JP2005201735A - Test method for simulating actual utilization of new type fuel - Google Patents

Test method for simulating actual utilization of new type fuel Download PDF

Info

Publication number
JP2005201735A
JP2005201735A JP2004007183A JP2004007183A JP2005201735A JP 2005201735 A JP2005201735 A JP 2005201735A JP 2004007183 A JP2004007183 A JP 2004007183A JP 2004007183 A JP2004007183 A JP 2004007183A JP 2005201735 A JP2005201735 A JP 2005201735A
Authority
JP
Japan
Prior art keywords
capsule
fuel
reactor
test
fuel element
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
JP2004007183A
Other languages
Japanese (ja)
Other versions
JP4022204B2 (en
Inventor
Ryoichi Kitamura
了一 北村
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.)
Japan Atomic Energy Agency
Original Assignee
Japan Nuclear Cycle Development Institute
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 Japan Nuclear Cycle Development Institute filed Critical Japan Nuclear Cycle Development Institute
Priority to JP2004007183A priority Critical patent/JP4022204B2/en
Publication of JP2005201735A publication Critical patent/JP2005201735A/en
Application granted granted Critical
Publication of JP4022204B2 publication Critical patent/JP4022204B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

Links

Images

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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

<P>PROBLEM TO BE SOLVED: To ensure safety of new type fuel having no or least utilization experience for using in a reactor. <P>SOLUTION: The whole of a single new type fuel element 30 for testing is installed in capsules 34a and 34b and held by a shroud tube 32. The capsules are independently contained in a compartment 14 to be a coolant flow path. A plurality of compartments are arranged around middle tie-rod 12 and its surrounding is covered with a wrapper tube 18 to be a capsule type irradiation fuel assembly 10 for testing. By loading this and irradiating with neutrons in a reactor, the use of the new type fuel elements in a commercial reactor is simulated while ensuring safety in the reactor by the capsule. <P>COPYRIGHT: (C)2005,JPO&NCIPI

Description

本発明は、原子炉における新型燃料の実用化のための模擬試験方法、及びそれに用いる試験用照射燃料集合体に関するものである。更に詳しく述べると本発明は、新型燃料の試験を含めた許認可取得までの方法、及びその試験を実施するための照射用燃料集合体に関するものである。   The present invention relates to a simulation test method for practical use of a new type fuel in a nuclear reactor, and a test irradiation fuel assembly used therefor. More specifically, the present invention relates to a method for obtaining approval including a test of a new type fuel, and an irradiation fuel assembly for performing the test.

原子炉材料や核燃料の研究開発などでは、材料試験片などを原子炉内に配置して放射線の作用下に曝す照射試験が行われている。例えば、高温の放射線環境下における液体冷却材中での材料のクリープ破断強度試験では、高圧ガスを封入した一定形状の円筒状の試験片を照射キャプセル内に収納し、それを原子炉内に挿入して、放射線環境下の液体中で試験片が破断するまでの時間を測定する(例えば特許文献1参照)。比較的小さな試験片の場合には、このような方法で特に問題は生じない。   In research and development of nuclear reactor materials and nuclear fuel, irradiation tests are conducted in which material specimens are placed in the nuclear reactor and exposed to radiation. For example, in a creep rupture strength test of a material in a liquid coolant under a high-temperature radiation environment, a cylindrical specimen with a fixed shape filled with high-pressure gas is stored in an irradiation capsule and inserted into a nuclear reactor. Then, the time until the test piece breaks in the liquid in the radiation environment is measured (see, for example, Patent Document 1). In the case of a relatively small test piece, this method does not cause any particular problem.

しかし、上記の方法は材料単体の試験であり、組み上げた燃料要素の試験では別の問題が生じる。試験用燃料要素を原子炉で使用する場合、
(1)試験用燃料要素に燃料溶融や被覆管破損が生じても、他の燃料要素に影響を与えないこと、及び
(2)試験用燃料要素の被覆管破損による燃料片やFP(核分裂生成物)の過度の拡散を防ぐこと、
が安全性確保に必要である。つまり、試験用燃料要素は、それ自体が、このような安全性を確保できる能力を有していなければならない。しかし、使用実績の無いあるいは少ない試験用燃料要素を原子炉で使用した場合、このような安全性を確保できるという保証はない。
However, the above method is a single material test, and another problem arises in the assembled fuel element test. When the test fuel element is used in a nuclear reactor,
(1) Even if fuel melting or cladding breakage occurs in the test fuel element, it does not affect other fuel elements, and (2) Fuel fragment or FP (fission generation due to damage to the cladding tube of the test fuel element) To prevent excessive diffusion of
Is necessary to ensure safety. That is, the test fuel element must itself have the ability to ensure such safety. However, there is no guarantee that such safety can be ensured when test fuel elements with little or no use are used in a nuclear reactor.

