JPS58637B2 - Nuclear reactor core using fuel assembly with molten fuel retainer - Google Patents

Nuclear reactor core using fuel assembly with molten fuel retainer

Info

Publication number
JPS58637B2
JPS58637B2 JP52126429A JP12642977A JPS58637B2 JP S58637 B2 JPS58637 B2 JP S58637B2 JP 52126429 A JP52126429 A JP 52126429A JP 12642977 A JP12642977 A JP 12642977A JP S58637 B2 JPS58637 B2 JP S58637B2
Authority
JP
Japan
Prior art keywords
fuel
molten
molten fuel
nuclear reactor
reactor core
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.)
Expired
Application number
JP52126429A
Other languages
Japanese (ja)
Other versions
JPS5459596A (en
Inventor
斎藤蔚
川島協
柳沢務
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.)
Doryokuro Kakunenryo Kaihatsu Jigyodan
Original Assignee
Doryokuro Kakunenryo Kaihatsu Jigyodan
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
Application filed by Doryokuro Kakunenryo Kaihatsu Jigyodan filed Critical Doryokuro Kakunenryo Kaihatsu Jigyodan
Priority to JP52126429A priority Critical patent/JPS58637B2/en
Publication of JPS5459596A publication Critical patent/JPS5459596A/en
Publication of JPS58637B2 publication Critical patent/JPS58637B2/en
Expired legal-status Critical Current

Links

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

Landscapes

  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は、原子炉において何等かの事故が生じ、燃料の
破損が生じた場合に、噴出する溶融燃料の一部もしくは
大部分をほぼ一定の領域内に保持することができるよう
な燃料集合体を使用した原子炉炉心に関するものである
DETAILED DESCRIPTION OF THE INVENTION The present invention is capable of retaining part or most of the molten fuel that spouts out within a substantially fixed area when some kind of accident occurs in a nuclear reactor and fuel is damaged. This relates to a nuclear reactor core using a fuel assembly that allows for

原子炉における事故の種類を初期事象で大別すれば、反
応度挿入事故、冷却材事故など炉心全体の初期事象から
始まるものと、燃料集合体中の冷却材流路閉塞事故など
局部的なものに分類できる。
The types of accidents in nuclear reactors can be roughly divided into initial events: those that begin with initial events in the entire reactor core, such as reactivity insertion accidents and coolant accidents, and those that are localized, such as coolant flow blockage accidents in fuel assemblies. It can be classified into

いずれにせよ出力は上昇し、燃料温度が上昇して燃料物
質が溶融したときにはその温度は2700〜2800℃
程度となり、ステンレス鋼、バナジウム、ニッケル等の
合金から構成される被覆材では、燃料破損が生じ溶融燃
料が冷却材中に放出されてしまう。
In any case, the output will increase, and when the fuel temperature increases and the fuel material melts, the temperature will be 2700-2800℃
With cladding materials made of alloys such as stainless steel, vanadium, and nickel, fuel failure occurs and molten fuel is released into the coolant.

燃料破損の典型的なケースは、燃料の熱膨張および燃料
の溶融に伴う体積膨張と溶融燃料からの核分裂生成ガス
放出による内圧上昇が被覆管に応力を与え破損させる場
合であると考えられる。
A typical case of fuel failure is considered to be when internal pressure increases due to thermal expansion of the fuel, volumetric expansion due to fuel melting, and release of fission product gas from the molten fuel apply stress to the cladding tube, causing it to break.

つまり、反応度事故時の出力上昇などにより燃料が加熱
され溶融するに従い体積の増加を伴いながら固体燃料内
にトラップされていた核分裂生成ガスが放出され、急速
に内圧が上昇し被覆管がひずみ、そのひずみ量が被覆管
の破損限界を越えたとき燃料破損が生じ、核分裂生成ガ
スと溶融燃料との混合物が噴出するというものである。
In other words, as the fuel heats up and melts due to an increase in output during a reactivity accident, the fission product gas trapped within the solid fuel is released while increasing its volume, causing a rapid increase in internal pressure and straining the cladding. When the amount of strain exceeds the failure limit of the cladding tube, fuel failure occurs and a mixture of fission product gas and molten fuel is ejected.

