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JP5896711B2 - Fuel assembly structure for fast reactor and fuel assembly arrangement structure in fast reactor - Google Patents
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JP5896711B2 - Fuel assembly structure for fast reactor and fuel assembly arrangement structure in fast reactor - Google Patents

Fuel assembly structure for fast reactor and fuel assembly arrangement structure in fast reactor Download PDF

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JP5896711B2
JP5896711B2 JP2011268066A JP2011268066A JP5896711B2 JP 5896711 B2 JP5896711 B2 JP 5896711B2 JP 2011268066 A JP2011268066 A JP 2011268066A JP 2011268066 A JP2011268066 A JP 2011268066A JP 5896711 B2 JP5896711 B2 JP 5896711B2
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fuel
fuel assembly
fast reactor
outer tube
fast
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JP2013120119A (en
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茂 國嶋
茂 國嶋
清水 亮
亮 清水
行秀 森
行秀 森
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Mitsubishi Heavy Industries Ltd
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    • YGENERAL 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
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Description

本発明は、高速中性子を利用する高速増殖炉等の原子炉で使用される高速炉用燃料集合体構造及び高速炉内の燃料集合体配置構造に関する。   The present invention relates to a fuel assembly structure for a fast reactor used in a nuclear reactor such as a fast breeder reactor using fast neutrons and a fuel assembly arrangement structure in the fast reactor.

高速中性子を利用する原子炉には、例えば高速増殖炉や増殖を目的としない高速中性子炉等があり、以下ではこれらを総称して「高速炉」と呼ぶ。
図4〜図6は、高速炉において使用される一般的な高速炉用燃料集合体(以下、「燃料集合体」と呼ぶ)1の構造を示している。なお、高速炉で使用される燃料集合体1は、軽水炉で使用される正方形断面とは異なる正六角形断面を有している。
Examples of fast neutron reactors include fast breeder reactors and fast neutron reactors not intended for breeding. These are collectively referred to as “fast reactors”.
4 to 6 show the structure of a general fast reactor fuel assembly (hereinafter referred to as “fuel assembly”) 1 used in a fast reactor. The fuel assembly 1 used in the fast reactor has a regular hexagonal cross section different from the square cross section used in the light water reactor.

燃料棒10は、ペレットと呼ばれる燃料要素を縦に連ねた円形断面形状の棒状構造物である。この燃料棒10は、高速中性子の利用効率を高めるため、図5に示すように、緻密な正三角形格子配列にして正六角筒状の外套管11(「ラッパ管」とも呼ばれている)内に収容されている。すなわち、燃料集合体1は、隣接する燃料棒10の中心が正三角形12を形成する格子配列とした燃料棒10の集合体であり、燃料棒10の集合体は、その周囲を取り囲むように密着して配置された外套管11を備えている。この外套管11は、正六角形の断面を有する筒体である。   The fuel rod 10 is a rod-shaped structure having a circular cross-sectional shape in which fuel elements called pellets are vertically connected. In order to increase the utilization efficiency of fast neutrons, the fuel rod 10 is arranged in a regular hexagonal tubular outer tube 11 (also called a “trumpet tube”) in a dense equilateral triangular lattice arrangement as shown in FIG. Is housed in. In other words, the fuel assembly 1 is an assembly of fuel rods 10 having a lattice arrangement in which the centers of adjacent fuel rods 10 form an equilateral triangle 12, and the assembly of fuel rods 10 is closely attached so as to surround the periphery thereof. The outer tube 11 is provided. The outer tube 11 is a cylinder having a regular hexagonal cross section.

