JPH0868886A - Mox fuel assembly for pwr - Google Patents

Mox fuel assembly for pwr

Info

Publication number
JPH0868886A
JPH0868886A JP6228777A JP22877794A JPH0868886A JP H0868886 A JPH0868886 A JP H0868886A JP 6228777 A JP6228777 A JP 6228777A JP 22877794 A JP22877794 A JP 22877794A JP H0868886 A JPH0868886 A JP H0868886A
Authority
JP
Japan
Prior art keywords
fuel
mox
fuel assembly
assembly
enrichment
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.)
Withdrawn
Application number
JP6228777A
Other languages
Japanese (ja)
Inventor
Masaaki Nakai
正明 中井
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.)
Nuclear Fuel Industries Ltd
Original Assignee
Nuclear Fuel Industries Ltd
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 Nuclear Fuel Industries Ltd filed Critical Nuclear Fuel Industries Ltd
Priority to JP6228777A priority Critical patent/JPH0868886A/en
Publication of JPH0868886A publication Critical patent/JPH0868886A/en
Withdrawn legal-status Critical Current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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

(57)【要約】 【目的】 PWR用MOX燃料集合体において、燃料棒
の種類を削減し、燃料成形加工のコストダウンを図る。 【構成】 燃料集合体の各コーナー部を除く外周部に一
定Pu富化度のMOX燃料棒1を配設すると共に、上記
燃料集合体の中心部に、上記外周部燃料棒より高い一定
Pu富化度のMOX燃料棒2を配設し、かつ前記各コー
ナー部に夫々、ガドリニアを含有するウラン燃料棒3を
配設する。
(57) [Abstract] [Purpose] In the MOX fuel assembly for PWRs, the number of types of fuel rods is reduced, and the cost of fuel forming is reduced. A MOX fuel rod 1 having a constant Pu enrichment is disposed on the outer peripheral portion of the fuel assembly excluding each corner portion, and a constant Pu richness higher than that of the outer peripheral fuel rod is provided on the central portion of the fuel assembly. A MOX fuel rod 2 having a degree of chemical conversion is provided, and a uranium fuel rod 3 containing gadolinia is provided at each of the corners.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は、PWR炉心においてウ
ラン燃料と混在して装荷されるMOX燃料、即ち、核分
裂性プルトニウムを含有するMOX燃料集合体に関する
ものである。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a MOX fuel loaded in a PWR core mixed with uranium fuel, that is, a MOX fuel assembly containing fissile plutonium.

【0002】[0002]

【従来の技術】PWR炉心においてMOX燃料を装荷す
る場合には、核特性の点から炉心の全燃料をMOX燃料
とすることはできないために、UO2 を主体とする通常
のウラン燃料と混在して装荷される。
2. Description of the Related Art When MOX fuel is loaded in a PWR core, it is not possible to use all the fuel in the core as MOX fuel from the viewpoint of nuclear characteristics. Therefore, it is mixed with normal uranium fuel mainly containing UO 2. Be loaded.

【0003】MOX燃料が上記ウラン燃料と混在した場
合には、ウラン燃料からの熱中性子流入によって、境界
となる燃料集合体の外周部、特にコーナー部で出力ピー
キングが上昇するため、現在では、上記燃料集合体を構
成するMOX燃料棒のPu富化度を3種類製造し、上記
外周部やコーナー部のPu富化度を低くしている。
When the MOX fuel is mixed with the uranium fuel, thermal neutron inflow from the uranium fuel increases the output peaking at the outer peripheral portion of the fuel assembly as a boundary, particularly at the corner portion. Three types of Pu enrichment of the MOX fuel rods constituting the fuel assembly are manufactured to reduce the Pu enrichment of the outer peripheral portion and the corner portion.

【0004】例えば現状の一例としては、図4に示す通
りであり、燃料集合体の各コーナー部とこれに隣接する
外周部の1本ずつの燃料棒に、低富化度の0.2 wt%
2 3 5U+3wt%Puf燃料棒4を配設し、残る外周部
とその1列内側のコーナー部付近ならびに制御棒案内シ
ンブルの外側に、中富化度の0.2 wt% 2 3 5U+4wt%
Puf燃料棒1を配設している。そして、残りの中心部
に高富化度の0.2 wt% 2 35U+7wt%Puf燃料棒2
を配設している。
For example, as an example of the current situation, it is as shown in FIG. 4, and a low enrichment of 0.2 wt% is applied to each of the fuel rods at the corners of the fuel assembly and the outer peripheral portion adjacent thereto.
2 3 5 disposed U + 3 wt% Puf fuel rods 4, the outside of the corner portion of the outer peripheral portion remaining with its one column inside and control rod guide thimbles, 0.2 wt% of Nakatomi degree 2 3 5 U + 4 wt%
A Puf fuel rod 1 is arranged. Then, 0.2 wt% 2 35 U + 7 wt% Puf fuel rod 2 with high enrichment is formed in the remaining central portion.
Is arranged.