そこで、原子炉での燃料の使用の許可に関する日本の安全審査では、許可範囲での安全設計の妥当性確認のために、海外先行炉での使用実績が求められてきた。そのため、使用実績の無いあるいは少ない燃料(以下、これを「新型燃料」と称す)を原子炉で使用するまでに必要な期間が長くなり、多種多様な新型燃料の試験を行うことが困難であった。
特開平9−145891号公報
Therefore, in Japan's safety review concerning permission for the use of fuel in nuclear reactors, a record of use in overseas advanced reactors has been required in order to confirm the validity of safety design within the scope of permission. For this reason, it takes a long time to use fuel with little or no use (hereinafter referred to as “new fuel”) in a nuclear reactor, making it difficult to test a wide variety of new fuels. It was.
Japanese Patent Laid-Open No. 9-145891

本発明が解決しようとする課題は、使用実績の無いあるいは少ない新型燃料を原子炉で使用することが困難であり、そのため新型燃料の実用化までに長期間を要する点である。   The problem to be solved by the present invention is that it is difficult to use a new fuel with little or no use record in a nuclear reactor, and therefore it takes a long time to put the new fuel into practical use.

本発明は、試験用の新型燃料要素1本全体をキャプセル内に装填し、該キャプセルを複数本配列保持して、キャプセル型照射燃料集合体とし、該キャプセル型照射燃料集合体を原子炉内に装荷して中性子照射を行うことにより、キャプセルによって原子炉内での安全性を確保しつつ実用炉での新型燃料要素の使用を模擬することを特徴とする新型燃料の実用化模擬試験方法である。   In the present invention, an entire new fuel element for testing is loaded into a capsule, and a plurality of the capsules are held in an array to form a capsule-type irradiation fuel assembly. The capsule-type irradiation fuel assembly is placed in a nuclear reactor. This is a practical test method for the practical use of a new fuel, characterized by simulating the use of a new fuel element in a practical reactor while ensuring safety in the reactor with a capsule by loading and neutron irradiation. .

また本発明は、上記新型燃料の実用化模擬試験方法で用いる照射燃料集合体であって、試験用の新型燃料要素1本全体をシュラウド管で保持してキャプセル内に装填し、該キャプセルを独立した冷却材流路となるコンパートメント内に収納し、更に複数のコンパートメントを中央のタイロッドの周囲に配列し、周囲をラッパ管で覆い、上端部にハンドリングヘッドを、下端部にエントランスノズルを設けた試験用キャプセル型照射燃料集合体である。   The present invention also relates to an irradiated fuel assembly used in the above-described practical simulation test method for a new fuel, wherein the entire new fuel element for testing is held in a shroud tube and loaded into the capsule, and the capsule is independently In a compartment that forms a coolant flow path, a plurality of compartments arranged around the center tie rod, covered with a trumpet tube, a handling head at the upper end, and an entrance nozzle at the lower end This is a capsule-type irradiation fuel assembly for use.

本発明は、上記のような新型燃料の実用化模擬試験方法と、それに用いる試験用のキャプセル型照射燃料集合体であり、この技術を利用することによって、使用実績の無いあるいは少ない新型燃料でも安全性を確保しつつ試験を行うことができる。例えば、新型燃料を高速実験炉「常陽」で使用できるようになり、次のような効果が得られる。
(1)高速増殖炉の実用化に向けた開発において、対象となっている多種多様な燃料(マイナーアクチニド添加燃料、バイパック燃料等)の照射試験が全て高速実験炉「常陽」で実施可能となる。
(2)新型燃料の使用開始までの準備について、海外炉での先行照射も含めると、必要な期間を約4年は短縮できる。
(3)燃料の組成の一部であるプルトニウムについて、その富化度を制限する必要がないため、ウラン無し燃料によるプルトニウム燃焼炉の研究開発に資する照射試験にも対応可能となる。
(4)米国等によるGEN−IV(第4世代原子力発電システム)をはじめとする多種多様な照射ニーズに対し、世界でも数少ない高速中性子照射場として、それらに応えることが可能となる。
(5)この技術は、今後、燃料体に限らず、核燃料物質やRIを含む材料等の使用にも適用可能となる。
The present invention is a simulation test method for practical application of a new fuel as described above, and a capsule-type irradiation fuel assembly for testing used therefor. By using this technology, it is possible to safely use a new fuel with little or no use record. The test can be performed while securing the property. For example, the new fuel can be used in the fast experimental reactor “Joyo”, and the following effects can be obtained.
(1) In the development for the practical application of fast breeder reactors, irradiation tests of various target fuels (minor actinide-added fuel, bipack fuel, etc.) can all be performed in the fast experimental reactor “Joyo” .
(2) With regard to preparations for the start of the use of new fuels, including prior irradiation in overseas reactors, the required period can be shortened by about 4 years.
(3) Since it is not necessary to limit the enrichment level of plutonium, which is a part of the fuel composition, it is possible to support irradiation tests that contribute to research and development of plutonium combustion furnaces using uranium-free fuel.
(4) It is possible to respond to various irradiation needs including GEN-IV (4th generation nuclear power generation system) by the United States etc. as one of the few fast neutron irradiation fields in the world.
(5) This technology will be applicable not only to fuel bodies but also to the use of nuclear fuel materials and materials containing RI.