従つて燃料破損が生じ溶融燃料が噴出すると、噴出物の
大部分は落下し、炉心構造物や原子炉容器底部に広く堆
積することになり、その除去は極めて困難なものとなる
Therefore, when a fuel failure occurs and molten fuel is ejected, most of the ejected material falls and is widely deposited on the core structure and the bottom of the reactor vessel, making it extremely difficult to remove.

また、あまり多量の溶融燃料が1箇所に集積保持される
と、臨界形状、即ち核分裂性物質を含む系が臨界に達す
るに必要な、寸法形状、となり核分裂連鎖反応が維持さ
れる虞れがある。
Furthermore, if too much molten fuel is accumulated and retained in one place, there is a risk that the fission chain reaction will be maintained due to the critical shape, that is, the size and shape necessary for the system containing fissile material to reach criticality. .

本発明の目的は、かかる問題を解決すべくなされたもの
であって、原子炉において何等かの事故が生じ、燃料被
覆管の破損が生じた場合に、溶融燃料の一部もしくは大
部分を保持することができるような溶融燃料の保持機能
を有し、かつ溶融燃料が臨界形状になることを回避し、
しかも中性子遮蔽機能をも果たすことのできる原子炉炉
心を提供することにある。
The purpose of the present invention is to solve this problem, and is designed to retain part or most of the molten fuel in the event that an accident occurs in a nuclear reactor and the fuel cladding tube is damaged. It has a molten fuel retention function that allows the molten fuel to be in a critical shape, and
Moreover, it is an object of the present invention to provide a nuclear reactor core that can also perform a neutron shielding function.

以下、図面に基づき本発明について詳述する。Hereinafter, the present invention will be explained in detail based on the drawings.

第1図は本発明で用いる核燃料集合体の一例の説開国で
ある。
FIG. 1 is an illustration of an example of a nuclear fuel assembly used in the present invention.

この燃料集合体1は高速炉用のものであって、内部に多
数の燃料要素2が束ねられて配置されている六角筒状の
ラッパ管3と、燃料交換時の取扱いのため該ラッパ管3
上端に形成されているハンドリングヘッド4と、ラッパ
管3の下端に設けられている円筒状のエントランスノズ
ル5を具備している。
This fuel assembly 1 is for a fast reactor, and includes a hexagonal cylindrical wrapper tube 3 in which a large number of fuel elements 2 are arranged in a bundle, and the wrapper tube 3 for handling during fuel exchange.
It includes a handling head 4 formed at the upper end and a cylindrical entrance nozzle 5 provided at the lower end of the wrapper tube 3.

エントランスノズル5の側壁には多数のオリフィス孔6
が穿設され、ラッパ管3の内部およびハンドリングヘッ
ド4の開口部に連通している。
A large number of orifice holes 6 are provided on the side wall of the entrance nozzle 5.
is bored and communicates with the inside of the wrapper tube 3 and the opening of the handling head 4.

エントランスノズル5の上方かつ燃料要素2の束の下方
には、多数の縦貫孔8が形成された高融点材料製の溶融
燃料保持体9が設けられており、また、燃料要素2の束
の上方には上部遮蔽体10が配置されている。
Above the entrance nozzle 5 and below the bundle of fuel elements 2, a molten fuel holder 9 made of a high melting point material and having a large number of vertical holes 8 is provided. An upper shielding body 10 is arranged.

溶融燃料保持体9の材質としては、冷却材(高速中性子
炉の場合、通常液体ナトリウム)や溶融した燃料と接触
したときに著しい反応等をひきおこさないようこれらの
物質と共存性のよいものであり、例えばタンタル、タン
グステントリウム化合物、ウラン化合物、黒鉛等を用い
ることができる。
The material of the molten fuel holder 9 should be one that has good coexistence with the coolant (usually liquid sodium in the case of a fast neutron reactor) and molten fuel so as not to cause a significant reaction when it comes into contact with these substances. For example, tantalum, tungstentrium compounds, uranium compounds, graphite, etc. can be used.

また、これらの物質は中性子に対する遮蔽能力もすぐれ
ており、炉心下方にある原子炉構造物または炉心支持構
造物の中性子照射に対する遮蔽体としても有効である。
Furthermore, these materials have excellent neutron shielding ability and are effective as shields for neutron irradiation of nuclear reactor structures or core support structures located below the reactor core.

