN109192333B (en) * | 2018-09-13 | 2020-06-23 | 中国核动力研究设计院 | Hexagonal casing type fuel assembly nuclear design reliability inspection reactor core and verification method |
| CN109192331B (en) * | 2018-09-13 | 2020-06-23 | 中国核动力研究设计院 | Hexagonal casing type fuel assembly nuclear design reliability inspection reactor core and adjusting method |
| CN109273108B (en) * | 2018-09-13 | 2020-06-23 | 中国核动力研究设计院 | Hexagonal casing type fuel reactor core pore channel nuclear design inspection reactor core and test method |
| CN114446496A (en) * | 2022-02-17 | 2022-05-06 | 中国核动力研究设计院 | Ultra-high flux reactor core based on annular fuel element |
| CN114446496B (en) * | 2022-02-17 | 2024-04-23 | 中国核动力研究设计院 | Ultra-high flux reactor core based on annular fuel elements |
Also Published As
| Publication number | Publication date |
|---|---|
| JP3135705B2 (en) | 2001-02-19 |
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| LAPS | Cancellation because of no payment of annual fees |