試験用燃料要素を原子炉内で使用する場合に、安全性確保に必要なことは、前述のように、「試験用燃料要素に燃料溶融や被覆管破損が生じても他の燃料要素に影響を与えないこと」及び「試験用燃料要素の被覆管破損による燃料片やFPの過度の拡散を防ぐこと」である。このため、使用実績がないあるいは少ない試験用燃料要素を用いた場合であつても、原子炉の安全性を確保できるように、従来、上記の条件を満足する能力を持たせていた試験用燃料要素に代わり、本発明では集合体構成部品にその能力を持たせるように発想の転換を図ったものである。そのため、試験用燃料要素を装填するキャプセルを内蔵したキャプセル型照射燃料集合体を開発し、それを用いることで試験用燃料要素を安全に原子炉内に装荷できるように構成している。   As described above, when using a test fuel element in a nuclear reactor, it is necessary to ensure the safety of the test fuel element even if fuel melt or cladding breakage occurs in the test fuel element. And “preventing excessive diffusion of fuel fragments and FP due to breakage of the cladding tube of the test fuel element”. For this reason, even in the case of using a test fuel element that has not been used or few, a test fuel that has been conventionally provided with the ability to satisfy the above conditions so as to ensure the safety of the nuclear reactor. Instead of elements, in the present invention, the idea is changed so that the assembly component has the ability. For this reason, a capsule-type irradiation fuel assembly having a built-in capsule for loading a test fuel element has been developed, and the test fuel element can be safely loaded into the reactor by using it.

具体的には、試験用の新型燃料要素1本全体をシュラウド管で保持してキャプセル内に装填し、該キャプセルを独立した冷却材流路となるコンパートメント内に収納し、更に複数のコンパートメントを中央のタイロッドの周囲に配列し、周囲をラッパ管で覆い、上端部にハンドリングヘッドを、下端部にエントランスノズルを設けて試験用キャプセル型照射燃料集合体とする。このキャプセル型照射燃料集合体を原子炉内に装荷して中性子照射を行うことにより、キャプセルによって原子炉内での安全性を確保しつつ実用炉での新型燃料要素の使用を模擬する。   Specifically, a whole new fuel element for testing is held by a shroud tube and loaded into a capsule, and the capsule is stored in a compartment serving as an independent coolant flow path. Are arranged around the tie rod, covered with a trumpet tube, a handling head at the upper end, and an entrance nozzle at the lower end to provide a test capsule type irradiated fuel assembly. By loading the capsule-type irradiated fuel assembly into the reactor and performing neutron irradiation, the use of the new fuel element in the practical reactor is simulated while ensuring safety in the reactor by the capsule.

図1は、本発明に係るキャプセル型照射燃料集合体の一実施例を示す説明図である。Aはキャプセル型照射燃料集合体の全体構造、Bは横断面、Cはコンパートメント、Dは開放型のキャプセル、Eは密封型のキャプセルをそれぞれ示している。キャプセル型照射燃料集合体10は、中央のタイロッド12の周りに6本のコンパートメント14を配置し、それらが上下両端で保持されて、ロックナット16で固定され、それらを六角筒状のラッパ管18で覆った構造である。キャプセル型照射燃料集合体の上端部にはハンドリングヘッド20を、下端部にはエントランスノズル22を配し、周囲にはスペーサパッド24が配設されている。このキャプセル型照射燃料集合体10は、運転用の燃料集合体と同形であり、それと置き換えて炉心に装荷できるようになっている。   FIG. 1 is an explanatory view showing an embodiment of a capsule-type irradiated fuel assembly according to the present invention. A is the entire structure of the capsule-type irradiated fuel assembly, B is a cross section, C is a compartment, D is an open type capsule, and E is a sealed type capsule. The capsule-type irradiation fuel assembly 10 has six compartments 14 arranged around a central tie rod 12, which are held at both upper and lower ends and fixed by lock nuts 16. It is the structure covered with. A handling head 20 is disposed at the upper end of the capsule-type irradiated fuel assembly, an entrance nozzle 22 is disposed at the lower end, and a spacer pad 24 is disposed around the periphery. The capsule-type irradiation fuel assembly 10 has the same shape as the fuel assembly for operation, and can be loaded into the core in place of it.