この燃料集合体1はそのエントランスノズル部5が原子
炉容器下部に取付けられた支持構造物にさしこまれて支
持され、冷却材はオリフィス孔6から流入し、エントラ
ンスノズル5、溶融保持体9の縦貫孔8を通って燃料要
素2に沿って上昇し、ハンドリングヘッド4から流出す
る。
This fuel assembly 1 is supported by having its entrance nozzle part 5 inserted into a support structure attached to the lower part of the reactor vessel, and the coolant flows in from the orifice hole 6, and the entrance nozzle part 5 and the melting holder 9 through the longitudinal bore 8 of the fuel element 2 and exits the handling head 4.

ここで、万一、何等かの事故が生じ、出力が上昇して燃
料集合体1内にて束ねられて収納されている燃料要素2
の被覆管が破損し、溶融燃料が噴出したとすると、該溶
融燃料の大部分は落下し、溶融燃料保持体9の上面に達
する。
In the unlikely event that some kind of accident occurs, the output increases and the fuel elements 2 that are bundled and stored in the fuel assembly 1
If the cladding tube is damaged and molten fuel spouts out, most of the molten fuel falls and reaches the upper surface of the molten fuel holder 9.

落下してくる溶融燃料は流動性があまりないから、その
大部分は溶融燃料保持体9の上面にとどまり保持される
Since the falling molten fuel does not have much fluidity, most of it remains on the upper surface of the molten fuel holder 9 and is held there.

前記のように保持体9は高融点材料で作られているから
、高温の溶融燃料によって侵される虞れもなく、確実に
保持できるのである。
As mentioned above, since the holder 9 is made of a high melting point material, it can be held reliably without the risk of being attacked by high temperature molten fuel.

第2図は本発明で用いる燃料集合体の他の例の説明図で
ある。
FIG. 2 is an explanatory diagram of another example of the fuel assembly used in the present invention.

第1図と相違する点は、溶融燃料保持体9の上方に下部
遮蔽体11を設けた点である。
The difference from FIG. 1 is that a lower shield 11 is provided above the molten fuel holder 9.

前記のようにタンタルやタングステントリウム化合物等
で作られた溶融燃料保持体9はそれら自身、中性子に対
する遮蔽能力がすぐれており、炉心下方に対する遮蔽体
としても利用できるが、それらのみでは不充分な場合、
例えばステンレス鋼製の如き下部遮蔽体11を併設する
ことによって、中性子に対する遮蔽をより確実にするこ
とができる。
As mentioned above, the molten fuel holders 9 made of tantalum, tungsten triumium compounds, etc. themselves have excellent shielding ability against neutrons and can be used as a shield for the lower part of the reactor core, but in cases where these alone are insufficient. ,
For example, by providing a lower shield 11 made of stainless steel, shielding against neutrons can be made more reliable.

溶融燃料保持体9と下部遮蔽体11とはどちらが上方に
位置してもかまわないが、第2図のように溶融燃料保持
体9を下方に位置させた方が取付は易い。
Although either of the molten fuel holder 9 and the lower shield 11 may be positioned upward, it is easier to attach the molten fuel holder 9 if it is positioned downward as shown in FIG.

溶融燃料保持体9のラッパ管3への固着は、例えば第3
図に示すように嵌め込みで行ってもよいし、第4図に示
すように、溶融燃料保持体9の側部から複数本の連結棒
12を突設し、該連結棒12の先端をラッパ管3の管壁
に溶接することによって行うようにしてもよい。
The adhesion of the molten fuel holding body 9 to the trumpet tube 3 can be achieved, for example, by the third
As shown in the figure, this may be done by fitting, or as shown in FIG. This may be done by welding to the pipe wall of No. 3.

さて、次にかかる構造の燃料集合体で構成した本発明の
原子炉について説明する。
Next, a nuclear reactor of the present invention constructed from a fuel assembly having such a structure will be explained.

第5図がその一実施例である。FIG. 5 shows an example of this.

原子炉容器(図示せず)内の下方部には燃料集合体の支
持構造物15が設けられていて、多数の 料集合体1a
、1b、1c、・・・はその各エントランスノズル5が
挿入されて固定される。
A support structure 15 for fuel assemblies is provided in the lower part of the reactor vessel (not shown), and supports a large number of fuel assemblies 1a.
, 1b, 1c, . . . have their respective entrance nozzles 5 inserted and fixed.