また、燃料要素から熱を取り出す冷却材には、高速中性子を減速させにくい液体金属として、液体ナトリウムが一般的に用いられている。この冷却材は、燃料集合体1を構成する外套管11の内部を下方から上方へと通過する過程で、燃料要素から発生する熱を取り出している。なお、図中の符号13は、冷却材が外套管11の内部に流入するエントランスノズルである。
このような高速炉では、万一の炉心損傷時において、溶融した燃料が一部に集中すると即発臨界を超過して核的暴走に至る「再臨界」と呼ばれる現象に至る可能性がある。そこで、この再臨界を回避するためには、炉心損傷時の溶融燃料を早期に炉外排出して分散させ、未臨界状態を恒久的に作り出す対策が必要となる。
Also, liquid sodium is generally used as a coolant that extracts heat from the fuel element as a liquid metal that is difficult to slow down fast neutrons. This coolant extracts heat generated from the fuel element in the process of passing from the lower part to the upper part of the outer tube 11 constituting the fuel assembly 1. In addition, the code | symbol 13 in a figure is an entrance nozzle into which a cooling material flows in into the outer tube 11 inside.
In such a fast reactor, in the unlikely event of core damage, if the molten fuel concentrates in part, it may lead to a phenomenon called “recriticality” that exceeds the immediate criticality and leads to nuclear runaway. Therefore, in order to avoid this re-criticality, it is necessary to take measures to permanently create a subcritical state by quickly discharging the molten fuel at the time of core damage to the outside and dispersing it.

万一の炉心損傷を想定した場合の再臨界を排除するため、下記の特許文献1には、燃料集合体内に上部開放型の制御棒案内管を設置し、溶融燃料排出ダクトとして機能させることが記載されている。
また、下記の特許文献2には、燃料棒から軸ブランケット燃料部の削除等を行い、溶融燃料排出ダクトとして機能させることが記載されている。
また、下記の特許文献3には、燃料集合体内に感熱式開放機構を設置し、溶融燃料排出ダクトとして機能させることが記載されている。
In order to eliminate recriticality in the event of core damage, the following patent document 1 discloses that a control rod guide tube with an open top is installed in the fuel assembly to function as a molten fuel discharge duct. Have been described.
Patent Document 2 below describes that the shaft blanket fuel part is deleted from the fuel rods to function as a molten fuel discharge duct.
Patent Document 3 below describes that a thermal opening mechanism is installed in the fuel assembly to function as a molten fuel discharge duct.

特開2009−85650号公報JP 2009-85650 A 特開2002−55187号公報JP 2002-55187 A 特許第2839222号公報Japanese Patent No. 2839222

上述したように、高速炉においては、万一の炉心損傷時に再臨界と呼ばれる核暴走現象に至る可能性があるので、この再臨界を回避するためには、炉心損傷時の溶融燃料を早期に炉外排出して分散させ、未臨界状態を恒久的に作り出す対策が必要となる。
本発明は、上記の課題を解決するためになされたもので、その目的とするところは、炉心損傷時における溶融燃料排出・分散能力を有し、再臨界に至ることを回避可能な高速炉用燃料集合体構造及び高速炉内の燃料集合体配置構造を提供することにある。
As mentioned above, in a fast reactor, there is a possibility that a nuclear runaway phenomenon called recriticality will occur at the time of core damage, so in order to avoid this recriticality, the molten fuel at the time of core damage must be removed early. It is necessary to take measures to create a subcritical state permanently by discharging it out of the furnace and dispersing it.
The present invention has been made to solve the above-mentioned problems, and its object is to have a molten fuel discharge / dispersion capability at the time of core damage and for a fast reactor capable of avoiding recriticality. It is an object of the present invention to provide a fuel assembly structure and a fuel assembly arrangement structure in a fast reactor.

本発明は、上記の課題を解決するため、下記の手段を採用した。
本発明の請求項1に係る高速炉用燃料集合体構造は、隣接する外周面を密着させた状態にして高速炉内に多数設置されている高速炉用燃料集合体構造であって、中空断面を有する筒状の外套管と、該外套管の内部に収納される多数の燃料棒とを備え、前記外套管の中空断面形状が、隣接する外套管外周面と軸方向へ連続して部分的に密着しない間隙形成部を備えていることを特徴とするものである。
In order to solve the above problems, the present invention employs the following means.
A fuel assembly structure for a fast reactor according to claim 1 of the present invention is a fuel assembly structure for a fast reactor that is installed in the fast reactor in a state where adjacent outer peripheral surfaces are in close contact with each other. And a plurality of fuel rods accommodated in the outer tube, and the hollow cross-sectional shape of the outer tube is partially continuous with the outer peripheral surface of the adjacent outer tube in the axial direction. It is characterized by having a gap forming portion that does not adhere to the surface.