【0005】なお、ここでいうPufの%とは、核分裂
性のPuのみのパーセンテージであり、核分裂性を有さ
ないPuもこの数値には表れていないが幾分かは混入す
る。
The percentage of Puf referred to here is the percentage of Pu that is fissile only, and Pu that does not have fissile properties is also not shown in this figure, but some is mixed.

【0006】[0006]

【発明が解決しようとする課題】しかしながら、上記従
来のMOX燃料集合体では、上記3種類の富化度のMO
X燃料棒を製造しなければならないことから、燃料成形
加工のコストが高くなるという問題を有している。
However, in the above-mentioned conventional MOX fuel assembly, MO of the above three types of enrichment is used.
Since X fuel rods must be manufactured, there is a problem in that the cost of fuel forming processing becomes high.

【0007】本発明は叙上の如き実状に対処し、一部の
燃料棒とその配置に新規な構成を見出すことにより、前
記出力ピーキングを従来と同等に抑制しながら、しかも
燃料集合体全体としてのPu装荷量をほとんど減らすこ
となく、前記MOX燃料棒の種類を削減し上記燃料成形
加工のコストダウンを図ることを目的とするものであ
る。
The present invention copes with the above-mentioned actual situation, and by finding a novel structure in some fuel rods and their arrangement, the output peaking is suppressed to the same level as the conventional one, and the fuel assembly as a whole is suppressed. The purpose of the present invention is to reduce the number of types of the MOX fuel rods and to reduce the cost of the fuel forming process without substantially reducing the Pu loading amount.

【0008】[0008]

【課題を解決するための手段】すなわち、上記本発明の
MOX燃料集合体の特徴は、核分裂性Puを含有するM
OX燃料棒を集束してなるPWR用MOX燃料集合体に
おいて、燃料集合体の各コーナー部を除く外周部に一定
Pu富化度のMOX燃料棒を配設すると共に、上記燃料
集合体の中心部に、上記外周部燃料棒より高い一定Pu
富化度のMOX燃料棒を配設し、かつ前記各コーナー部
に夫々、ガドリニアを含有するウラン燃料棒を配設した
ところにある。
That is, the feature of the MOX fuel assembly of the present invention is that it contains M containing fissile Pu.
In a MOX fuel assembly for PWR formed by focusing OX fuel rods, MOX fuel rods having a constant Pu enrichment are arranged in the outer peripheral portion of the fuel assembly except for each corner portion, and the central portion of the fuel assembly is also provided. And a constant Pu higher than the outer peripheral fuel rods
MOX fuel rods having a high degree of enrichment are provided, and uranium fuel rods containing gadolinia are provided at the respective corners.

【0009】[0009]

【作用】上記本発明のMOX燃料集合体では、従来の3
富化度のMOX燃料棒を2種類にすると共に、出力ピー
キング抑制のために各コーナー部の計4本を中性子吸収
作用のあるガドリニアの入った燃料棒としている。
In the above MOX fuel assembly of the present invention, the conventional 3
There are two types of enriched MOX fuel rods, and in order to suppress output peaking, a total of four fuel rods with gadolinia that absorb neutrons are used at each corner.

【0010】すなわち、本発明では上記の如き構成によ
って、燃料集合体の出力ピーキングを従来と同等に抑制
しながら、しかも集合体全体としての核分裂性Pu装荷
量をほとんど減らすことなく、上記MOX燃料棒の種類
を上記2種に削減し燃料成形加工のコストを低減するこ
とが可能である。
That is, according to the present invention, the MOX fuel rod has the above-mentioned structure while suppressing the output peaking of the fuel assembly to the same level as the conventional one, and at the same time, substantially reducing the fissile Pu loading of the entire assembly. It is possible to reduce the number of types to the above two types and reduce the cost of fuel forming processing.

【0011】[0011]

【実施例】以下、さらに添付図面を参照して、本発明の
実施例を説明する。
Embodiments of the present invention will be described below with reference to the accompanying drawings.

【0012】図1は本発明実施例の17×17配列のP
WR用MOX燃料集合体における燃料棒の配置を示す平
面図であり、この燃料集合体は、核分裂性Puを含有す
るMOX燃料棒を4つのコーナー部を除いて概略正方行
列に集束し、外周部よりも中心部により高い富化度のM
OX燃料棒を配設している。
FIG. 1 shows a 17 × 17 array P of the embodiment of the present invention.
FIG. 3 is a plan view showing the arrangement of fuel rods in a WR MOX fuel assembly, in which the MOX fuel rods containing fissile Pu are converged into a substantially square matrix except for the four corner portions, and the outer peripheral portion is formed. Higher enrichment M in the center than
An OX fuel rod is provided.