試験用の新型燃料要素30は、その1本全体がシュラウド管32で保持されて、厚肉管のキャプセル34a,34b内に装填されるようになっている。このキャプセル34a,34bは、新型燃料要素30の被覆管が破損した際に生じる圧力が、キャプセルの外へ伝わらないようにし、他の燃料要素等への破損伝播を防止する機能を果たす。キャプセルには、開放型(内壁構造容器)と密封型(密封構造容器)とがある。開放型のキャプセル34aの場合には、容器胴36の上方と下方にストレーナ38を設置し、上下に開放部を形成する。密封型のキャプセル34bの場合には、ストレーナに代えて容器胴36の上方と下方に閉止板40を設置することで密封構造とする。   One of the new test fuel elements 30 is held by a shroud tube 32 and loaded into the thick-walled capsules 34a and 34b. The capsules 34a and 34b function to prevent the pressure generated when the cladding tube of the new fuel element 30 is damaged from being transmitted to the outside of the capsule and to prevent the propagation of damage to other fuel elements. There are an open type (inner wall structure container) and a sealed type (sealed structure container). In the case of the open type capsule 34a, strainers 38 are installed above and below the container body 36, and open portions are formed vertically. In the case of the sealed capsule 34b, a sealing structure is formed by installing a closing plate 40 above and below the container body 36 in place of the strainer.

このような開放型のキャプセル34aまたは密封型のキャプセル34bが、1本ずつコンパートメント14に収納される。コンパートメント14によって、新型燃料要素1本毎に独立した冷却材流路が確保される。そこで、コンパートメント14は、内外2重構造をなし、外管42と内管44の間をガス層として、このガス層に断熱効果の高いガスを充填することにより、独立した冷却材流路の確保と合わせて、熱的に新型燃料要素1本毎に独立させることを可能としている。下端部に冷却材流入孔50が開口し、オリフィス52が設けられ、上端部に多数の小孔54が開口してそれが冷却材流出部となっている。   Such an open type capsule 34a or a sealed type capsule 34b is stored in the compartment 14 one by one. The compartment 14 ensures an independent coolant channel for each new fuel element. Therefore, the compartment 14 has an inner / outer dual structure, and a gas layer is formed between the outer tube 42 and the inner tube 44, and the gas layer is filled with a gas having a high heat insulating effect, thereby securing an independent coolant channel. In addition, it is possible to make each new fuel element thermally independent. A coolant inflow hole 50 is opened at the lower end portion, an orifice 52 is provided, and a number of small holes 54 are opened at the upper end portion, which serve as a coolant outflow portion.

キャプセル34a,34bの容器胴は厚肉管からなり、これによって新型燃料要素の被覆管が破損した際に生じる圧力にキャプセルが耐えうる構造とする。キャプセルは、その試験内容だけでなく従来にも増して安全審査が厳しくなることから、材質や肉厚などが制限される。例えば、JISのSUS316を改良した材料(高速増殖炉「もんじゅ」の被覆管やラッパ管に使用している材料)を用い、肉厚は2.8mm以上とする。   The container bodies of the capcells 34a and 34b are made of thick-walled pipes, so that the capsules can withstand the pressure generated when the cladding tube of the new fuel element is broken. Capsule is not only limited to the contents of the test but also has a more stringent safety review than before, so the material and thickness are limited. For example, a material obtained by improving JIS SUS316 (a material used for a cladding tube or a trumpet tube of a fast breeder reactor “Monju”) is used, and the wall thickness is 2.8 mm or more.