このような本発明の高速炉用燃料集合体構造によれば、中空断面を有する筒状の外套管と、該外套管の内部に収納される多数の燃料棒とを備え、外套管の中空断面形状が、隣接する外套管外周面と軸方向へ連続して部分的に密着しない間隙形成部を備えているので、隣接する外套管の間隙形成部により、外套管外周面に沿って軸方向へ連続する溶融燃料排出ダクトが形成される。   According to such a fuel assembly structure for a fast reactor of the present invention, it is provided with a cylindrical outer tube having a hollow cross section and a number of fuel rods housed inside the outer tube, and the hollow cross section of the outer tube. Since it has a gap forming portion that is not partially in close contact with the adjacent outer tube outer peripheral surface in the axial direction, the shape is formed along the outer tube outer peripheral surface in the axial direction by the gap forming portion of the adjacent outer tube. A continuous molten fuel discharge duct is formed.

上記の発明においては、前記燃料棒が円形断面を有し、前記外套管の内部に正三角形格子配列として多数収納されていることが好ましく、これにより、高速中性子の利用効率を高めることが可能になる。   In the above invention, it is preferable that the fuel rod has a circular cross section and is accommodated in a large number as an equilateral triangular lattice array inside the mantle tube, thereby making it possible to increase the utilization efficiency of fast neutrons. Become.

上記の発明において、前記外套管の中空断面形状を正十二角形とすることが好ましく、これにより、従来一般的に採用されている正六角形断面の延長線上にあるため変更が容易であり、さらに、組み付けの方向性に従来以上の制限がないという利点もある。   In the above-mentioned invention, it is preferable that the hollow cross-sectional shape of the outer tube is a regular dodecagon, which is easy to change because it lies on an extension line of a regular hexagonal cross section that has been generally adopted conventionally, There is also an advantage that there is no limit to the direction of assembly.

本発明に係る高速炉内の燃料集合体配置構造は、請求項1から3のいずれか1項に記載の高速炉用燃料集合体構造を有する高速炉用燃料集合体が、少なくともブランケット燃料に周囲を囲まれた炉心中央部に配置されていることを特徴とするものである。   The fuel assembly arrangement structure in the fast reactor according to the present invention is such that the fast reactor fuel assembly having the fast reactor fuel assembly structure according to any one of claims 1 to 3 surrounds at least the blanket fuel. It is arrange | positioned at the core center part enclosed.

このような高速炉内の燃料集合体配置構造によれば、請求項1から3のいずれか1項に記載の高速炉用燃料集合体構造を有する高速炉用燃料集合体が、少なくともブランケット燃料に周囲を囲まれた炉心中央部に配置されているので、少なくとも炉心中央部に溶融燃料排出ダクトを形成することができる。そして、溶融燃料排出ダクトが不要のブランケット燃料設置領域においては、従来構造の高速炉用燃料集合体を配置し、高速炉内に収納設置される燃料棒の総数低減を最小限に抑えることができる。   According to such a fuel assembly arrangement structure in a fast reactor, the fast reactor fuel assembly having the fast reactor fuel assembly structure according to any one of claims 1 to 3 is at least a blanket fuel. Since it is disposed in the central part of the core surrounded by the periphery, the molten fuel discharge duct can be formed at least in the central part of the core. In the blanket fuel installation area where no molten fuel discharge duct is required, a fast reactor fuel assembly having a conventional structure can be arranged to minimize the reduction in the total number of fuel rods housed and installed in the fast reactor. .

本発明の高速炉用燃料集合体構造及び高速炉内の燃料集合体配置構造によれば、万一の炉心損傷時には、高温となった溶融燃料が外套管を溶融し、炉心部に形成した溶融燃料排出ダクトを通って早期に炉外へ排出・分散するので、未臨界状態を恒久的に作り出す炉心損傷時の溶融燃料排出・分散能力を有し、再臨界に至ることを回避できる。すなわち、万一炉心が損傷時した場合でも、再臨界と呼ばれる核暴走現象に至ることを回避できる。   According to the fuel assembly structure for a fast reactor and the fuel assembly arrangement structure in the fast reactor according to the present invention, in the unlikely event of core damage, the molten fuel that has become hot melts the outer tube and forms a melt in the core portion. Since it is discharged and dispersed out of the reactor early through the fuel discharge duct, it has the ability to discharge and disperse molten fuel at the time of core damage that permanently creates a subcritical state and can avoid recriticality. That is, even if the core is damaged, it is possible to avoid a nuclear runaway phenomenon called recriticality.