各燃料集合体1a、1b、1c、・・・の構造は第1図
、第2図に示したのと同様のものであって、エントラン
スノズル5の上方でかつ燃料要素2の東の下方に高融点
材料で作られた柱状の溶融燃料保持体9a、9b、9c
、・・・がそれぞれ配置されている。
The structure of each fuel assembly 1a, 1b, 1c, . . . is similar to that shown in FIGS. Columnar molten fuel holding bodies 9a, 9b, 9c made of high melting point material
,... are arranged respectively.

ここで、炉心中央の燃料集合体の溶融燃料保持体はどそ
の柱高が高くなっており、炉心周辺にいくにつれて次第
に低くなるように配置されている。
Here, the molten fuel holding bodies of the fuel assembly in the center of the core are arranged such that the height of each column is high and becomes gradually lower toward the periphery of the core.

つまり、溶融燃料保持体9の上面は、炉心中央はど高く
、炉心周辺にいくにつれて低なっているから、燃料被覆
管が破損し、溶融燃料保持体9の上面に落下堆積した溶
融燃料が臨界形状になるのを避けることができる。
In other words, since the upper surface of the molten fuel holder 9 is high at the center of the core and becomes lower toward the periphery of the core, the fuel cladding tube is damaged and the molten fuel that falls and accumulates on the upper surface of the molten fuel holder 9 becomes critical. shape can be avoided.

また、高速炉の炉心では中央はど中性子束が高く、周辺
はど中性子束が低い。
Furthermore, in the core of a fast reactor, neutron flux is high in the center and low in the periphery.

前記のように、溶融燃料保持体は中性子遮蔽能力があり
、その柱高変化も中性子束の高低に対応して変化させて
いるから、炉心下方部の中性子照射による照射損傷を避
けることができる。
As mentioned above, the molten fuel holder has the ability to shield neutrons, and its column height is also changed in accordance with the height of the neutron flux, so irradiation damage due to neutron irradiation in the lower part of the core can be avoided.

本発明は上記のように構成した原子炉炉心であるから、
原子炉において何等かの事故が生じ、燃料被覆管の破損
が生じた場合に、溶融燃料の一部もしくは大部分を確実
に保持することができ、かつ溶融燃料が臨界形状になる
ことを回避でき、しかも中性子遮蔽機能を果たすことが
でき、中性子束の高低に応じた溶融燃料の柱高変化によ
り、炉心下方部の中性子照射による照射損傷を避けるこ
とができる等の数々のすぐれた効果を奏しうるものであ
る。
Since the present invention is a nuclear reactor core configured as described above,
In the event that some kind of accident occurs in a nuclear reactor and the fuel cladding tube is damaged, a part or most of the molten fuel can be reliably retained and the molten fuel can be prevented from becoming in a critical shape. Furthermore, it can perform a neutron shielding function, and has many excellent effects, such as being able to avoid irradiation damage due to neutron irradiation in the lower part of the reactor core by changing the height of the molten fuel column according to the level of neutron flux. It is something.

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

第1図は本発明で用いる核燃料集合体の一例の説明図、
第2図は核燃料集合体の他の例の説明図、第3図、第4
図はそれぞれ溶融燃料保持体のラッパ管への取付は方を
示す説明図、第5図は本発明に係る原子炉炉心の一実施
例の説明図である。 1・・・・・・燃料集合体、2・・・・・・燃料要素、
3・・・・・・ラッパ管、4・・・・・・ハンドリング
ヘッド、5・・・・・・エントランスノズル、8・・・
・・・縦貫孔、9・・・・・・溶融燃料保持体、15・
・・・・・燃料集合体の支持構造物。
FIG. 1 is an explanatory diagram of an example of a nuclear fuel assembly used in the present invention,
Figure 2 is an explanatory diagram of other examples of nuclear fuel assemblies, Figures 3 and 4.
Each figure is an explanatory view showing how to attach a molten fuel holding body to a trumpet tube, and FIG. 5 is an explanatory view of an embodiment of a nuclear reactor core according to the present invention. 1...Fuel assembly, 2...Fuel element,
3...Trumpet pipe, 4...Handling head, 5...Entrance nozzle, 8...
... Vertical hole, 9 ... Molten fuel holding body, 15.
...Fuel assembly support structure.

