JP2001235574A - Reflector control type fast breeder reactor - Google Patents

Reflector control type fast breeder reactor

Info

Publication number
JP2001235574A
JP2001235574A JP2000049031A JP2000049031A JP2001235574A JP 2001235574 A JP2001235574 A JP 2001235574A JP 2000049031 A JP2000049031 A JP 2000049031A JP 2000049031 A JP2000049031 A JP 2000049031A JP 2001235574 A JP2001235574 A JP 2001235574A
Authority
JP
Japan
Prior art keywords
neutron
reflector
core
reactor
fast breeder
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
Application number
JP2000049031A
Other languages
Japanese (ja)
Other versions
JP4101424B2 (en
Inventor
Tsugio Yokoyama
次男 横山
Hisato Matsumiya
壽人 松宮
Yasushi Tsuboi
靖 坪井
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Toshiba Corp
Original Assignee
Toshiba Corp
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Priority to JP2000049031A priority Critical patent/JP4101424B2/en
Application filed by Toshiba Corp filed Critical Toshiba Corp
Priority to US09/749,547 priority patent/US7139352B2/en
Publication of JP2001235574A publication Critical patent/JP2001235574A/en
Priority to US11/348,333 priority patent/US20060126775A1/en
Priority to US11/377,178 priority patent/US20060210010A1/en
Priority to US12/128,524 priority patent/US20090010374A1/en
Application granted granted Critical
Publication of JP4101424B2 publication Critical patent/JP4101424B2/en
Priority to US12/270,680 priority patent/US20090080586A1/en
Priority to US12/625,173 priority patent/US20100067641A1/en
Priority to US12/764,163 priority patent/US20100322369A1/en
Priority to US13/006,260 priority patent/US20110194664A1/en
Priority to US13/014,206 priority patent/US8331523B2/en
Priority to US13/361,543 priority patent/US8711997B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

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Classifications

    • 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Abstract

PROBLEM TO BE SOLVED: To lengthen the service life of a reactor core without lengthening the fuel length of a fuel assembly. SOLUTION: This reflector control type fast breeder reactor is provided with a neutron reflector 5 outside of a reactor core 2 submerged in a liquid metal coolant in a reactor vessel 1, and controls the reactivity of the reactor core 2 by moving the reflector 5 vertically to adjust the leakage of neutrons from the reactor core 2. In this case, a combustible poison assembly 19 containing a mixed material of a neutron moderator and a neutron absorber is charged in a center part clearance charged with a large number of fuel assemblies 16, in the reactor core 2. The fast neutrons are thereby moderated by the neutron moderator, and the neutrons are absorbed by the neutron absorber to heighten neutron absorbing capacity.

Description

【発明の詳細な説明】DETAILED DESCRIPTION OF THE INVENTION

【0001】[0001]

【発明の属する技術分野】本発明は中性子反射体を上下
方向に移動させて炉心からの中性子の漏洩を調整して炉
心の反応度を制御する反射体制御方式の液体金属冷却型
高速増殖炉(以下、高速炉と記す)に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a reflector-controlled liquid metal-cooled fast breeder reactor for controlling the reactivity of a reactor core by adjusting the leakage of neutrons from the reactor core by moving a neutron reflector vertically. Hereinafter, referred to as a fast reactor).

【0002】[0002]

【従来の技術】図5及び図6により従来の反射体制御方
式の高速炉の概要を説明する。図5はこの種の高速炉の
概略的縦断面図で、図6は図5におけるA−A矢視方向
横断面図である。ただし、図6中には図5中に記載して
ないガードベッセル18を記載している。
2. Description of the Related Art An outline of a conventional reflector controlled fast furnace will be described with reference to FIGS. FIG. 5 is a schematic longitudinal sectional view of this type of fast reactor, and FIG. 6 is a transverse sectional view taken along the line AA in FIG. However, FIG. 6 shows a guard vessel 18 not shown in FIG.

【0003】図5及び図6において、符号1は原子炉容
器、2は原子炉容器1内の中央部に設置された炉心で、
炉心2は外側が炉心バレル3により囲繞され内部に多数
体の燃料集合体と、その中央部に装荷される中性子吸収
用チャンネルとからなっている。炉心バレル3の外側に
は所定の隙間を有して隔壁4が配置され、炉心バレル3
と隔壁4との隙間には中性子反射体5と、この中性子反
射体5を駆動する中性子反射体駆動装置6が設置されて
いる。
[0005] In FIGS. 5 and 6, reference numeral 1 denotes a reactor vessel, and 2 denotes a reactor core installed in the center of the reactor vessel 1.
The core 2 is surrounded by a core barrel 3 on the outside, and includes a large number of fuel assemblies inside, and a neutron absorption channel loaded at the center thereof. A partition wall 4 is disposed outside the core barrel 3 with a predetermined gap.
A neutron reflector 5 and a neutron reflector driving device 6 for driving the neutron reflector 5 are provided in a gap between the neutron reflector 5 and the partition wall 4.

【0004】炉心バレル3と隔壁4との隙間は炉心2の
運転に使用する中性子反射体5の移動領域であるととも
に、冷却材の流路ともなっている。隔壁4と原子炉容器
1との間には多数の中性子しゃへい体7が配置されてい
る。
[0004] The gap between the core barrel 3 and the partition wall 4 is a moving area of the neutron reflector 5 used for the operation of the core 2 and also serves as a coolant flow path. A large number of neutron shields 7 are arranged between the partition wall 4 and the reactor vessel 1.

【0005】炉心2,炉心バレル3,中性子反射体5,
隔壁4及び中性子しゃへい体7は支持構造物8上に設置
されている。支持構造物8には冷却材通流孔(図示せ
ず)が多数設けられており、支持構造物8と原子炉容器
1との間は下部プレナム9となっている。また、隔壁4
と原子炉容器1との間に配置された中性子しゃへい体7
の上方には中間熱交換器10と電磁ポンプ11が上下に設け
られており、中間熱交換器10には二次側冷却材通流配管
12が取り付けられている。
[0005] core 2, core barrel 3, neutron reflector 5,
The partition wall 4 and the neutron shield 7 are installed on a support structure 8. The support structure 8 is provided with a large number of coolant flow holes (not shown), and a lower plenum 9 is provided between the support structure 8 and the reactor vessel 1. Also, the partition 4
Neutron shield 7 placed between the reactor and reactor vessel 1
An intermediate heat exchanger 10 and an electromagnetic pump 11 are provided above and below, and the intermediate heat exchanger 10 has a secondary coolant flow pipe.
12 are installed.

【0006】原子炉容器1の上端開口部はしゃへいプラ
グ13により閉塞されており、原子炉容器1内は液体ナト
リウム等の液体金属の冷却材14で満たされている。冷却
材14としゃへいプラグ13の間は上部プレナム15となって
おり、上部プレナム15には不活性ガスが封入される。
[0006] The upper end opening of the reactor vessel 1 is closed by a shielding plug 13, and the inside of the reactor vessel 1 is filled with a coolant 14 of a liquid metal such as liquid sodium. An upper plenum 15 is provided between the coolant 14 and the shielding plug 13, and the upper plenum 15 is filled with an inert gas.

【0007】炉心2は図6に示したように炉心バレル3
と、この炉心バレル3によって囲まれハニカム状に配列
された例えば18本の燃料集合体16と、これらの燃料集合
体16の中央部に装荷される中性子吸収用チャンネル17と
から構成されている。中性子吸収用チャンネル17は炉心
2の炉停止用で、運転時には上方に引き抜かれる。な
お、図6中符号18はガードベッセルで、原子炉容器1の
周囲を包囲する保護容器である。
[0007] The core 2 is a core barrel 3 as shown in FIG.
For example, there are 18 fuel assemblies 16 arranged in a honeycomb shape surrounded by the core barrel 3, and neutron absorption channels 17 loaded at the center of these fuel assemblies 16. The neutron absorption channel 17 is for shutting down the reactor core 2 and is withdrawn upward during operation. In FIG. 6, reference numeral 18 denotes a guard vessel, which is a protective vessel surrounding the reactor vessel 1.