本発明に係る高速炉用燃料集合体構造の一実施形態を示す図で、(a)は隣接する複数の燃料集合体配置例を示す断面図、(b)は高速炉用燃料集合体構造の一例を示す拡大断面図である。BRIEF DESCRIPTION OF THE DRAWINGS It is a figure which shows one Embodiment of the fuel assembly structure for fast reactors which concerns on this invention, (a) is sectional drawing which shows the example of several adjacent fuel assembly arrangement | positioning, (b) is the fuel assembly structure for fast reactors It is an expanded sectional view showing an example. 高速炉内における高速炉用燃料集合体の炉内配置例を示す断面図である。It is sectional drawing which shows the example of arrangement | positioning in the reactor of the fuel assembly for fast reactors in a fast reactor. 図1に示した高速炉用燃料集合体構造及び燃料集合体配置例に関する変形例を示す断面図である。FIG. 6 is a cross-sectional view showing a modification of the fast reactor fuel assembly structure and fuel assembly arrangement example shown in FIG. 1. 従来の一般的な高速炉用燃料集合体構造を示す斜視図である。It is a perspective view which shows the conventional general fuel assembly structure for fast reactors. (a)は図4のA−A断面図、(b)は隣接する燃料要素の正三角形格子配列を示す説明図である。(A) is AA sectional drawing of FIG. 4, (b) is explanatory drawing which shows the equilateral triangular lattice arrangement | sequence of an adjacent fuel element. 従来例として、高速炉内における高速炉用燃料集合体の炉内配置例を示す断面図である。It is sectional drawing which shows the example of arrangement | positioning in the reactor of the fuel assembly for fast reactors in a fast reactor as a prior art example.

以下、本発明に係る高速炉用燃料集合体構造及び高速炉内の燃料集合体配置構造の一実施形態を図面に基づいて説明する。
本実施形態の高速炉用燃料集合体構造は、高速中性子を利用する「高速炉」と呼ばれる原子炉に使用される燃料であり、図4に示した従来構造の燃料集合体1と比較して、外套管11の断面形状以外は基本的に同じである。
Hereinafter, an embodiment of a fuel assembly structure for a fast reactor and a fuel assembly arrangement structure in the fast reactor according to the present invention will be described with reference to the drawings.
The fuel assembly structure for a fast reactor according to the present embodiment is a fuel used in a nuclear reactor called a “fast reactor” using fast neutrons, and is compared with the fuel assembly 1 having a conventional structure shown in FIG. The outer tube 11 is basically the same except for the cross-sectional shape.

図1に示す高速炉用燃料集合体(以下、「燃料集合体」と呼ぶ)1Aは、隣接する外周面を密着させた状態にして、高速炉の炉内に多数設置される。図1に示された5本の燃料集合体1Aは、炉内に多数設置される燃料集合体の一部であり、各燃料集合体1Aは、筒体の軸が上下方向となるように配置され、隣接する筒体側壁面(外周面)どうしが密着している。
図示の燃料集合体1Aは、中空断面を有する筒状の外套管11Aと、外套管11Aの内部に正三角形格子配列として収納される円形断面を有する多数の燃料棒10とを備えている。本実施形態の外套管11Aは、その中空断面形状を正十二角形とすることにより、隣接する外套管11Aの外周面と断面形状における一部で密着しない間隙形成部20を備えている。なお、図示の燃料棒10については、正三角形格子配列として外套管11Aの内部に多数収納される円形断面としたが、これに限定されることはない。
A large number of fast reactor fuel assemblies (hereinafter referred to as “fuel assemblies”) 1A shown in FIG. 1 are installed in the reactor of the fast reactor with their adjacent outer peripheral surfaces being in close contact with each other. The five fuel assemblies 1A shown in FIG. 1 are a part of many fuel assemblies installed in the furnace, and each fuel assembly 1A is arranged so that the axis of the cylinder is in the vertical direction. Adjacent cylinder side wall surfaces (outer peripheral surfaces) are in close contact with each other.
The illustrated fuel assembly 1 </ b> A includes a cylindrical outer tube 11 </ b> A having a hollow cross section, and a large number of fuel rods 10 having a circular cross section housed as an equilateral triangular lattice array inside the outer tube 11 </ b> A. The outer tube 11A of the present embodiment is provided with a gap forming portion 20 that is not in close contact with the outer peripheral surface of the adjacent outer tube 11A in a part of the cross-sectional shape by making the hollow cross-sectional shape a regular dodecagon. The illustrated fuel rod 10 has a circular cross section that is accommodated in the outer tube 11A as an equilateral triangular lattice arrangement, but is not limited thereto.