ところで、燃料要素の種類が異なる場合、大きく違う可能性があるのは、その直径と全長である。直径は燃料要素の保持手段の径方向の大きさに、全長は保持手段の軸方向位置に影響を及ぼす。キャプセルを試験用の新型燃料要素の直径及び全長に合わせて製作すればよいのであるが、キャプセルは新型燃料要素の被覆管が破損した際に生じる圧力にキャプセルが耐えられるよう寸法を定める必要があり、そのためキャプセルを燃料要素の直径及び全長に合わせて製作するというわけにはいかない事情がある。そこで本発明では、キャプセルの中にシュラウド管と呼ぶ別の管を設けて、これを燃料要素とキャプセルの空間を維持するスペーサとする構造を採用している。シュラウド管は、その名のとおり管状であり、保持する燃料要素の直径に合わせた内径、保持する燃料要素の全長に合わせた長さとする。従って、シュラウド管のみ燃料要素に合わせた専用設計となる。シュラウド管はキャプセル内に固定されるが、燃料要素が異なっても固定位置と固定方法を同一にできるので、燃料要素の種類が異なっても同一のキャプセルを使用することが可能になる。   By the way, when the types of fuel elements are different, it is the diameter and the total length that may greatly differ. The diameter affects the radial size of the holding means of the fuel element, and the total length affects the axial position of the holding means. Capsules can be made to match the diameter and length of the new fuel element for testing, but the capsule must be dimensioned to withstand the pressure generated when the cladding of the new fuel element breaks. Therefore, there is a situation where it is not possible to manufacture the capsule according to the diameter and the total length of the fuel element. Therefore, the present invention employs a structure in which another tube called a shroud tube is provided in the capsule, and this is used as a spacer for maintaining the space between the fuel element and the capsule. As the name suggests, the shroud tube is tubular, and has an inner diameter that matches the diameter of the fuel element to be held and a length that matches the overall length of the fuel element to be held. Therefore, only the shroud tube is designed exclusively for the fuel element. Although the shroud tube is fixed in the capsule, since the fixing position and the fixing method can be the same even if the fuel elements are different, it is possible to use the same capsule even if the types of the fuel elements are different.

上記のように、キャプセルとしては、開放型のキャプセル34aの他、試験用燃料要素の被覆管破損により放出される燃料片及び核分裂生成物(FP)を全て閉じこめる密封型のキャプセル34bがある。   As described above, as the capsule, there is an open-type capsule 34a, and a sealed-type capsule 34b that can confine all the fuel pieces and fission products (FP) released due to breakage of the cladding of the test fuel element.

開放型キャプセル34aは、キャプセルの上下が開放されていることから、炉内装荷により一次系冷却材のナトリウムを熱ボンド材として内部に導入できる利点を有しており、現有施設・設備での再組立・再装荷が可能である。しかし、試験用燃料要素の被覆管破損により放出される燃料片及びFPを全て閉じこめることはできない。このため、開放型キャプセルは、プラントの運転時の異常な過渡変化時にあっても試験用燃料要素の被覆管の健全性が確保できる場合に限り使用できることとし、プラントの事故と相まって試験用燃料要素の被覆管が破損した際に放出される燃料片及びFPの過度の拡散を防ぐため、キャプセル上下の開放部にストレーナ38を設置している。   The open-type capsule 34a has an advantage that the primary coolant sodium can be introduced into the inside as a thermal bond material by the furnace interior load because the top and bottom of the capsule are open. Can be assembled and reloaded. However, it is not possible to confine all the fuel pieces and FP released due to breakage of the cladding tube of the test fuel element. For this reason, open-type capsules can be used only when the soundness of the cladding of the test fuel element can be secured even during abnormal transient changes during plant operation. In order to prevent excessive diffusion of the fuel pieces and FP that are released when the cladding tube is broken, strainers 38 are installed in the open portions above and below the capsule.

このような構造をとることで、例えば、酸化物燃料を溶融させる試験を行う場合(酸化物燃料以外は溶融させない)、万一、被覆管破損事故が発生しても、溶融燃料と冷却材の接触により発生する圧力に対し十分な強度を有するよう設計することにより、他の燃料要素の健全性に悪影響を与える恐れは生じない。   By taking such a structure, for example, when performing a test for melting oxide fuel (other than oxide fuel is not melted), even if a cladding tube accident occurs, the molten fuel and coolant By designing to have sufficient strength against the pressure generated by contact, there is no possibility of adversely affecting the health of other fuel elements.

ここでストレーナ38はステンレス鋼製の多孔板であり、熱を伝える物質として、開放型キャプセル34a内に一次系冷却材であるナトリウムを導入できるよう孔を開けたものである。ただし、万一の新型燃料要素の被覆管の破損に伴って生じる小片が、原子炉の一次系の何処かに引っかかって冷却材の流れを阻害することがないように、ある程度の大きさのものを捕らえる目的で、小径の多孔としている。   Here, the strainer 38 is a perforated plate made of stainless steel, and has a hole so that sodium, which is a primary coolant, can be introduced into the open-type capsule 34a as a material for transferring heat. However, it should be of a certain size so that the small pieces generated in the event of a breakage of the cladding of the new fuel element will not get caught in any part of the primary system of the reactor and obstruct the coolant flow. For the purpose of catching, it has a small-diameter porous.