【0008】ここで、冷却材14は電磁ポンプ11によって
原子炉容器1の内部を矢印で示すように循環して炉心2
内に流入し、炉心2からの熱を取り出して炉心2から流
出する。流出した冷却材14は中間熱交換器10によって二
次冷却材配管12内を流れる二次冷却材と熱交換する。
Here, the coolant 14 is circulated by the electromagnetic pump 11 through the inside of the reactor vessel 1 as shown by arrows, and
, And takes out heat from the core 2 and flows out of the core 2. The outflowing coolant 14 exchanges heat with the secondary coolant flowing in the secondary coolant pipe 12 by the intermediate heat exchanger 10.

【0009】すなわち、冷却材14は隔壁4の内側を下か
ら上方向に流れ、その途中で炉心2に流入し、核分裂に
よって生じた熱を奪って温度が上昇する。そして、この
温度が上昇した冷却材14は中間熱交換器10内に流入し、
ここで二次冷却材との熱交換を行って冷却される。
That is, the coolant 14 flows upward from the inside of the partition wall 4 from below, and flows into the reactor core 2 on the way, taking heat generated by nuclear fission and increasing the temperature. Then, the coolant 14 whose temperature has risen flows into the intermediate heat exchanger 10,
Here, it is cooled by performing heat exchange with the secondary coolant.

【0010】冷却された冷却材14は、中間熱交換器10か
ら下方向に流出し、電磁ポンプ11によって昇圧され隔壁
4と原子炉容器1との間と中性子しゃへい体7間を通り
抜けて支持構造物8を流下し、下部プレナム9に流入し
てから上方に向けて炉心2の下部に回り込み、再び炉心
2内に導入される。
The cooled coolant 14 flows downward from the intermediate heat exchanger 10, is pressurized by the electromagnetic pump 11, passes between the partition wall 4 and the reactor vessel 1, and between the neutron shield 7 and the support structure. The material 8 flows down, flows into the lower plenum 9, then goes upward to the lower part of the core 2, and is introduced into the core 2 again.

【0011】中性子しゃへい体7は原子炉容器1の中性
子照射量を全プラント寿命にわたって所定値以下に制限
するためのものである。中性子反射体5は中性子反射体
駆動装置6の駆動に伴って、炉心バレル3と隔壁4との
間の移動領域内をこれに沿って上下方向に移動する。こ
の動作により炉心2からの中性子の漏洩を調整し、炉心
2の燃焼による反応度変化を補償する。
The neutron shield 7 is for limiting the neutron irradiation dose of the reactor vessel 1 to a predetermined value or less over the entire plant life. The neutron reflector 5 moves up and down in the movement area between the core barrel 3 and the partition 4 with the driving of the neutron reflector driving device 6. This operation adjusts the leakage of neutrons from the core 2 and compensates for the reactivity change due to the combustion of the core 2.

【0012】[0012]

【発明が解決しようとする課題】しかしながら、従来の
中性子反射体5を移動して炉心2の反応度を制御する高
速増殖炉において、炉心2の寿命を延ばそうとすると、
燃料集合体16の燃料長を長くする必要がある。すなわ
ち、燃焼が進むに従い、燃料集合体16の有する反応度は
負となり、その分、炉心2の下部から炉心2の高さを覆
うように中性子反射体5を持ち上げ、中性子反射能力を
増大させて、中性子反射体5の正の反応度を増大させ
て、炉心2全体としては常に反応度を0として、つまり
臨界状態で燃焼を続ける運転を行わなければならない。
However, in a conventional fast breeder reactor in which the reactivity of the core 2 is controlled by moving the neutron reflector 5, the life of the core 2 is extended.
It is necessary to increase the fuel length of the fuel assembly 16. That is, as the combustion proceeds, the reactivity of the fuel assembly 16 becomes negative, and accordingly, the neutron reflector 5 is lifted from the lower part of the core 2 so as to cover the height of the core 2 to increase the neutron reflection ability. It is necessary to increase the positive reactivity of the neutron reflector 5 so that the reactivity of the core 2 as a whole is always 0, that is, an operation in which combustion is continued in a critical state.

【0013】このため、運転期間を延ばそうとすると、
燃料長を長くしなければならない。燃料長を長くすると
原子炉容器1の全体も長くなり、経済性が悪化する。ま
た、炉心2の寿命中の変形による反応度の変化、燃料集
合体16の引き抜き力の増加等の課題がある。
For this reason, when trying to extend the driving period,
The fuel length must be increased. If the fuel length is lengthened, the entire length of the reactor vessel 1 is also lengthened, and the economic efficiency deteriorates. There are also problems such as a change in reactivity due to deformation during the life of the reactor core 2 and an increase in pulling force of the fuel assembly 16.

【0014】本発明は上記課題を解決するためになされ
たもので、燃料長を長く延ばすことなく、初期の余剰反
応度を大きくするだけで炉心の寿命を延ばすことがで
き、経済性及び燃料の健全性が優れた中性子反射体制御
方式の高速増殖炉を提供することにある。
SUMMARY OF THE INVENTION The present invention has been made to solve the above-mentioned problems, and it is possible to extend the life of the core only by increasing the initial excess reactivity without increasing the fuel length, thereby improving the economy and fuel efficiency. It is an object of the present invention to provide a fast breeder reactor with a neutron reflector control system having excellent soundness.

【0015】[0015]

【課題を解決するための手段】請求項1に係る発明は、
原子炉容器内の液体金属冷却材に浸された炉心の外側に
中性子反射体を配置し、この中性子反射体を上下方向に
移動させて前記炉心からの中性子の漏洩を調整すること
によって前記炉心の反応度を制御する反射体制御方式の
高速増殖炉において、前記炉心内に中性子減速材と中性
子吸収材を混合した物質を装荷してなることを特徴とす
る。
The invention according to claim 1 is
A neutron reflector is arranged outside the core immersed in the liquid metal coolant in the reactor vessel, and the neutron reflector is moved up and down to adjust the leakage of neutrons from the core so that the neutron leaks from the core. In a reflector-controlled fast breeder reactor for controlling the reactivity, a material obtained by mixing a neutron moderator and a neutron absorber is loaded in the core.

【0016】本発明において、原子炉が最初に運転を開
始した場合、つまり、炉心が臨界に達したとき、炉内の
一部の中性子は炉心内に配置した中性子減速材と中性子
吸収材を混合した物質、例えば水素化ジルコニウムとガ
ドリニウムを混合した物質に吸収された状態にある。
In the present invention, when the reactor starts operation for the first time, that is, when the core reaches criticality, some neutrons in the reactor mix the neutron moderator and the neutron absorber arranged in the core. In a mixed state, for example, a mixture of zirconium hydride and gadolinium.

【0017】炉心の燃焼が進むに従い、燃料集合体から
発生する中性子量は少なくなっていくが、炉心内に配置
した水素化ジルコニウムとガドリニウムを混合した物質
のガドリニウムも中性子を吸収し、核変換するので、減
少する。このため、炉心の燃焼が進むに従い、水素化ジ
ルコニウムとガドリニウムを混合した物質の中性子吸収
能力も低下する。
As the burning of the core progresses, the amount of neutrons generated from the fuel assembly decreases, but gadolinium, which is a mixture of zirconium hydride and gadolinium disposed in the core, also absorbs neutrons and transmutes. So decrease. For this reason, as the core burns, the neutron absorption ability of a substance obtained by mixing zirconium hydride and gadolinium also decreases.

【0018】このことから、燃焼が進むことによる燃料
の余剰反応度の変化を従来技術より見かけ上小さくする
ことができる。すなわち、炉心寿命を延ばすために燃料
長を延ばさなくでも、初期の余剰反応度を大きくするだ
けで炉心寿命を延ばすことができる。したがって、本発
明によれば、従来の炉心を長寿命化するための燃料長を
延ばす方法による経済性の悪化、燃料健全性の課題を解
決することができ、炉心寿命を延ばすことができる。
Accordingly, the change in the excess reactivity of the fuel due to the progress of the combustion can be made apparently smaller than in the prior art. In other words, the core life can be extended only by increasing the initial excess reactivity without extending the fuel length in order to extend the core life. Therefore, according to the present invention, it is possible to solve the problems of reduced economy and fuel integrity by the conventional method of extending the fuel length for extending the life of the core, and prolong the life of the core.