【0013】そして、本発明実施例では、かかるMOX
燃料集合体において、上記4つの各コーナー部を除く外
周部と、外周の制御棒案内シンブルの外側とに、中富化
度の0.2 wt% 2 3 5U+4wt%Puf燃料棒1を配設す
ると共に、上記燃料集合体の残る中心部に高富化度の0.
2 wt% 2 3 5U+7wt%Puf燃料棒2を配設し、かつ
前記各コーナー部に夫々、2.6 wt% 2 3 5U+6wt%G
2 3 燃料棒3を配設している。
In the embodiment of the present invention, the MOX
In the fuel assembly, a medium enrichment degree of 0.2 wt% 2 35 U + 4 wt% Puf fuel rod 1 is arranged on the outer peripheral portion excluding the above four corner portions and on the outer side of the outer peripheral control rod guide thimble. High enrichment of 0 in the remaining center of the fuel assembly.
Disposed to 2 wt% 2 3 5 U + 7wt% Puf fuel rods 2, and respectively to said each corner, 2.6 wt% 2 3 5 U + 6wt% G
A d 2 O 3 fuel rod 3 is provided.

【0014】しかして、上記本発明実施例のMOX燃料
集合体と、図4に示した前記従来のMOX燃料集合体と
の無限増倍率の比較を図2に示し、また図3に同、ロー
カルピーキングの比較を示す。
A comparison of the infinite multiplication factors of the MOX fuel assembly according to the embodiment of the present invention and the conventional MOX fuel assembly shown in FIG. 4 is shown in FIG. 2 and also in FIG. A comparison of peaking is shown.

【0015】その結果は下記表1にも示す通りであり、
本発明と従来例とは各燃焼度においてほぼ同等で、ま
た、0GWd/tでのローカルピーキングが低減するこ
とにより装荷パターンの自由度が増し、ウラン燃料と混
在した場合でも、上記従来の3富化度と同等にローカル
ピーキングが抑制される。
The results are also shown in Table 1 below.
The present invention and the conventional example are almost the same in each burnup, and the degree of freedom of the loading pattern is increased by reducing the local peaking at 0 GWd / t. Local peaking is suppressed to the same degree as the degree of chemical conversion.

【0016】[0016]

【表1】 [Table 1]

【0017】さらに、上記本発明実施例と従来例の各燃
料集合体において、集合体1体あたりの核分裂性Pu装
荷量は、本発明実施例が従来例に比較し約1%減少する
のみである。
Further, in each of the fuel assemblies of the embodiment of the present invention and the conventional example, the fissile Pu loading amount per assembly is only reduced by about 1% in the embodiment of the present invention as compared with the conventional example. is there.

【0018】すなわち、本発明実施例では上述のよう
に、燃料集合体の出力ピーキングを従来と同等に抑制し
ながら、しかも集合体全体としての核分裂性Pu装荷量
をほとんど減らすことなく、上記MOX燃料棒の種類を
特に従来と同じ汎用の2種に削減し、燃料成形加工のコ
ストを大幅に低減することが可能である。
That is, in the embodiment of the present invention, as described above, the output peaking of the fuel assembly is suppressed to the same level as in the conventional case, and the fissionable Pu loading of the entire assembly is hardly reduced, and the MOX fuel is produced. It is possible to reduce the types of rods to two types of general-purpose, which are the same as the conventional ones, and to significantly reduce the cost of fuel molding.

【0019】[0019]

【発明の効果】以上説明したように、本発明のPWR用
MOX燃料集合体は、燃料集合体の各コーナー部を除く
外周部に一定Pu富化度のMOX燃料棒を配設すると共
に、上記燃料集合体の中心部に、上記外周部燃料棒より
高い一定Pu富化度のMOX燃料棒を配設し、かつ前記
各コーナー部に夫々、ガドリニアを含有するウラン燃料
棒を配設したものであり、燃料集合体の出力ピーキング
を従来と同等に抑制しながら、しかも集合体全体として
の核分裂性Pu装荷量をほとんど減らすことなく、MO
X燃料棒の種類を従来の3富化度から2種に削減し、燃
料成形加工のコストを低減するとの顕著な効果を有する
ものである。
As described above, in the MOX fuel assembly for PWR according to the present invention, MOX fuel rods having a constant Pu enrichment degree are arranged in the outer peripheral portion of the fuel assembly excluding each corner portion. A MOX fuel rod having a constant Pu enrichment higher than that of the outer peripheral fuel rods is arranged at the center of the fuel assembly, and a uranium fuel rod containing gadolinia is arranged at each of the corners. Yes, the output peaking of the fuel assembly is suppressed to the same level as that of the conventional one, and the fissionable Pu loading of the entire assembly is hardly reduced.
This has a remarkable effect of reducing the number of types of X fuel rods from the conventional 3 enrichment to 2 and reducing the cost of fuel forming processing.