通常は、上記のような開放型のキャプセル34aを使用するが、被覆管が破損するように故意に設計した場合など被覆管の開孔を許容する設計を行う場合には密封型のキャプセル34bを使用する。被覆管開孔時に放出される核分裂生成ガス及び燃料を、密封型のキャプセル34b内に閉じ込め、原子炉内への拡散を防止する。   Normally, the open type capcell 34a as described above is used. However, when the design is to allow the opening of the cladding tube, such as when the cladding tube is intentionally designed to break, the sealed type capsule 34b is used. use. The fission product gas and fuel released when the cladding tube is opened are confined in a sealed capsule 34b to prevent diffusion into the reactor.

本発明では、運転用燃料集合体と入れ替えてキャプセル型照射燃料集合体を炉心に装荷し試験する。従って、キャプセル型照射燃料集合体を装荷する位置は、運転用燃料集合体のある位置となる。なお、装荷するキャプセル型照射燃料集合体の体数は、安全性などの観点から最大7体程度に制限される。   In the present invention, the encapsulated irradiation fuel assembly is loaded on the core and tested in place of the operating fuel assembly. Therefore, the position where the capsule-type irradiation fuel assembly is loaded is the position where the operating fuel assembly is located. The number of encapsulated irradiated fuel assemblies to be loaded is limited to a maximum of about 7 from the viewpoint of safety and the like.

原子炉内におけるキャプセル型照射燃料集合体の設計寿命は、例えば750日程度である。しかし、新型燃料要素の装荷期間は1500日を超えるものが多くある。そのような場合には、複数のキャプセル型照射燃料集合体を乗り継ぎながら照射試験を行うことになる。   The design life of the capsule-type irradiation fuel assembly in the nuclear reactor is, for example, about 750 days. However, the loading period of new fuel elements often exceeds 1500 days. In such a case, an irradiation test is performed while connecting a plurality of capsule-type irradiation fuel assemblies.

本発明の実用化模擬試験においては、原子炉の事故と相まって、照射試験に供している新型燃料要素の健全性が喪失しても、これに起因する事象が、キャプセル型照射燃料集合体の中で収束することであれば、新型燃料要素は安全である(許認可が受けられる)と判断できる。   In the practical use simulation test of the present invention, even if the integrity of the new fuel element used in the irradiation test is lost due to the accident of the reactor, an event caused by this will occur in the capsule-type irradiated fuel assembly. If it converges at, it can be determined that the new fuel element is safe (permitted).

このようにすることで、万一、プラントの事故と相まってキャプセルに収めた試験用燃料要素の健全性が喪失しても、キャプセルの健全性が確保され、プラントに悪影響を及ぼす恐れはない。事故時にあってもキャプセルが安全性を担保することから、設置許可時の試験用燃料要素の設計にあっては、キャプセルの健全性に影響を与えないよう、設計方針及び設計方法並びに制限値の設定の考え方を明確にすればよく、燃料材や被覆材の物性データが必要にならない(使用実績も必要ない)新しい許認可取得方法が確立できた。   By doing in this way, even if the soundness of the test fuel element stored in the capsule is lost due to an accident in the plant, the soundness of the capsule is ensured and there is no possibility of adversely affecting the plant. Since the capsule will ensure safety even in the event of an accident, the design policy, design method and limit values should be set so that the integrity of the capsule will not be affected in the design of the test fuel element at the time of installation permission. It is only necessary to clarify the concept of setting, and a new license acquisition method has been established that does not require physical property data of fuel materials and coating materials (no need for actual use).

なお本発明方法は、高速増殖炉のみならず、全ての原子炉で実施可能なことはいうまでもない。   Needless to say, the method of the present invention can be implemented not only in a fast breeder reactor but also in all reactors.

本発明に係るキャプセル型照射燃料集合体の一実施例を示す説明図。Explanatory drawing which shows one Example of the capsule-type irradiation fuel assembly which concerns on this invention.

符号の説明Explanation of symbols

10 キャプセル型照射燃料集合体
12 タイロッド
14 コンパートメント
18 ラッパ管
20 ハンドリングヘッド
22 エントランスノズル
30 新型燃料要素
32 シュラウド管
34a 開放型のキャプセル
34b 密封型のキャプセル
DESCRIPTION OF SYMBOLS 10 Capsule type irradiation fuel assembly 12 Tie rod 14 Compartment 18 Trumpet pipe 20 Handling head 22 Entrance nozzle 30 New fuel element 32 Shroud pipe 34a Open type capsule 34b Sealed type capsule

Claims (2)

