JPS58140673A - Fuel assembly - Google Patents

Fuel assembly

Info

Publication number
JPS58140673A
JPS58140673A JP57022683A JP2268382A JPS58140673A JP S58140673 A JPS58140673 A JP S58140673A JP 57022683 A JP57022683 A JP 57022683A JP 2268382 A JP2268382 A JP 2268382A JP S58140673 A JPS58140673 A JP S58140673A
Authority
JP
Japan
Prior art keywords
fuel
fuel assembly
combustion
reactivity
gadolinia
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.)
Pending
Application number
JP57022683A
Other languages
Japanese (ja)
Inventor
律夫 吉岡
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
Tokyo Shibaura Electric Co 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP57022683A priority Critical patent/JPS58140673A/en
Publication of JPS58140673A publication Critical patent/JPS58140673A/en
Pending 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

  • Fuel-Injection Apparatus (AREA)

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 〔発明の技術分野〕 本発明は漣騰水形原子炉(BWR)の燃料集合体に関す
る。
DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a fuel assembly for a Benteng Water Reactor (BWR).

〔発明の技術的背景〕[Technical background of the invention]

881図に従来のBWRの燃料集合体の水平断面wAt
示す。燃料棒lが8行8列に並び、水が貫流できるジル
カロイ製の中空管からなる1〜2本の9ji−タ・ロッ
ド2會含んでいる。燃料棒lはスペーサー(1示せず)
により束ねられておル、周囲を四角筒状のチャンネルボ
ックス3によ)囲マれている。又チャンネルボックス3
の外側を十字型の制御棒4が必要に応じ、挿入されてい
る。通常の燃料棒1はジルカロイ製の被覆管の中に、U
O,ペレットが封入されている。更に、燃燐初期の余剰
反応W、を抑制する為に、可燃性毒物として数チのガド
リニア(GdlOs )をUO,中に混入し、UO,−
Gd、O,とした燃料ペレットをジルカロイ被覆゛gに
封入したガドリニア入シ燃料棒5が数本(第1図では8
本ありWで示されている。)用いられている。Gd1O
,中のGd (ガドリニウム)ハ、天然のものが用いら
れ、その組成は下内己の表のとおりである。
Figure 881 shows a horizontal cross section wAt of a conventional BWR fuel assembly.
show. The fuel rods are arranged in 8 rows and 8 columns and include 1 or 2 9jita rods each consisting of a hollow tube made of Zircaloy through which water can flow. Fuel rod l is a spacer (1 not shown)
They are bundled together and surrounded by a rectangular cylindrical channel box 3). Also channel box 3
A cross-shaped control rod 4 is inserted into the outside of the control rod 4 as required. A normal fuel rod 1 is placed inside a Zircaloy cladding tube.
O, pellets are enclosed. Furthermore, in order to suppress the excess reaction W at the initial stage of phosphorus combustion, several tons of gadolinia (GdlOs) as a burnable poison were mixed into UO, and UO,-
There are several gadolinia-filled fuel rods 5 (8 in Fig.
There is a book and it is indicated by W. ) is used. Gd1O
, Gd (gadolinium) is a natural substance, and its composition is as shown in the table below.