【0019】請求項2に係る発明は、原子炉容器内の液
体金属冷却材に浸された炉心の外側に中性子反射体を配
置し、この中性子反射体を上下方向に移動させて前記炉
心からの中性子の漏洩を調整することによって前記炉心
の反応度を制御する反射体制御方式の高速増殖炉におい
て、中性子減速材と中性子吸収材を混合した物質を含む
中性子吸収体棒とし、この中性子吸収体棒を複数本ラッ
パ管内に組み込んで可燃性毒物集合体とし、この可燃性
毒物集合体を前記炉心の中央部に装荷してなることを特
徴とする。
According to a second aspect of the present invention, a neutron reflector is disposed outside a core immersed in a liquid metal coolant in a reactor vessel, and the neutron reflector is moved up and down to move the neutron reflector from the core. In a reflector-controlled fast breeder reactor that controls the reactivity of the core by adjusting the leakage of neutrons, a neutron absorber rod containing a substance obtained by mixing a neutron moderator and a neutron absorber, and the neutron absorber rod Are assembled into a plurality of wrapper tubes to form a burnable poisonous aggregate, and the burnable poisonous aggregate is loaded in a central portion of the core.

【0020】本発明によれば、中性子吸収材であるたと
えばガドリニウムとともに中性子減速材である水素化ジ
ルコニウムを混合した可燃性毒物を炉心の中央部に配置
することにより、中性子を効果的に減速し、中性子吸収
材に吸収させ、中性子吸収能力を高めることができる。
According to the present invention, neutrons are effectively decelerated by arranging a burnable poison mixed with neutron absorbing material such as gadolinium and zirconium hydride as a neutron moderator in the center of the core, It can be absorbed by a neutron absorbing material to enhance the neutron absorbing ability.

【0021】請求項3に係る発明は、原子炉容器内の液
体金属冷却材に浸された炉心の外側に中性子反射体を配
置し、この中性子反射体を上下方向に移動させて前記炉
心からの中性子の漏洩を調整することによって前記炉心
の反応度を制御する反射体制御方式の高速増殖炉におい
て、中性子減速材と中性子吸収材を混合した物質を前記
中性子反射体の上部キャビティに装荷してなることを特
徴とする。
According to a third aspect of the present invention, a neutron reflector is disposed outside a reactor core immersed in a liquid metal coolant in a reactor vessel, and the neutron reflector is moved up and down to move the neutron reflector from the reactor core. In a reflector-controlled fast breeder reactor that controls reactivity of the core by adjusting neutron leakage, a material obtained by mixing a neutron moderator and a neutron absorber is loaded into the upper cavity of the neutron reflector. It is characterized by the following.

【0022】本発明によれば、従来、中性子反射体の上
部は中性子反射体の価値を上げるためにキャビティにな
っているが、中性子反射体の上部の中性子吸収体には中
性子しゃへい能力が加わることによって、上部構造物が
簡素化できる。
According to the present invention, conventionally, the upper part of the neutron reflector is formed as a cavity in order to increase the value of the neutron reflector, but the neutron absorber above the neutron reflector has an additional neutron shielding ability. Thereby, the superstructure can be simplified.

【0023】請求項4に係る発明は、前記中性子減速材
と中性子吸収材を混合した物質を前記炉心内に装荷する
にあたり、前記中性子吸収棒の径方向分布を内側ほど濃
くしてなることを特徴とする。
The invention according to claim 4 is characterized in that, when a substance obtained by mixing the neutron moderator and the neutron absorbing material is loaded into the core, the radial distribution of the neutron absorbing rods is made deeper toward the inside. And

【0024】本発明によれば、初期の熱中性子の吸収効
果の低下幅を下げ、吸収反応度の低下を直線的に減少さ
せる。これにより、燃焼による余剰反応度の変化が見か
け上直線的となるため、反射体の駆動による燃焼制御も
直線的で、一定速度で行うことができ、燃焼制御が容易
になる。
According to the present invention, the reduction in the initial thermal neutron absorption effect is reduced, and the reduction in the absorption reactivity is linearly reduced. Thus, the change in the excess reactivity due to the combustion becomes apparently linear, so that the combustion control by driving the reflector can be performed linearly and at a constant speed, thereby facilitating the combustion control.

【0025】請求項5に係る発明は、前記中性子反射体
の上部に装荷した中性子減速材と中性子吸収材を混合し
た物質は黒鉛とガドリニウムとを混合した物質からなる
ことを特徴とする。
The invention according to claim 5 is characterized in that the material in which the neutron moderator and the neutron absorber loaded on the neutron reflector are mixed is a material in which graphite and gadolinium are mixed.

【0026】本発明によれば、中性子減速材と中性子吸
収材を混合した物質を炉心内に装荷する場合、中性子減
速材として黒鉛を使用すると高温での健全性に優れ、設
計の裕度が増え、冷却材出口温度を高温化した場合にも
十分対応できる。
According to the present invention, when a material containing a mixture of a neutron moderator and a neutron absorber is loaded into a reactor core, if graphite is used as the neutron moderator, the soundness at high temperatures is excellent and the design margin is increased. In addition, it can sufficiently cope with a case where the coolant outlet temperature is increased.

【0027】請求項6に係る発明は、前記中性子減速材
と中性子吸収材を混合した物質を被覆管内に充填して中
性子吸収体棒を形成するにあたり、前記中性子減速材と
中性子吸収材を顆粒状に成形し、この顆粒状物を前記被
覆管内に振動充填法により充填してなることを特徴とす
る。
According to a sixth aspect of the present invention, when the neutron moderator and the neutron absorbing material are mixed into a cladding tube to form a neutron absorbing rod, the neutron moderating material and the neutron absorbing material are granulated. And the granular material is filled in the cladding tube by a vibration filling method.

【0028】本発明によれば、中性子減速材含有中性子
吸収体の製造工程が簡素化され、製造時に遠隔操作が容
易となり、中性子減速材または中性子吸収材が放射性物
質である場合などの危険物が存在しても中性子減速材含
有中性子吸収体の製造が容易となる。
According to the present invention, the manufacturing process of the neutron moderator-containing neutron absorber is simplified, remote control is facilitated during the manufacturing, and dangerous substances such as when the neutron moderator or the neutron absorber is a radioactive substance. Even if it is present, it becomes easy to manufacture a neutron absorber containing a neutron moderator.

【0029】請求項7に係る発明は、前記中性子減速材
と中性子吸収材を混合した物質を収納する被覆管または
ラッパ管の内面に水素の透過を防止する内張りを設けて
なることを特徴とする。
[0029] The invention according to claim 7 is characterized in that a cladding tube or a wrapper tube for containing a substance obtained by mixing the neutron moderator and the neutron absorbing material is provided with an inner lining for preventing permeation of hydrogen. .

【0030】本発明によれば、被覆管またはラッパ管の
内面に水素透過防止材を内張りすることにより、減速材
含有中性子吸収体の炉心での燃焼によって生成される水
素の被覆管またはラッパ管外への漏洩を防止できる。
According to the present invention, the hydrogen permeation preventing material is lined on the inner surface of the cladding tube or the wrapper tube, so that the hydrogen produced by the combustion of the neutron absorber containing the moderator in the core is not covered by the cladding tube or the wrapper tube. Leakage can be prevented.

【0031】請求項8に係る発明は、原子炉容器内の液
体金属冷却材に浸された炉心の外側に中性子反射体を配
置し、この中性子反射体を上下方向に移動させて前記炉
心からの中性子の漏洩を調整することによって前記炉心
の反応度を制御する反射体制御方式の高速増殖炉におい
て、前記炉心内に中性子減速材と中性子吸収材を混合し
た物質と、核分裂生成物を混合してなる減速材含有中性
子吸収体を配置したことを特徴とする。
According to the present invention, a neutron reflector is disposed outside a core immersed in a liquid metal coolant in a reactor vessel, and the neutron reflector is moved in a vertical direction to move the neutron reflector from the core. In a reflector-controlled fast breeder reactor that controls the reactivity of the core by adjusting the leakage of neutrons, a material in which a neutron moderator and a neutron absorber are mixed in the core, and fission products are mixed. Characterized in that a neutron absorber containing a moderator is disposed.