試験用の新型燃料要素1本全体をキャプセル内に装填し、該キャプセルを複数本配列保持してキャプセル型照射燃料集合体とし、該キャプセル型照射燃料集合体を原子炉内に装荷して中性子照射を行うことにより、キャプセルによって原子炉内での安全性を確保しつつ実用炉での新型燃料要素の使用を模擬することを特徴とする新型燃料の実用化模擬試験方法。   A whole new fuel element for testing is loaded into a capsule, and a plurality of capsules are held in an array to form a capsule-type irradiation fuel assembly. The capsule-type irradiation fuel assembly is loaded into a nuclear reactor and irradiated with neutrons. A practical test method for the practical use of a new fuel, characterized in that the use of a new fuel element in a practical reactor is simulated while ensuring safety in the reactor by a capsule. 請求項1記載の新型燃料の実用化模擬試験方法で用いる照射燃料集合体であって、試験用の新型燃料要素1本全体をシュラウド管で保持してキャプセル内に装填し、該キャプセルを独立した冷却材流路となるコンパートメント内に収納し、更に複数のコンパートメントを中央のタイロッドの周囲に配列し、周囲をラッパ管で覆い、上端部にハンドリングヘッドを、下端部にエントランスノズルを設けた試験用キャプセル型照射燃料集合体。
An irradiated fuel assembly for use in the practical test method for practical application of a new fuel according to claim 1, wherein one whole new fuel element for test is held in a shroud tube and loaded into the capsule, and the capsule is made independent. For testing, which is housed in a compartment that serves as a coolant flow path, and multiple compartments are arranged around the center tie rod, covered with a trumpet tube, a handling head at the upper end, and an entrance nozzle at the lower end Capsule type irradiation fuel assembly.
JP2004007183A 2004-01-14 2004-01-14 Test method for practical use of new fuel Expired - Fee Related JP4022204B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2004007183A JP4022204B2 (en) 2004-01-14 2004-01-14 Test method for practical use of new fuel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2004007183A JP4022204B2 (en) 2004-01-14 2004-01-14 Test method for practical use of new fuel

Publications (2)

Publication Number Publication Date
JP2005201735A true JP2005201735A (en) 2005-07-28
JP4022204B2 JP4022204B2 (en) 2007-12-12

Family

ID=34820914

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2004007183A Expired - Fee Related JP4022204B2 (en) 2004-01-14 2004-01-14 Test method for practical use of new fuel

Country Status (1)

Country Link
JP (1) JP4022204B2 (en)

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR100878330B1 (en) 2007-08-06 2009-01-14 한국원자력연구원 Plug type research reactor irradiation rig
JP2010243465A (en) * 2009-04-10 2010-10-28 Japan Atomic Energy Agency Capsule for light-water reactor fuel irradiation test device
CN101335058B (en) * 2008-08-06 2011-07-20 中国原子能科学研究院 Fuel assembly simulation piece of sodium-cooled fast reactor
CN104183290A (en) * 2013-05-28 2014-12-03 中国原子能科学研究院 Neptunium-containing transmutation test assembly for experimental fast reactor
CN109585047A (en) * 2018-11-12 2019-04-05 中核核电运行管理有限公司 A kind of domestic nuclear fuel assembly enters heap Irradiation Test method
CN110853779A (en) * 2019-11-20 2020-02-28 中国核动力研究设计院 Nuclear fuel irradiation test method
CN111968767A (en) * 2020-09-10 2020-11-20 中国工程物理研究院核物理与化学研究所 Rib type temperature control irradiation device and application thereof
CN112863710A (en) * 2021-01-15 2021-05-28 中国核动力研究设计院 Irradiation test device suitable for rod bundle type fast reactor fuel element
CN114999688A (en) * 2022-06-14 2022-09-02 中国核动力研究设计院 Scaling simulation fuel assembly

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105355236B (en) * 2015-10-13 2018-02-02 上海核工程研究设计院 A kind of simplified simulated fuel assembly