この間隙形成部20は、外套管11Aの断面形状において軸方向へ連続して設けられ、隣接する外套管11Aの外周面と密着しない部分である。このように、隣接する外套管11Aの外周面と軸方向に連続して密着しない部分の間隙形成部20が設けられたことにより、燃料集合体1Aが多数配置された炉内には、外套管11Aの外周面に沿って軸方向へ連続(連通)する溶融燃料排出ダクト30が形成されている。すなわち、本実施形態の高速炉用燃料集合体構造は、隣接する燃料集合体1A間に生じるギャップを形成し、このギャップを溶融燃料排出ダクト30として機能させるものである。   The gap forming portion 20 is a portion that is provided continuously in the axial direction in the cross-sectional shape of the outer tube 11A and does not adhere to the outer peripheral surface of the adjacent outer tube 11A. Thus, by providing the gap forming portion 20 that is not in close contact with the outer peripheral surface of the adjacent mantle tube 11A in the axial direction, the mantle tube is provided in the furnace in which many fuel assemblies 1A are arranged. A molten fuel discharge duct 30 that is continuous (communicated) in the axial direction is formed along the outer peripheral surface of 11A. That is, the fast reactor fuel assembly structure of the present embodiment forms a gap generated between adjacent fuel assemblies 1 </ b> A, and this gap functions as the molten fuel discharge duct 30.

本実施形態に示した燃料集合体1Aの場合、外套管11Aが正十二角形断面を有しているので、正十二角形を構成する12本の辺は、6辺が交互に隣接する外套管11Aと密着する密着部21となり、残った他の6辺が隣接する外套管11Aと密着しない間隙形成部20となる。この結果、図1(a)に示すように、隣接する3本の外套管11Aにより、正三角形断面の溶融燃料排出ダクト30が1本形成される。また、燃料集合体1Aの周囲には、1本あたり6本の溶融燃料排出ダクト30が形成されている。   In the case of the fuel assembly 1A shown in the present embodiment, since the mantle tube 11A has a regular dodecagonal cross section, the twelve sides constituting the regular dodecagon have six sides alternately adjacent to the mantle. The contact portion 21 is in close contact with the tube 11A, and the remaining six sides are the gap forming portion 20 that is not in close contact with the adjacent outer tube 11A. As a result, as shown in FIG. 1A, a single molten fuel discharge duct 30 having an equilateral triangular cross section is formed by the adjacent three outer tube 11A. In addition, six molten fuel discharge ducts 30 are formed around one fuel assembly 1A.

外套管11Aの内部には、正六角形断面の外套管11と同様に、多数の燃料棒10が正三角形格子配列として収納される。
このように、外套管11Aを正十二角形断面とした高速炉用燃料集合体構造を採用すれば、外套管11Aの中空断面形状が隣接する外套管外周面と軸方向へ連続して部分的に密着しない間隙形成部20を備えているので、隣接する外套管11Aの間隙形成部20と協働することにより、外套管11Aの外周面に沿って軸方向へ連続する溶融燃料排出ダクト30が形成される。
Like the outer tube 11 having a regular hexagonal cross section, a large number of fuel rods 10 are accommodated in the outer tube 11A as an equilateral triangular lattice arrangement.
As described above, when the fast reactor fuel assembly structure having the outer tube 11A having a regular dodecagonal cross section is adopted, the hollow cross-sectional shape of the outer tube 11A is partially continuous with the outer surface of the adjacent outer tube in the axial direction. Since the gap forming portion 20 that does not adhere to the outer tube 11A is provided, the molten fuel discharge duct 30 that continues in the axial direction along the outer peripheral surface of the outer tube 11A can be obtained by cooperating with the gap forming portion 20 of the adjacent outer tube 11A. It is formed.