【0032】本発明によれば、中性子吸収棒に核分裂生
成物を混合することによって他の原子炉で生成された放
射性廃棄物に含有されている核分裂生成物の有効利用を
図ることができるとともに、核分裂生成物を消費し減量
化に寄与できる。
According to the present invention, by mixing fission products with a neutron absorbing rod, it is possible to effectively utilize fission products contained in radioactive waste generated in another nuclear reactor, It can consume fission products and contribute to weight reduction.

【0033】請求項9に係る発明は、前記減速材含有中
性子吸収体を前記炉心内に装荷するにあたり、前記中性
子吸収材の可燃性毒物の径方向分布を内側ほど濃くして
なることを特徴とする。
The ninth aspect of the present invention is characterized in that, when the moderator-containing neutron absorber is loaded in the core, the radial distribution of the burnable poison of the neutron absorber is made deeper toward the inside. I do.

【0034】本発明によれば、減速材含有中性子吸収体
の燃焼による吸収反濃度の低下を直線的にすることによ
って、余剰反応度の低下を見かけ上直線的にし、必要と
なる中性子反射体の駆動量の制御を容易にし、炉心の燃
焼制御を容易にすることができる。
According to the present invention, the decrease in the absorption re-concentration due to the combustion of the neutron absorber containing the moderator is made linear, so that the excess reactivity is made apparently linear, so that the necessary neutron reflector is reduced. Control of the driving amount can be facilitated, and combustion control of the core can be facilitated.

【0035】請求項10に係る発明は、前記減速材含有中
性子吸収体を前記炉心内中央部近傍の燃料集合体に設け
てなることを特徴とする。本発明によれば、燃料集合体
内に中性子減速材と熱中性子吸収材を混合した中性子吸
収体棒を配置することにより、炉心中央部に可燃性毒物
集合体を装荷する必要がない。そのため、炉心中央部に
設ける中性子吸収体棒の設計が容易になる。
The invention according to claim 10 is characterized in that the moderator-containing neutron absorber is provided in a fuel assembly near a central portion in the core. According to the present invention, there is no need to load a burnable poisonous assembly in the center of the core by disposing a neutron absorber rod in which a neutron moderator and a thermal neutron absorber are mixed in the fuel assembly. Therefore, the design of the neutron absorber rod provided in the center of the core becomes easy.

【0036】請求項11に係る発明は、前記減速材含有中
性子吸収体を前記炉心中央に装荷する可燃性毒物集合体
に設けてなることを特徴とする。本発明によれば、燃焼
末期に中性子エネルギーの小さな領域での吸収効果が減
少するため、通常の高速増殖炉の炉心より燃焼末期でも
中性子エネルギーの低い領域での核分裂の寄与が大き
い。このため、燃焼末期でも冷却材生成ボイド生成によ
るスペクトルの硬化に対して正反応度への移行が大きく
ならず、燃焼末期にボイド反応度が正側に移行し難くな
り、安全上有利となる。
The invention according to claim 11 is characterized in that the neutron absorber containing the moderator is provided in a burnable poisonous aggregate loaded in the center of the core. According to the present invention, since the absorption effect in the region where the neutron energy is small at the end of combustion is reduced, the contribution of fission in the region where the neutron energy is low even at the end of combustion is larger than in the core of a normal fast breeder reactor. For this reason, even in the last stage of the combustion, the shift to the positive reactivity does not become large with respect to the hardening of the spectrum due to the coolant generation void generation, and the void reactivity hardly shifts to the positive side at the end of the combustion, which is advantageous in safety.

【0037】請求項12に係る発明は、前記液体金属冷却
材は鉛または鉛−ビスマス合金からなることを特徴とす
る。本発明によれば、冷却材に鉛または鉛とビスマス合
金を使用することにより、さらに中性子増殖性が高く、
炉心寿命を延ばすことができる。
The invention according to claim 12 is characterized in that the liquid metal coolant is made of lead or a lead-bismuth alloy. According to the present invention, the use of lead or a lead and bismuth alloy for the coolant further increases the neutron multiplication,
The life of the core can be extended.

【0038】[0038]

【発明の実施の形態】図1(a),(b),図2及び図
3により、本発明に係る高速増殖炉の第1の実施の形態
を説明する。図1(a)は本実施の形態に係る高速増殖
炉の要部を示す横断面図、図1(b)は図1(a)の縦
断面図、図2は図1(a),(b)における可燃性毒物
集合体の横断面図、図3は本実施の形態の作用を説明す
るための特性図で、図1(a),(b)中、図5及び図
6と同一部分または同様の機能を有する部分には同一符
号を付して、重複する部分の説明は省略する。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS A first embodiment of a fast breeder reactor according to the present invention will be described with reference to FIGS. 1 (a), 1 (b), 2 and 3. FIG. 1A is a cross-sectional view showing a main part of the fast breeder reactor according to the present embodiment, FIG. 1B is a vertical cross-sectional view of FIG. 1A, and FIG. 3B is a cross-sectional view of the burnable poisonous substance aggregate, and FIG. 3 is a characteristic diagram for explaining the operation of the present embodiment. In FIG. 1A and FIG. Or, portions having similar functions are denoted by the same reference numerals, and description of overlapping portions will be omitted.

【0039】本実施の形態が従来例と異なる点は、図6
に示した炉心2の中央部に装荷した中性子吸収用チャン
ネル17の代りに、図1に示したように可燃性毒物集合体
19を装荷してなることにある。図1は例えば炉心2の等
価直径約80cm,炉心2の有効長約200cm の反射体制御方
式のナトリウム冷却小型高速増殖炉に適用した例を示し
ている。
This embodiment is different from the conventional example in that FIG.
Instead of the neutron absorption channel 17 loaded in the center of the core 2 shown in FIG. 1, a burnable poison aggregate as shown in FIG.
It has to be loaded with 19. FIG. 1 shows an example in which the present invention is applied to a reflector-controlled sodium-cooled small fast breeder reactor having an equivalent diameter of the core 2 of about 80 cm and an effective length of the core 2 of about 200 cm.

【0040】炉心2の外側の中性子反射体5はカバーガ
ス空間を含むグラファイトまたはステンレス鋼(SUS )
等の構造材で構成され、長さ約200cm ,厚さ15cmのもの
が使用されている。中性子反射体5の外壁は隔壁4が、
その外側は中性子しゃへい体7が、さらにその外側は原
子炉容器1となっている。炉心2の中央には例えば水素
化ジルコニウムとガドリニウムを混合した物質を含んだ
可燃性毒物集合体19が装荷されている。
The neutron reflector 5 outside the reactor core 2 is made of graphite or stainless steel (SUS) including a cover gas space.
It has a length of about 200 cm and a thickness of 15 cm. The partition wall 4 is formed on the outer wall of the neutron reflector 5,
The neutron shielding body 7 is on the outside and the reactor vessel 1 is on the outside. At the center of the reactor core 2 is loaded a burnable poisonous aggregate 19 containing, for example, a mixture of zirconium hydride and gadolinium.

【0041】可燃性毒物集合体19は図2に示したように
六角筒状のラッパ管20内に、中性子減速材と中性子吸収
材との混合物質22を被覆管21内に充填して構成した中性
子吸収体棒23を7本結束して組み込んでなるものであ
る。被覆管21はステンレス鋼等の構造材で、中性子減速
材と中性子吸収材との混合物質22は例えば水素化ジルコ
ニウムとガドリニウムの混合物である。
As shown in FIG. 2, the burnable poisonous substance aggregate 19 is formed by filling a mixed substance 22 of a neutron moderator and a neutron absorbing material into a cladding tube 21 in a hexagonal tubular wrapper tube 20. The neutron absorber rods 23 are bundled and assembled. The cladding tube 21 is a structural material such as stainless steel, and the mixed substance 22 of the neutron moderator and the neutron absorbing material is, for example, a mixture of zirconium hydride and gadolinium.