Claims (1)

【特許請求の範囲】[Claims] 1 エントランスノズルの上部でかつ燃料要素束の下方
に、多数の縦貫孔を有する高融点材料製の柱状の溶融燃
料保持体を設けてなる核燃料集合体で構成され、該溶融
燃料保持体の柱高を炉内の中性子束が高い領域はど高く
、中性子束が低い領域はど低くした原子炉炉心。
1 A nuclear fuel assembly consisting of a columnar molten fuel holder made of a high melting point material having a large number of longitudinal holes provided above the entrance nozzle and below the fuel element bundle, and the column height of the molten fuel holder. In the reactor core, areas with high neutron flux in the reactor are set high, and areas with low neutron flux are set low.
JP52126429A 1977-10-21 1977-10-21 Nuclear reactor core using fuel assembly with molten fuel retainer Expired JPS58637B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP52126429A JPS58637B2 (en) 1977-10-21 1977-10-21 Nuclear reactor core using fuel assembly with molten fuel retainer

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP52126429A JPS58637B2 (en) 1977-10-21 1977-10-21 Nuclear reactor core using fuel assembly with molten fuel retainer

Publications (2)

Publication Number Publication Date
JPS5459596A JPS5459596A (en) 1979-05-14
JPS58637B2 true JPS58637B2 (en) 1983-01-07

Family

ID=14934961

Family Applications (1)

Application Number Title Priority Date Filing Date
JP52126429A Expired JPS58637B2 (en) 1977-10-21 1977-10-21 Nuclear reactor core using fuel assembly with molten fuel retainer

Country Status (1)

Country Link
JP (1) JPS58637B2 (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2951578B1 (en) * 2009-10-16 2012-06-08 Commissariat Energie Atomique ASSEMBLY OF NUCLEAR FUEL AND NUCLEAR REACTOR COMPRISING AT LEAST ONE SUCH ASSEMBLY
JP6615605B2 (en) * 2015-12-25 2019-12-04 株式会社東芝 Fast reactor core and fast reactor

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS52137588A (en) * 1976-05-14 1977-11-17 Hitachi Ltd Fuel assembly

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS52137588A (en) * 1976-05-14 1977-11-17 Hitachi Ltd Fuel assembly

Also Published As

Publication number Publication date
JPS5459596A (en) 1979-05-14

Similar Documents

Publication Publication Date Title
DE2614187C2 (en) Catcher for melted reactor material in the event of a reactor accident
US4116764A (en) Apparatus for controlling nuclear core debris
US4420458A (en) Nuclear fuel assembly with coolant conducting tube
JPH0778548B2 (en) Nuclear fuel assembly with large diameter coolant guide tube
DE1119427B (en) Transport container for radioactive material
EP3234948B1 (en) Fuel assembly for an sfr nuclear reactor, comprising a housing containing a removably fastened upper neutron shielding device
EP0186487B1 (en) Spent fuel storage cask having basked with grid assemblies
JPH1062575A (en) Fuel rod having resistance to corrosion and resistance to hydride formation
JPS637353B2 (en)
EP0928488B1 (en) Gap forming and cooling structure for a nuclear reactor
US3378458A (en) Nuclear reactor fuel element
EP1233423B1 (en) Apparatus for cooling and protecting a reactor pressure vessel in the event of a core melting accident
US3981598A (en) Fuse and application of said fuse to the construction of an emergency shutdown system for a nuclear reactor
JPS58637B2 (en) Nuclear reactor core using fuel assembly with molten fuel retainer
US4076587A (en) Fuse and application of said fuse to the construction of an emergency shutdown system for a nuclear reactor
JPH033917B2 (en)
US5333156A (en) Nuclear fuel assembly with an integrated passive safety device
US4664878A (en) Light water moderator filled rod for a nuclear reactor
KR970060252A (en) Nuclear fuel pellets
EP0514121B1 (en) Nuclear fuel assembly comprising two-diameter fuel rods
JPS6130719B2 (en)
US3886037A (en) Nuclear fuel pin controlled failure device
US3249510A (en) Shutdown apparatus for nuclear reactors
JP5947733B2 (en) Fast reactor core
SU712050A3 (en) Device for capturing molten and structural fragments of exothermal assemblies of nuclear reactor