すなわち、万一の炉心損傷時において、高温となった溶融燃料は、外套管11Aを溶融して燃料集合体1Aの外部へと流出するので、上述した溶融燃料排出ダクト30は、溶融燃料を炉外へ速やかに排出させるための溶融燃料排出・分散能力を有する溶融燃料排出通路として機能する。この場合、溶融燃料を炉外へ排出して分散させる主な駆動力は、炉心燃料の核分裂によって生成されるガス圧力、すなわち、燃料要素内に保持されている核分裂生成ガスの圧力である。
この結果、万一炉心が損傷した場合でも、未臨界状態を恒久的に作り出す炉心損傷時の溶融燃料は、溶融燃料排出ダクト30を通って早期に炉外へ排出・分散されるので、溶融燃料の集中に起因する再臨界と呼ばれる核暴走現象に至ることを回避できる。
That is, in the unlikely event of damage to the core, the molten fuel that has reached a high temperature melts the outer tube 11A and flows out of the fuel assembly 1A. It functions as a molten fuel discharge passage having a molten fuel discharge / dispersion capability for quick discharge to the outside. In this case, the main driving force for discharging and dispersing the molten fuel out of the reactor is the gas pressure generated by fission of the core fuel, that is, the pressure of the fission gas held in the fuel element.
As a result, even if the core is damaged, the molten fuel at the time of core damage that permanently creates a subcritical state is discharged and dispersed through the molten fuel discharge duct 30 to the outside of the reactor at an early stage. It is possible to avoid a nuclear runaway phenomenon called recriticality caused by the concentration of.

ところで、正十二角形断面の外套管11Aは、例えば図1(b)に破線で示すように、正六角形断面の角部をカットした形状となる。このため、正十二角形断面の外套管11Aでは、正三角形格子配列にして収納される燃料棒10の収まりが角部カット部分の周辺において低下し、この結果、収納可能な燃料棒10の総本数は多少減少する。   By the way, the outer tube 11A having a regular dodecagonal cross section has a shape in which the corners of the regular hexagonal cross section are cut as shown by a broken line in FIG. For this reason, in the outer tube 11A having a regular dodecagonal cross section, the accommodation of the fuel rods 10 accommodated in an equilateral triangular lattice arrangement is reduced around the corner cut portion. As a result, the total number of fuel rods 10 that can be accommodated is reduced. The number decreases somewhat.

そこで、例えば図2に示す高速炉用燃料集合体の炉内配置例では、外套管11Aを正十二角形断面形状にして溶融燃料排出ダクト30の形成が可能な燃料集合体1Aを炉心中央部に配置し、その外周部にブランケット燃料として配置される燃料集合体1には、従来と同様に、正六角形断面形状の外套管11を用いた高速炉用燃料集合体構造のものを配置する。すなわち、高速炉内には、上述した実施形態の高速炉用燃料集合体構造を有する多数の燃料集合体1Aが炉心中央部に配置され、かつ、燃料集合体1Aの周囲に配設されるブランケット燃料として、中空断面を正六角形とした外套管11の内部に円形断面の燃料棒10を正三角形格子配列にして多数収納した燃料集合体1が配置される。換言すれば、燃料集合体1Aは、少なくともブランケット燃料の燃料集合体1に周囲を囲まれた炉心中央部に配置されていればよい。   Therefore, for example, in the example of the arrangement of the fast reactor fuel assembly shown in FIG. 2, the fuel assembly 1A capable of forming the molten fuel discharge duct 30 with the outer tube 11A having a regular dodecagonal cross-sectional shape is formed in the central portion of the core. As in the prior art, a fuel assembly structure for a fast reactor using a sheath tube 11 having a regular hexagonal cross section is disposed in the fuel assembly 1 disposed as a blanket fuel on the outer periphery thereof. That is, in the fast reactor, a number of fuel assemblies 1A having the fuel assembly structure for the fast reactor according to the above-described embodiment are disposed in the center of the core, and are blankets disposed around the fuel assemblies 1A. As a fuel, a fuel assembly 1 in which a large number of fuel rods 10 having a circular cross section are accommodated in a regular triangular lattice arrangement is disposed inside a sheath tube 11 having a hollow hexagonal cross section. In other words, the fuel assembly 1 </ b> A only needs to be arranged at the center of the core surrounded by at least the blanket fuel assembly 1.