【0042】つぎに本実施の形態の作用を説明する。図
3に図1の炉心の最終状態の炉心状態に対する燃焼中の
各種反応度変化例を示す。図3では燃料集合体16の燃焼
反応度の変化aと、中性子反射体5の価値の変化bと、
可燃性毒物集合体19の反応度変化cを示す。30年間の燃
焼による燃料集合体16の余剰の反応度変化が大きく、中
性子反射体5の価値の変化だけでは初期の燃料の余剰の
反応度をキャンセルすることができない。中性子反射体
5の制御だけでは図3の燃焼反応度を持った30年間の長
寿命炉心を構成すると初期炉心の中性子増倍が大きすぎ
て運転できない。つまり、初期炉心構成では大きく臨界
を超過してしまう。
Next, the operation of the present embodiment will be described. FIG. 3 shows examples of various reactivity changes during combustion with respect to the final core state of the core of FIG. In FIG. 3, a change a in the combustion reactivity of the fuel assembly 16 and a change b in the value of the neutron reflector 5;
9 shows a change in reactivity c of the burnable poisonous substance aggregate 19. The excess reactivity change of the fuel assembly 16 due to the combustion for 30 years is large, and the initial excess fuel reactivity cannot be canceled only by the change in the value of the neutron reflector 5. If a long-life core having the combustion reactivity shown in FIG. 3 and having a long life of 30 years is constructed only by controlling the neutron reflector 5, the neutron multiplication of the initial core is too large to operate. That is, the initial core configuration greatly exceeds the criticality.

【0043】これに中性子を吸収する可燃性毒物、例え
ばガドリニウムを炉内に挿入しておけば、燃料集合体16
の初期の余剰な反応度をキャンセルし、さらに燃焼によ
ってガドリニウムは減少するため、燃料の燃焼反応度の
減少とともに、可燃性毒物の反応度も減少し、中性子反
射体5の制御による中性子反射体5の反応度変化と可燃
性毒物の反応度と合わせて長寿命の燃焼制御が可能とな
る。
If a burnable poison that absorbs neutrons, such as gadolinium, is inserted into the furnace, the fuel assembly 16
Gadolinium is reduced by the combustion, and the reactivity of the burnable poison is also reduced along with the decrease in the fuel combustion reactivity, and the neutron reflector 5 is controlled by the neutron reflector 5. Along with the change in the reactivity of the fuel and the reactivity of the burnable poison, it is possible to control the combustion for a long life.

【0044】また、本炉心のような高速増殖炉では、中
性子吸収材であるガドリニウムとともに中性子減速材で
ある水素化ジルコニウムを混合した物質を炉内に配置す
れば、中性子を減速させて効果的に中性子の吸収が可能
となる。
In a fast breeder reactor such as the present core, if a substance in which gadolinium as a neutron absorber and zirconium hydride as a neutron moderator are mixed in the reactor, neutrons can be decelerated effectively. Neutron absorption becomes possible.

【0045】つぎに図4により本発明に係る高速増殖炉
の第2の実施の形態を説明する。図4は本実施の形態の
要部を示し、図1(a)と対応しており、図4中、図1
(a)と同一部分には同一符号を付して重複する部分の
説明は省略する。本実施の形態が第1の実施の形態と異
なる点は、中性子反射体5の上部に中性子減速材と中性
子吸収材を混合した物質を内蔵した中性子減速材付き中
性子吸収体24を配置したことにある。
Next, a second embodiment of the fast breeder reactor according to the present invention will be described with reference to FIG. FIG. 4 shows a main part of this embodiment and corresponds to FIG. 1A.
The same parts as those in (a) are denoted by the same reference numerals, and the description of the overlapping parts will be omitted. This embodiment is different from the first embodiment in that a neutron absorber with a neutron moderator 24 containing a mixed material of a neutron moderator and a neutron absorber is disposed above the neutron reflector 5. is there.

【0046】従来、中性子反射体5の上部は中性子反射
体5の価値を上げるためキャビティ(空所)になってい
るが、本実施の形態ではこのキャビティに中性子減速材
付き中性子吸収体24を装荷する。これにより、第1の実
施の形態の作用効果のほかに、中性子しゃへい機能が付
与されるとともに、上部構造物が簡素化できる効果があ
る。
Conventionally, the upper portion of the neutron reflector 5 has a cavity (vacant space) in order to increase the value of the neutron reflector 5, but in the present embodiment, the neutron absorber 24 with a neutron moderator is loaded in this cavity. I do. Thus, in addition to the functions and effects of the first embodiment, a neutron shielding function is provided and the upper structure can be simplified.

【0047】つぎに本発明に係る高速増殖炉の第3の実
施の形態を説明する。本実施の形態は第1の実施の形態
において、中性子減速材と中性子吸収材を混合した物質
を炉心2内に装荷する場合、中性子減速材である可燃性
毒物の径方向分布を内側ほど濃くすることにある。
Next, a third embodiment of the fast breeder reactor according to the present invention will be described. In the present embodiment, in the first embodiment, when a substance in which a neutron moderator and a neutron absorber are mixed is loaded into the reactor core 2, the radial distribution of the burnable poison as the neutron moderator is made deeper toward the inside. It is in.

【0048】本実施の形態による作用効果は、第1の実
施の形態とほぼ同様であるが、その他、初期の中性子の
吸収効果の低下幅を下げ、反濃度の低下を直線的にでき
る。したがって、本実施の形態によれば、反応度が直線
的であるため、燃焼による余剰反応度の変化が見かけ上
直線的になるため、中性子反射体5の駆動による燃焼制
御も直線的にでき、中性子反射体5の駆動をほぼ一定速
度で行うことができ、燃焼制御が容易となる。
The operation and effect of the present embodiment are almost the same as those of the first embodiment, but in addition, the decrease of the initial neutron absorption effect can be reduced, and the reduction of the anti-concentration can be made linear. Therefore, according to the present embodiment, since the reactivity is linear, the change in excess reactivity due to combustion becomes apparently linear, so that the combustion control by driving the neutron reflector 5 can also be performed linearly. The neutron reflector 5 can be driven at a substantially constant speed, and combustion control is facilitated.

【0049】つぎに本発明に係る高速増殖炉の第4の実
施の形態を説明する。本実施の形態は第1の実施の形態
において、中性子減速材と中性子吸収材を混合した物質
を炉心2内に装荷する場合、中性子減速材として黒鉛を
使用したことにある。本実施の形態によれば、第1の実
施の形態とほぼ同様の作用効果を有するが、その他高温
での健全性に優れ、設計の裕度が増加し、冷却材出口温
度を高温化した場合にも対応できる。
Next, a fourth embodiment of the fast breeder reactor according to the present invention will be described. This embodiment is different from the first embodiment in that graphite is used as a neutron moderator when a substance obtained by mixing a neutron moderator and a neutron absorber is loaded into the core 2. According to the present embodiment, it has substantially the same operation and effect as the first embodiment, but also has excellent soundness at high temperatures, increases the design margin, and increases the coolant outlet temperature. Can also respond.

【0050】つぎに本発明に係る高速増殖炉の第5の実
施の形態を説明する。本実施の形態は、第1の実施の形
態において、図2に示したように被覆管21内に中性子減
速材と中性子吸収材との混合物質22を振動充填法により
充填して中性子吸収体棒23を形成したことにある。
Next, a description will be given of a fifth embodiment of the fast breeder reactor according to the present invention. This embodiment is different from the first embodiment in that a mixed substance 22 of a neutron moderator and a neutron absorbing material is filled into a cladding tube 21 by a vibration filling method as shown in FIG. 23.

【0051】すなわち、中性子減速材と中性子吸収材と
の混合物質22として例えば水素化ジルコニウムとガドリ
ニウムを混合する場合に、両者を所定量秤量後、顆粒状
に成形し、これらの顆粒を下端が封止された被覆管21に
加振機により振動を与えながら上端開口から徐々に投入
して充填する。振動充填後、被覆管21の上端開口に上端
栓を取り付け封止して中性子吸収体棒23を完成させる。
被覆管21は加振機の加振台に取り付けられて所定の振動
が付与される。
That is, when, for example, zirconium hydride and gadolinium are mixed as the mixed substance 22 of the neutron moderator and the neutron absorbing material, both are weighed to a predetermined amount and then formed into granules, and these granules are sealed at the lower end. The stopped covering tube 21 is gradually charged from the upper end opening while being vibrated by a vibrator to be filled. After the vibration filling, a neutron absorber rod 23 is completed by attaching an upper end plug to the upper end opening of the cladding tube 21 and sealing it.
The cladding tube 21 is attached to a vibrating table of a vibrator to apply a predetermined vibration.