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

【図1】本発明実施例の17×17配列のPWR用MO
X燃料集合体における燃料棒の配置を示す平面図であ
る。
FIG. 1 is a 17 × 17 array MO for PWR according to an embodiment of the present invention.
FIG. 6 is a plan view showing the arrangement of fuel rods in an X fuel assembly.

【図2】本発明実施例のMOX燃料集合体と従来のMO
X燃料集合体の無限増倍率を比較したグラフである。
FIG. 2 is a MOX fuel assembly according to an embodiment of the present invention and a conventional MO.
6 is a graph comparing infinite multiplication factors of X fuel assemblies.

【図3】本発明実施例のMOX燃料集合体と従来のMO
X燃料集合体のローカルピーキングを比較したグラフで
ある。
FIG. 3 is a MOX fuel assembly according to an embodiment of the present invention and a conventional MO.
7 is a graph comparing local peaking of X fuel assemblies.

【図4】従来の17×17配列のPWR用MOX燃料集
合体における燃料棒の配置を示す平面図である。
FIG. 4 is a plan view showing an arrangement of fuel rods in a conventional 17 × 17 array MOX fuel assembly for PWR.

【符号の説明】[Explanation of symbols]

1 中富化度燃料棒 2 高富化度燃料棒 3 ガドリニア入りウラン燃料棒 4 低富化度燃料棒 1 Medium enrichment fuel rods 2 High enrichment fuel rods 3 Uranium fuel rods with gadolinia 4 Low enrichment fuel rods

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】 核分裂性Puを含有するMOX燃料棒を
集束してなるPWR用MOX燃料集合体において、燃料
集合体の各コーナー部を除く外周部に一定Pu富化度の
MOX燃料棒を配設すると共に、上記燃料集合体の中心
部に、上記外周部燃料棒より高い一定Pu富化度のMO
X燃料棒を配設し、かつ前記各コーナー部に夫々、ガド
リニアを含有するウラン燃料棒を配設したことを特徴と
するPWR用MOX燃料集合体。
1. A MOX fuel assembly for a PWR, which is formed by focusing MOX fuel rods containing fissionable Pu, wherein MOX fuel rods having a constant Pu enrichment are arranged at the outer peripheral portion of each fuel assembly except for each corner portion. In addition, at the center of the fuel assembly, a MO having a constant Pu enrichment higher than that of the outer peripheral fuel rods is installed.
An MOX fuel assembly for a PWR, characterized in that X fuel rods are provided, and uranium fuel rods containing gadolinia are provided at the respective corners.
JP6228777A 1994-08-29 1994-08-29 Mox fuel assembly for pwr Withdrawn JPH0868886A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP6228777A JPH0868886A (en) 1994-08-29 1994-08-29 Mox fuel assembly for pwr

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP6228777A JPH0868886A (en) 1994-08-29 1994-08-29 Mox fuel assembly for pwr

Publications (1)

Publication Number Publication Date
JPH0868886A true JPH0868886A (en) 1996-03-12

Family

ID=16881688

Family Applications (1)

Application Number Title Priority Date Filing Date
JP6228777A Withdrawn JPH0868886A (en) 1994-08-29 1994-08-29 Mox fuel assembly for pwr

Country Status (1)

Country Link
JP (1) JPH0868886A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2005004167A1 (en) * 2003-06-30 2005-01-13 Nuclear Fuel Industries, Ltd. Mox fuel assembly for pressurized water reactor
JP2008170454A (en) * 2008-03-24 2008-07-24 Nuclear Fuel Ind Ltd MOX fuel assemblies for pressurized water reactors
JP2013501234A (en) * 2009-08-06 2013-01-10 アレバ・エヌペ Plutonium-How to operate a pressurized water reactor to reach an equilibrium cycle

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2005004167A1 (en) * 2003-06-30 2005-01-13 Nuclear Fuel Industries, Ltd. Mox fuel assembly for pressurized water reactor
EP1650767A4 (en) * 2003-06-30 2011-05-25 Nuclear Fuel Ind Ltd MOX COMBUSTIBLE ASSEMBLY AND PRESSURIZED WATER REACTOR
JP2008170454A (en) * 2008-03-24 2008-07-24 Nuclear Fuel Ind Ltd MOX fuel assemblies for pressurized water reactors
JP2013501234A (en) * 2009-08-06 2013-01-10 アレバ・エヌペ Plutonium-How to operate a pressurized water reactor to reach an equilibrium cycle

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