このように、炉心中央部に設置する燃料集合体1Aと、ブランケット燃料として炉心の周囲に配置する燃料集合体1とを併用した高速炉内の燃料集合体配置構造によれば、高温の溶融燃料が外套管11Aを溶融して燃料集合体1Aの外部へ流出する炉心中央部に溶融燃料排出ダクト30を形成して溶融燃料排出・分散能力をもたせ、さらに、外套管11を溶融するような高温にならないため溶融燃料排出ダクト30が不要となるブランケット燃料設置領域には、従来構造の燃料集合体1を配置し、高速炉内に収納設置される燃料棒10の総数低減を最小限に抑えている。   Thus, according to the fuel assembly arrangement structure in the fast reactor using the fuel assembly 1A installed in the center of the core and the fuel assembly 1 arranged around the core as a blanket fuel, the high-temperature molten fuel Forms a molten fuel discharge duct 30 at the center of the core where the outer tube 11A is melted and flows out of the fuel assembly 1A to provide molten fuel discharge / dispersion capability, and further, the outer tube 11 is melted at a high temperature. In the blanket fuel installation area where the molten fuel discharge duct 30 is not required, the conventional fuel assembly 1 is arranged to minimize the total number of fuel rods 10 housed and installed in the fast reactor. Yes.

上述した実施形態では、外套管11Aの中空断面形状を正十二角形としたが、これに限定されることはなく、例えば図3に示す変形例のように、燃料集合体1Bの外套管11Bを円形断面とし、円弧状の間隙形成部20′により溶融燃料排出ダクト30′を形成するようにしてもよい。
すなわち、本実施形態において、外套管11A,11Bの断面形状については、隣接する間隙形成部20,20′により溶融燃料排出ダクト30,30′を形成できればよく、従って、正十二角筒状や円形の他にも、正八角形や正十六角形など、溶融燃料排出ダクトを形成可能な種々の多角筒状が採用可能である。
In the above-described embodiment, the hollow cross-sectional shape of the mantle tube 11A is a regular dodecagon, but it is not limited to this. For example, as in the modification shown in FIG. 3, the mantle tube 11B of the fuel assembly 1B. May have a circular cross section, and the molten fuel discharge duct 30 'may be formed by the arc-shaped gap forming portion 20'.
That is, in this embodiment, the outer tube 11A, 11B has a cross-sectional shape as long as the molten fuel discharge ducts 30, 30 ′ can be formed by the adjacent gap forming portions 20, 20 ′. In addition to the circular shape, various polygonal cylindrical shapes that can form a molten fuel discharge duct, such as a regular octagon and a regular dodecagon, can be employed.

しかし、外套管11の中空断面形状を正十二角形とした外套管11Aは、燃料棒10を正三角格子状にして配列する上で最も効率のよい正六角形断面の延長線上にあるため、従来構造からの変更が容易である。すなわち、正十二角筒状の外套管11Aは、既存の外套管11である正六角筒状の延長として考えやすく、従って、特にブランケット燃料を正六角形のままとした場合は、正十二角形との組合せが容易である。
また、円形断面の外套管11Bは、多角形断面形状の筒体と比較して製造が容易になるという利点を有している。
However, the outer tube 11A in which the hollow cross-sectional shape of the outer tube 11 is a regular dodecagon is on the extension line of the regular hexagonal cross section that is most efficient in arranging the fuel rods 10 in a regular triangular lattice shape. Easy to change from structure. In other words, the outer tube 11A having a regular dodecagonal tube shape can be easily considered as an extension of the existing hexagonal tube shape that is the existing mantle tube 11. Therefore, when the blanket fuel is left in a regular hexagonal shape, the dodecagonal tube shape is easy. Easy to combine with.
Further, the outer tube 11B having a circular cross section has an advantage that it is easy to manufacture as compared with a cylindrical body having a polygonal cross section.