【0052】本実施の形態によれば、中性子減速材含有
の中性子吸収体棒23の形成工程が簡素化され、形成時の
遠隔操作が可能となり、中性子減速材または中性子吸収
材が放射性物質である場合などの危険物であっても、中
性子吸収体棒23の形成が容易になる。
According to the present embodiment, the process of forming the neutron absorber rod 23 containing the neutron moderator is simplified, remote control can be performed during the formation, and the neutron moderator or the neutron absorber is a radioactive substance. The neutron absorber rod 23 can be easily formed even with dangerous substances such as cases.

【0053】つぎに本発明に係る高速増殖炉の第6の実
施の形態を説明する。本実施の形態は第1の実施の形態
において、図2に示す被覆管21またはラッパ管20の内面
に水素の透過を防止する内張り、例えばクロムのコーテ
ィング層を設けたことにある。このクロムのコーティン
グ層は中性子減速材と熱中性子吸収材を混合した物質、
例えば水素化ジルコニウムとガドリニウムを混合した物
質と接触している。
Next, a description will be given of a sixth embodiment of the fast breeder reactor according to the present invention. This embodiment is different from the first embodiment in that a lining, for example, a chromium coating layer for preventing hydrogen permeation is provided on the inner surface of the cladding tube 21 or the wrapper tube 20 shown in FIG. This chromium coating layer is a mixture of neutron moderator and thermal neutron absorber,
For example, it is in contact with a mixture of zirconium hydride and gadolinium.

【0054】本実施の形態によれば、水素の透過を防止
する内張りを設けた可燃性毒物集合体19を図1(a),
(b)に示すように炉心2の中央部に装荷することによ
り、炉心の燃焼によって生成される水素の可燃性毒物集
合体19外への漏洩を防止できる。その他の作用効果は第
1の実施の形態と同様である。
According to the present embodiment, the burnable poisonous substance aggregate 19 provided with a lining for preventing the permeation of hydrogen is provided by the method shown in FIGS.
By loading the core 2 at the center as shown in (b), it is possible to prevent hydrogen generated by combustion of the core 2 from leaking out of the burnable poisonous aggregates 19. Other functions and effects are the same as those of the first embodiment.

【0055】つぎに本発明に係る高速増殖炉の第7の実
施の形態を説明する。本実施の形態は第1の実施の形態
において、中性子減速材と中性子吸収材を混合した物
質、例えば水素化ジルコニウムと中性子吸収材として核
分裂生成物(FP)を混合した物質を炉心2内に装荷して
中性子吸収能力を高めたことにある。
Next, a description will be given of a seventh embodiment of the fast breeder reactor according to the present invention. This embodiment is different from the first embodiment in that a material obtained by mixing a neutron moderator and a neutron absorber, for example, a material obtained by mixing zirconium hydride and fission products (FP) as a neutron absorber is loaded into the core 2. Neutron absorption capacity.

【0056】本実施の形態によれば、中性子吸収材に核
分裂生成物(FP)を使用することによって、他の原子炉
で生成された放射性物質を有効利用し、核分裂生成物の
削減に寄与する。その他の作用効果は第1の実施の形態
と同様である。
According to the present embodiment, by using fission products (FP) as the neutron absorbing material, radioactive materials generated in other nuclear reactors can be effectively used, thereby contributing to the reduction of fission products. . Other functions and effects are the same as those of the first embodiment.

【0057】つぎに本発明に係る高速増殖炉の第8の実
施の形態を説明する。本実施の形態は第1の実施の形態
において、冷却材として液体金属を使用した高速増殖炉
において、中性子減速材と中性子吸収材を混合した物質
を炉心2内に装荷するにあたり、中性子減速材である可
燃性毒物の径方向分布を内側ほど濃くすることにより、
初期の中性子の吸収効果の低下幅を下げ、反応度を直線
的にするとともに、中性子減速材付き中性子吸収体の燃
焼による吸収度の低下を直線的にすることにある。
Next, an eighth embodiment of the fast breeder reactor according to the present invention will be described. In the first embodiment, in the fast breeder reactor using liquid metal as a coolant in the first embodiment, when a material obtained by mixing a neutron moderator and a neutron absorber is loaded into the reactor core 2, the neutron moderator is used. By making the radial distribution of a burnable poison deeper inward,
An object of the present invention is to reduce the decrease in the initial neutron absorption effect and make the reactivity linear, and to make the absorption decrease due to the burning of the neutron absorber with a neutron moderator linear.

【0058】本実施の形態によれば、余剰反応度の低下
を見かけ上直線的にして、必要となる中性子反射体の駆
動量の制御を容易にし、炉心の燃焼制御を容易にするこ
とができる。
According to the present embodiment, it is possible to make the decrease in the excess reactivity linear in appearance, to facilitate the control of the required driving amount of the neutron reflector, and to facilitate the combustion control of the core. .

【0059】つぎに本発明に係る高速増殖炉の第9の実
施の形態を説明する。本実施の形態は第1の実施の形態
において、中性子減速材と熱中性子吸収材を混合した物
質、例えば水素化ジルコニウムとガドリニウムを混合し
た物質を炉心中央部近傍の燃料集合体16に設けて、中性
子吸収能力を高めたことにある。
Next, a ninth embodiment of the fast breeder reactor according to the present invention will be described. In the present embodiment, in the first embodiment, a material obtained by mixing a neutron moderator and a thermal neutron absorber, for example, a material obtained by mixing zirconium hydride and gadolinium is provided in the fuel assembly 16 near the center of the core, The neutron absorption capacity has been enhanced.

【0060】本実施の形態によれば、燃料集合体16内に
中性子減速材と熱中性子吸収材を混合した物質を設ける
ことにより、炉心の中央部に可燃性毒物集合体19を装荷
する必要がなく、中央部に装荷する中性子吸収体棒また
は図6に示した中性子吸収用チャンネル17の設計が容易
となる。
According to the present embodiment, by providing a substance in which a neutron moderator and a thermal neutron absorber are mixed in the fuel assembly 16, it is necessary to load the burnable poison assembly 19 in the center of the core. In addition, the design of the neutron absorber rod loaded in the center or the neutron absorption channel 17 shown in FIG. 6 is facilitated.

【0061】つぎに本発明に係る高速増殖炉の第10の実
施の形態を説明する。本実施の形態は上述した各々の高
速増殖炉において、中性子減速材と中性子吸収材を混合
した物質、例えば水素化ジルコニウムとガドリニウムを
混合した物質を炉心中央部の可燃性毒物集合体に設け、
燃焼末期のボイド反応度の正側への移行を緩和すること
にある。本実施の形態に係る反射体制御方式の高速増殖
炉の場合、機能は第1の実施の形態とほぼ同様である。
Next, a tenth embodiment of the fast breeder reactor according to the present invention will be described. In this embodiment, in each of the fast breeder reactors described above, a substance in which a neutron moderator and a neutron absorber are mixed, for example, a substance in which zirconium hydride and gadolinium are mixed is provided in the burnable poison aggregate in the center of the core,
It is to alleviate the transition of the void reactivity toward the positive side at the end of combustion. In the case of the reflector-controlled fast breeder reactor according to the present embodiment, the function is almost the same as in the first embodiment.

【0062】一般に高速増殖炉では、炉心が燃焼するに
従いボイド反応度が正側に上昇する。これは燃焼末期の
方がボイドが発生した場合のスペクトル硬化により正反
応度が多く入ることを意味する。
In general, in a fast breeder reactor, the void reactivity increases to the positive side as the core burns. This means that in the last stage of combustion, the degree of correct reaction is increased due to spectral hardening when voids are generated.

【0063】しかし、本実施の形態のように中性子減速
材付き中性子吸収体棒を設けた高速増殖炉においては、
燃焼末期に中性子エネルギーの小さな領域での吸収効果
が減少するため、通常の高速増殖炉の炉心より燃焼末期
でも中性子エネルギーの低い領域での核分裂の寄与が大
きい。
However, in a fast breeder reactor provided with a neutron absorber rod with a neutron moderator as in this embodiment,
Since the absorption effect in the region where the neutron energy is small in the last stage of combustion decreases, fission contribution in the region where the neutron energy is low even in the last stage of the combustion is larger than that in the core of a normal fast breeder reactor.