Cited By (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR100878330B1 (en) 2007-08-06 2009-01-14 한국원자력연구원 Plug type research reactor irradiation rig
CN101335058B (en) * 2008-08-06 2011-07-20 中国原子能科学研究院 Fuel assembly simulation piece of sodium-cooled fast reactor
JP2010243465A (en) * 2009-04-10 2010-10-28 Japan Atomic Energy Agency Capsule for light-water reactor fuel irradiation test device
CN104183290A (en) * 2013-05-28 2014-12-03 中国原子能科学研究院 Neptunium-containing transmutation test assembly for experimental fast reactor
CN109585047A (en) * 2018-11-12 2019-04-05 中核核电运行管理有限公司 A kind of domestic nuclear fuel assembly enters heap Irradiation Test method
CN109585047B (en) * 2018-11-12 2022-05-20 中核核电运行管理有限公司 In-pile irradiation testing method for domestic nuclear fuel assembly
CN110853779A (en) * 2019-11-20 2020-02-28 中国核动力研究设计院 Nuclear fuel irradiation test method
CN111968767A (en) * 2020-09-10 2020-11-20 中国工程物理研究院核物理与化学研究所 Rib type temperature control irradiation device and application thereof
CN111968767B (en) * 2020-09-10 2024-05-28 中国工程物理研究院核物理与化学研究所 Rib type temperature control irradiation device and application thereof
CN112863710A (en) * 2021-01-15 2021-05-28 中国核动力研究设计院 Irradiation test device suitable for rod bundle type fast reactor fuel element
CN114999688A (en) * 2022-06-14 2022-09-02 中国核动力研究设计院 Scaling simulation fuel assembly
CN114999688B (en) * 2022-06-14 2024-04-26 中国核动力研究设计院 Scaling simulation fuel assembly

Also Published As

Publication number Publication date
JP4022204B2 (en) 2007-12-12

Similar Documents

Publication Publication Date Title
JP4022204B2 (en) Test method for practical use of new fuel
Tentner et al. Severe accident approach-final report. Evaluation of design measures for severe accident prevention and consequence mitigation.
JP2015172592A (en) Sheathed, annular metal nuclear fuel
US9761332B2 (en) Nuclear reactor neutron shielding
US3459636A (en) Vented fuel pin
KR20140097452A (en) Assembly for a nuclear reactor, comprising nuclear fuel and a system for triggering and inserting at least one neutron absorber and/or mitigator element
US20210210229A1 (en) Liquid metal-cooled nuclear reactor incorporating a completely passive residual power removal (dhr) system
Batyrbekov et al. Experimental opportunities and main results of the impulse graphite reactor use for research in safety area
KR20120011044A (en) Nuclear fission reactor fuel assembly and system for controlled removal of a volatile fission product
JP6615605B2 (en) Fast reactor core and fast reactor
Cinotti et al. Status of the Studies Performed by the European Industry on the LBE Cooled XADS
Yan et al. A study of air ingress and its prevention in HTGR
US4312707A (en) Nuclear fuel rod
JP2009085650A (en) Core component or fast reactor, core fuel assembly, core, and reactor structure
JP2000046979A (en) Control rod for reactor
KR101020780B1 (en) Capsule for irradiation of nuclear fuel
JPH08509548A (en) Fuel rods that cause secondary damage at planned locations
Fuketa et al. Safety significance of the halden IFA-650 LOCA test results
Plitz et al. Experience with failed LMR oxide fuel element performance in European fast reactors
Headquarters Subject
Issard Fuel Behaviour in Transport after Dry Storage: a Key Issue for the Management of used Nuclear Fuel
JP2017040588A (en) Nuclear reactor facility
Poole Feasibility of Detecting Gas Leakage by Monitoring the Outer Surface Temperatures of a Horizontal SNF Canister: Numerical Simulations
JPH09101396A (en) Method for annihilating treatment of unnecessary nuclide using reactor
Van den Eynde et al. Neutronic design of the XT-ADS core with in-pilesections

Legal Events

Date Code Title Description
A977 Report on retrieval

Free format text: JAPANESE INTERMEDIATE CODE: A971007

Effective date: 20060515

A131 Notification of reasons for refusal

Free format text: JAPANESE INTERMEDIATE CODE: A131

Effective date: 20070508

A711 Notification of change in applicant

Free format text: JAPANESE INTERMEDIATE CODE: A712

Effective date: 20070618

A521 Written amendment

Free format text: JAPANESE INTERMEDIATE CODE: A523

Effective date: 20070704

TRDD Decision of grant or rejection written
A01 Written decision to grant a patent or to grant a registration (utility model)

Free format text: JAPANESE INTERMEDIATE CODE: A01

Effective date: 20070911

A61 First payment of annual fees (during grant procedure)

Free format text: JAPANESE INTERMEDIATE CODE: A61

Effective date: 20070928

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20101005

Year of fee payment: 3

R150 Certificate of patent or registration of utility model

Free format text: JAPANESE INTERMEDIATE CODE: R150

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20111005

Year of fee payment: 4

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20121005

Year of fee payment: 5

FPAY Renewal fee payment (event date is renewal date of database)

Free format text: PAYMENT UNTIL: 20131005

Year of fee payment: 6

R250 Receipt of annual fees

Free format text: JAPANESE INTERMEDIATE CODE: R250

LAPS Cancellation because of no payment of annual fees