上述したように、本実施形態の高速炉用燃料集合体構造によれば、万一の炉心損傷時に溶融燃料が炉心部に形成した溶融燃料排出ダクト30を通って早期に炉外へ排出・分散するので、再臨界と呼ばれる核暴走現象に至ることを回避できる。
なお、本発明は上述した実施形態に限定されることはなく、その要旨を逸脱しない範囲内において適宜変更することができる。
As described above, according to the fast reactor fuel assembly structure of the present embodiment, in the unlikely event of core damage, molten fuel is discharged and dispersed out of the reactor early through the molten fuel discharge duct 30 formed in the core. Therefore, it is possible to avoid a nuclear runaway phenomenon called recriticality.
In addition, this invention is not limited to embodiment mentioned above, In the range which does not deviate from the summary, it can change suitably.

1,1A,1B 高速炉用燃料集合体(燃料集合体)
10 燃料棒
11,11A,11B 外套管
20,20′ 間隙形成部
21 密着部
30,30′ 溶融燃料排出ダクト
1,1A, 1B Fast Reactor Fuel Assembly (Fuel Assembly)
DESCRIPTION OF SYMBOLS 10 Fuel rod 11, 11A, 11B Mantle tube 20, 20 'Gap formation part 21 Contact | adherence part 30, 30' Molten fuel discharge duct

Claims (4)

隣接する外周面を密着させた状態にして高速炉内に多数設置されている高速炉用燃料集合体構造であって、
中空断面を有する筒状の外套管と、該外套管の内部に収納されている多数の燃料棒とを備え、
前記外套管の中空断面形状が、隣接する外套管外周面と軸方向へ連続して部分的に密着しない間隙形成部を備え
前記外套管の中空断面形状が正十二角形であることを特徴とする高速炉用燃料集合体構造。
A fuel assembly structure for a fast reactor that is installed in the fast reactor in a state where the adjacent outer peripheral surfaces are in close contact with each other,
A cylindrical outer tube having a hollow cross section, and a number of fuel rods housed in the outer tube,
A hollow cross-sectional shape of the outer tube is provided with a gap forming part that does not partially adhere to the outer peripheral surface of the adjacent outer tube continuously in the axial direction ,
A fuel assembly structure for a fast reactor, wherein a hollow cross-sectional shape of the outer tube is a regular dodecagon .
前記燃料棒が円形断面を有し、前記外套管の内部に正三角形格子配列として多数収納されていることを特徴とする請求項1に記載の高速炉用燃料集合体構造。   2. The fuel assembly structure for a fast reactor according to claim 1, wherein the fuel rod has a circular cross section and is accommodated in the outer tube as a regular triangular lattice array. 請求項1又は2に記載の高速炉用燃料集合体構造を有する高速炉用燃料集合体が、少なくともブランケット燃料に周囲を囲まれた炉心中央部に配置されていることを特徴とする高速炉内の燃料集合体配置構造。 A fast reactor fuel assembly having the fuel assembly structure for a fast reactor according to claim 1 or 2 , wherein the fast reactor fuel assembly is disposed at least in a central portion of the core surrounded by a blanket fuel. Fuel assembly arrangement structure. 前記炉心中央部に中空断面形状を正十二角形とした前記外套管を配置し、その外周部に中空断面形状を正六角形とした前記外套管を配置することを特徴とする請求項3に記載の高速炉内の燃料集合体配置構造。The outer tube having a hollow cross-sectional shape of a regular dodecagon is disposed at the core central portion, and the outer tube having a hollow cross-sectional shape of a regular hexagon is disposed at an outer peripheral portion thereof. The fuel assembly arrangement structure in the fast reactor.
JP2011268066A 2011-12-07 2011-12-07 Fuel assembly structure for fast reactor and fuel assembly arrangement structure in fast reactor Expired - Fee Related JP5896711B2 (en)

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