【0064】このため、燃焼末期でも冷却材ボイド生成
によるスペクトルの硬化に対して正反応度への移行が大
きくならない。したがって、燃焼末期にボイド反応度が
正側に移行し難くなり、安全上優れた特性となる。
For this reason, even at the end of combustion, the shift to the positive reactivity does not become large with respect to the hardening of the spectrum due to the generation of coolant voids. Therefore, it is difficult for the void reactivity to shift to the positive side at the end of combustion, and characteristics excellent in safety are obtained.

【0065】つぎに本発明に係る高速増殖炉の第11の実
施の形態を説明する。本実施の形態は第1の実施の形態
において、液体金属冷却材として使用した液体ナトリウ
ムの代りに鉛または鉛−ビスマス合金を使用したことに
ある。その他の構成は第1の実施の形態と同様である。
Next, an eleventh embodiment of the fast breeder reactor according to the present invention will be described. This embodiment is different from the first embodiment in that lead or a lead-bismuth alloy is used instead of liquid sodium used as a liquid metal coolant. Other configurations are the same as those of the first embodiment.

【0066】本実施の形態によれば、高速中性子を減速
し、中性子吸収材に吸収させて中性子吸収能力を高める
ことができるとともに、中性子増殖性が高く、炉心の寿
命を延ばすことができる。
According to this embodiment, fast neutrons can be decelerated and absorbed by a neutron absorbing material to increase the neutron absorbing ability, and the neutron multiplying property is high and the life of the reactor core can be extended.

【0067】[0067]

【発明の効果】本発明によれば、炉心の寿命を延ばすた
めに必要であった燃料長を、延ばす必要がなく、中性子
吸収能力を高めることによって初期の余剰反応度を大き
くするだけで、炉心の寿命を延ばすことができる。
According to the present invention, it is not necessary to lengthen the fuel length required to extend the life of the core, but only by increasing the initial excess reactivity by increasing the neutron absorption capacity, the core length can be increased. Life can be extended.

【図面の簡単な説明】[Brief description of the drawings]

【図1】(a)は本発明に係る高速増殖炉の第1の実施
の形態を示す横断面図、(b)は(a)における概略的
縦断面図。
FIG. 1A is a cross-sectional view showing a fast breeder reactor according to a first embodiment of the present invention, and FIG. 1B is a schematic vertical cross-sectional view in FIG.

【図2】図1(a),(b)における可燃性毒物集合体
を示す横断面図。
FIG. 2 is a cross-sectional view showing the burnable poison aggregate in FIGS. 1 (a) and 1 (b).

【図3】本発明に係る高速増殖炉の作用を説明するため
の特性図。
FIG. 3 is a characteristic diagram for explaining the operation of the fast breeder reactor according to the present invention.

【図4】本発明に係る高速増殖炉の第2の実施の形態の
要部を示す縦断面図。
FIG. 4 is a longitudinal sectional view showing a main part of a second embodiment of the fast breeder reactor according to the present invention.

【図5】従来の反射体制御方式の高速増殖炉を概略的に
示す縦断面図。
FIG. 5 is a longitudinal sectional view schematically showing a conventional reflector-controlled fast breeder reactor.

【図6】図5のA−A矢視方向断面を拡大して示す横断
面図。
FIG. 6 is an enlarged cross-sectional view showing a cross section taken along line AA of FIG. 5;

【符号の説明】[Explanation of symbols]

1…原子炉容器、2…炉心、3…炉心バレル、4…隔
壁、5…中性子反射体、6…中性子反射体駆動装置、7
…中性子しゃへい体、8…支持構造物、9…下部プレナ
ム、10…中間熱交換器、11…電磁ポンプ、12…二次冷却
材配管、13…しゃへいプラグ、14…冷却材、15…上部プ
レナム、16…燃料集合体、17…中性子吸収用チャンネ
ル、18…ガードベッセル、19…可燃性毒物集合体、20…
ラッパ管、21…被覆管、22…中性子減速材と中性子吸収
材との混合物質、23…中性子吸収体棒、24…中性子減速
材付き中性子吸収体、a…燃料集合体の反応度の変化、
b…反射体の変化、c…可燃性毒物集合体の変化。
DESCRIPTION OF SYMBOLS 1 ... Reactor vessel, 2 ... Core, 3 ... Core barrel, 4 ... Partition wall, 5 ... Neutron reflector, 6 ... Neutron reflector driver, 7
... neutron shield, 8 ... support structure, 9 ... lower plenum, 10 ... intermediate heat exchanger, 11 ... electromagnetic pump, 12 ... secondary coolant piping, 13 ... shield plug, 14 ... coolant, 15 ... upper plenum , 16: fuel assembly, 17: neutron absorption channel, 18: guard vessel, 19: burnable poison assembly, 20 ...
Wrapper tube, 21: cladding tube, 22: mixed substance of neutron moderator and neutron absorber, 23: neutron absorber rod, 24: neutron absorber with neutron moderator, a: change in reactivity of fuel assembly,
b: change in reflector, c: change in burnable poison aggregate.

Claims (12)

【特許請求の範囲】[Claims] 【請求項1】 原子炉容器内の液体金属冷却材に浸され
た炉心の外側に中性子反射体を配置し、この中性子反射
体を上下方向に移動させて前記炉心からの中性子の漏洩
を調整することによって前記炉心の反応度を制御する反
射体制御方式の高速増殖炉において、前記炉心内に中性
子減速材と中性子吸収材を混合した物質を装荷してなる
ことを特徴とする反射体制御方式の高速増殖炉。
1. A neutron reflector is disposed outside a reactor core immersed in a liquid metal coolant in a reactor vessel, and the neutron reflector is moved up and down to adjust neutron leakage from the reactor core. In the fast breeder reactor of the reflector control system that controls the reactivity of the core by the above, the reflector control system characterized in that a material obtained by mixing a neutron moderator and a neutron absorbing material is loaded in the core Fast breeder reactor.
【請求項2】 原子炉容器内の液体金属冷却材に浸され
た炉心の外側に中性子反射体を配置し、この中性子反射
体を上下方向に移動させて前記炉心からの中性子の漏洩
を調整することによって前記炉心の反応度を制御する反
射体制御方式の高速増殖炉において、中性子減速材と中
性子吸収材を混合した物質を含む中性子吸収体棒とし、
この中性子吸収体棒を複数本ラッパ管内に組み込んで可
燃性毒物集合体とし、この可燃性毒物集合体を前記炉心
の中央部に装荷してなることを特徴とする反射体制御方
式の高速増殖炉。
2. A neutron reflector is disposed outside a reactor core immersed in a liquid metal coolant in a reactor vessel, and the neutron reflector is moved up and down to adjust neutron leakage from the reactor core. In the fast breeder reactor of the reflector control system to control the reactivity of the core by doing, a neutron absorber rod containing a substance mixed neutron moderator and neutron absorber,
A reflector controlled fast breeder reactor characterized in that a plurality of the neutron absorber rods are incorporated into a wrapper tube to form a burnable poison aggregate, and the burnable poison aggregate is loaded in a central portion of the core. .
【請求項3】 原子炉容器内の液体金属冷却材に浸され
た炉心の外側に中性子反射体を配置し、この中性子反射
体を上下方向に移動させて前記炉心からの中性子の漏洩
を調整することによって前記炉心の反応度を制御する反
射体制御方式の高速増殖炉において、中性子減速材と中
性子吸収材を混合した物質を前記中性子反射体の上部キ
ャビティに装荷してなることを特徴とする反射体制御方
式の高速増殖炉。
3. A neutron reflector is disposed outside a reactor core immersed in liquid metal coolant in a reactor vessel, and the neutron reflector is moved up and down to adjust neutron leakage from the reactor core. In a fast breeder reactor of a reflector control type for controlling the reactivity of the core by mixing, a material obtained by mixing a neutron moderator and a neutron absorber is loaded in an upper cavity of the neutron reflector. Body controlled fast breeder reactor.
【請求項4】 前記中性子減速材と中性子吸収材を混合
した物質を前記炉心内に装荷するにあたり、前記中性子
吸収棒の径方向分布を内側ほど濃くしてなることを特徴
とする請求項1記載の反射体制御方式の高速増殖炉。
4. The method according to claim 1, wherein a radial distribution of the neutron absorbing rods is increased toward the inside when loading the mixed material of the neutron moderator and the neutron absorbing material into the core. Fast breeder reactor with reflector control system.
【請求項5】 前記中性子反射体の上部に装荷した中性
子減速材と中性子吸収材を混合した物質は黒鉛とガドリ
ニウムとを混合した物質からなることを特徴とする請求
項3記載の反射体制御方式の高速増殖炉。
5. The reflector control method according to claim 3, wherein the substance in which the neutron moderator and the neutron absorber loaded on the neutron reflector are mixed is a substance in which graphite and gadolinium are mixed. Fast breeder reactor.
【請求項6】 前記中性子減速材と中性子吸収材を混合
した物質を被覆管内に充填して中性子吸収体棒を形成す
るにあたり、前記中性子減速材と中性子吸収材を顆粒状
に成形し、この顆粒状物を前記被覆管内に振動充填法に
より充填してなることを特徴とする請求項2記載の反射
体制御方式の高速増殖炉。
6. A neutron moderator and a neutron absorber are formed into granules by filling a clad tube with a substance obtained by mixing the neutron moderator and the neutron absorber, to form a neutron absorber rod. 3. A fast breeder reactor according to claim 2, wherein said cladding is filled in said cladding tube by a vibration filling method.
【請求項7】 前記中性子減速材と中性子吸収材を混合
した物質を収納する被覆管またはラッパ管の内面に水素
の透過を防止する内張りを設けてなることを特徴とする
請求項2記載の反射体制御方式の高速増殖炉。
7. The reflection according to claim 2, wherein a cladding for preventing the permeation of hydrogen is provided on an inner surface of a cladding tube or a wrapper tube for containing a substance obtained by mixing the neutron moderator and the neutron absorbing material. Body controlled fast breeder reactor.
【請求項8】 原子炉容器内の液体金属冷却材に浸され
た炉心の外側に中性子反射体を配置し、この中性子反射
体を上下方向に移動させて前記炉心からの中性子の漏洩
を調整することによって前記炉心の反応度を制御する反
射体制御方式の高速増殖炉において、前記炉心内に中性
子減速材と中性子吸収材を混合した物質と、核分裂生成
物を混合してなる減速材含有中性子吸収体を配置したこ
とを特徴とする反射体制御方式の高速増殖炉。
8. A neutron reflector is disposed outside a reactor core immersed in liquid metal coolant in a reactor vessel, and the neutron reflector is moved up and down to adjust neutron leakage from the reactor core. In a reflector-controlled fast breeder reactor that controls the reactivity of the reactor core, a neutron absorber containing a neutron moderator and a neutron absorber mixed in the core, and a moderator-containing neutron absorber formed by mixing fission products A reflector-controlled fast breeder reactor with a body arranged.
【請求項9】 前記減速材含有中性子吸収体を前記炉心
内に装荷するにあたり、前記中性子吸収材の可燃性毒物
の径方向分布を内側ほど濃くしてなることを特徴とする
請求項8記載の反射体制御方式の高速増殖炉。
9. The method according to claim 8, wherein, when the moderator-containing neutron absorber is loaded into the core, the radial distribution of the burnable poison of the neutron absorber is made deeper toward the inside. Fast breeder reactor with reflector control.
【請求項10】 前記減速材含有中性子吸収体を前記炉
心内中央部近傍の燃料集合体に設けてなることを特徴と
する請求項1記載の反射体制御方式の高速増殖炉。
10. The reflector-controlled fast breeder reactor according to claim 1, wherein said moderator-containing neutron absorber is provided in a fuel assembly near a central portion in said reactor core.
【請求項11】 前記減速材含有中性子吸収体を前記炉
心中央に装荷する可燃性毒物集合体に設けてなることを
特徴とする請求項8記載の反射体制御方式の高速増殖
炉。
11. The reflector-controlled fast breeder reactor according to claim 8, wherein said moderator-containing neutron absorber is provided in a burnable poisonous substance assembly loaded in the center of said reactor core.
【請求項12】 前記液体金属冷却材は鉛または鉛−ビ
スマス合金からなることを特徴とする請求項1ないし11
記載の反射体制御方式の高速増殖炉。
12. The liquid metal coolant according to claim 1, wherein the coolant is made of lead or a lead-bismuth alloy.
The fast breeder reactor of the reflector control system described in the above.
JP2000049031A 1999-12-28 2000-02-25 Reflector-controlled fast breeder reactor Expired - Fee Related JP4101424B2 (en)

Priority Applications (11)

Application Number Priority Date Filing Date Title
JP2000049031A JP4101424B2 (en) 2000-02-25 2000-02-25 Reflector-controlled fast breeder reactor
US09/749,547 US7139352B2 (en) 1999-12-28 2000-12-28 Reactivity control rod for core
US11/348,333 US20060126775A1 (en) 1999-12-28 2006-02-07 Reactivity control rod for core, core of nuclear reactor, nuclear reactor and nuclear power plant
US11/377,178 US20060210010A1 (en) 1999-12-28 2006-03-17 Reactivity control rod for core, core of nuclear reactor, nuclear reactor and nuclear power plant
US12/128,524 US20090010374A1 (en) 1999-12-28 2008-05-28 Reactivity control rod for core, core of nuclear reactor, nuclear reactor and nuclear power plant
US12/270,680 US20090080586A1 (en) 1999-12-28 2008-11-13 Reactivity control rod for core, core of nuclear reactor, nuclear reactor and nuclear power plant
US12/625,173 US20100067641A1 (en) 1999-12-28 2009-11-24 Reactivity control rod for core, core of nuclear reactor, nuclear reactor and nuclear power plant
US12/764,163 US20100322369A1 (en) 1999-12-28 2010-04-21 Liquid cooled nuclear reactor with annular steam generator
US13/006,260 US20110194664A1 (en) 1999-12-28 2011-01-13 Reactivity control rod for core, core of nuclear reactor, nuclear reactor and nuclear power plant
US13/014,206 US8331523B2 (en) 1999-12-28 2011-01-26 Liquid cooled nuclear reactor with annular steam generator
US13/361,543 US8711997B2 (en) 1999-12-28 2012-01-30 Reactor core of liquid metal cooled reactor

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Application Number Priority Date Filing Date Title
JP2000049031A JP4101424B2 (en) 2000-02-25 2000-02-25 Reflector-controlled fast breeder reactor

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JP4101424B2 JP4101424B2 (en) 2008-06-18

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Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2010054261A (en) * 2008-08-27 2010-03-11 Japan Atomic Energy Agency Fast reactor and fuel assembly
US7773716B2 (en) 2004-02-19 2010-08-10 Kabushiki Kaisha Toshiba Fast reactor having reflector control system and neutron reflector thereof
JP2011095017A (en) * 2009-10-28 2011-05-12 Toshiba Corp Reflector control reactor
CN113241201A (en) * 2021-04-29 2021-08-10 西南科技大学 Non-uniform control rod with non-uniform reflecting layer

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US7773716B2 (en) 2004-02-19 2010-08-10 Kabushiki Kaisha Toshiba Fast reactor having reflector control system and neutron reflector thereof
US7864913B2 (en) 2004-02-19 2011-01-04 Kabushiki Kaisha Toshiba Fast reactor having reflector control system and neutron reflector thereof
US8126105B2 (en) 2004-02-19 2012-02-28 Kabushiki Kaisha Toshiba Fast reactor having reflector control system and neutron reflector thereof
JP2010054261A (en) * 2008-08-27 2010-03-11 Japan Atomic Energy Agency Fast reactor and fuel assembly
JP2011095017A (en) * 2009-10-28 2011-05-12 Toshiba Corp Reflector control reactor
CN113241201A (en) * 2021-04-29 2021-08-10 西南科技大学 Non-uniform control rod with non-uniform reflecting layer
CN113241201B (en) * 2021-04-29 2022-03-04 西南科技大学 Non-uniform control rod with non-uniform reflecting layer

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