これらのGd同位体のうち、中性子吸収断面積(#、)
の大きいのはGd−155とGd−157で、各々61
000バーン、240000バーンとな−pている。G
dが可燃性毒物として利用されるのは、Gd−155゜
Gd−157の2つの同位体が非常に大きいσ1を持っ
ておシ、燃焼初期の燃料の余剰反応度をおさえるととも
に、中性子吸収にょシGd−155→Gd−156゜G
d−157→Gd−158へと変換し、生成後のGd 
−156、Gd−158の#、が小さい為、燃焼末期で
は、中性子を無駄食いするのが少ないからである。(G
d−156,Gd−158のσ1は数バーン程度である
。)〔背景技術の問題点〕 所が、近年、燃料の経済性向丘の為に、燃料のU−23
58411度が増加し、また、原子炉の長期間運転と相
まって、余剰反応度が一段と大きくなシ、これを抑える
為、Gd人シ燃料棒本数及びGd濃度が増加する傾向に
ある。この為、燃焼末期におけるGd−156,Gd−
158等の中性子の無駄食いは、無視できなくな9つつ
ある。
Among these Gd isotopes, the neutron absorption cross section (#,)
Gd-155 and Gd-157 have the highest values, each with 61
There are 000 burns and 240000 burns. G
The reason why d is used as a burnable poison is that the two isotopes Gd-155 and Gd-157 have very large σ1, which suppresses the excess reactivity of the fuel at the initial stage of combustion and prevents neutron absorption. Gd-155→Gd-156゜G
Converting from d-157 to Gd-158, the generated Gd
-156 and Gd-158 are small, so fewer neutrons are wasted in the final stage of combustion. (G
σ1 of d-156 and Gd-158 is about several burns. ) [Problems with the background technology] However, in recent years, due to the economical nature of fuel, U-23 fuel
58,411 degrees Celsius, and combined with the long-term operation of the nuclear reactor, the surplus reactivity is further increasing.In order to suppress this, the number of Gd fuel rods and the Gd concentration tend to increase. For this reason, Gd-156, Gd-
The wasteful consumption of neutrons of magnitude 158 is becoming impossible to ignore.

爾2図に、Gdt−全く含まなVk燃料集合体と、5−
のGd、0.を混入したUO,−Gd、0.燃料棒t8
8本有る燃料集合体のKoO(無限増倍率)を比較して
示しである。燃焼末期、例えば20GWD/T の時点
で19bΔに以との差があることが判る。この差は燃料
費にするとlO優にもな9、大きな損失となっている。
Figure 2 shows a Vk fuel assembly containing no Gdt, and 5-
Gd of 0. UO, -Gd mixed with 0. fuel rod t8
This is a comparison of the KoO (infinite multiplication factor) of eight fuel assemblies. It can be seen that there is a difference in 19bΔ at the end of combustion, for example at 20GWD/T. In terms of fuel costs, this difference amounts to 100%, which is a huge loss.

ところで第2図におけるKooO!(1%ΔK)の内訳
けt−調べて見ると、前述のGd−156、Gd−15
8の中性子吸収による反応度損失もさることながら、実
はGd−155−) Ga−156→Gd−157と、
連鎖的に生成したGd−157がわずかに残り、4IL
量ではあってもσ、が巨大である為、このGd−157
による反応度損失への寄与が最も大きいことが判明した
By the way, KooO! in Figure 2! (1%ΔK) Breakdown t- Looking at the above-mentioned Gd-156, Gd-15
In addition to the reactivity loss due to neutron absorption of 8, in fact, Gd-155-) Ga-156 → Gd-157,
A small amount of Gd-157 generated in a chain remains, and 4IL
Although it is a large amount, σ is huge, so this Gd-157
was found to have the largest contribution to reactivity loss.

〔発明の目的〕[Purpose of the invention]

本発明は、を記の事情に1みてなされたもので(ト)−
155及びGd−156からのGd−157生成量を従
来よシ減少させる事によ〕、燃焼末期のGdによる中性
子の無駄負い、即ち反応度損失を防止することを目的と
する。
The present invention has been made in view of the following circumstances.
By reducing the amount of Gd-157 produced from Gd-155 and Gd-156 compared to the conventional method, the purpose is to prevent wasted neutrons due to Gd at the final stage of combustion, that is, reactivity loss.

〔発明の1!要〕 本発明は、Gd−157を濃縮した―工燃性毒物を含有
する燃料集合体にある。
[Invention 1! [Summary] The present invention resides in a fuel assembly containing an industrial fuel poison enriched with Gd-157.

〔発明の実施例〕[Embodiments of the invention]

外的形状は、従来(第1図)と岡じであシ、iトリニア
入夛燃料棒5に、ガドリニア(Gd*Os )数Sを含
有したUO,ベレットが封入きれている。
The external shape is the same as that of the conventional one (FIG. 1); the fuel rod 5 containing i-trinia is filled with UO and pellets containing the number S of gadolinia (Gd*Os).

本発明の特徴は、このガドリニア中のGdの同位体組成
比が天然のもの(第1表)と異なり、Gd−157を主
なる成分としていることである。天然のものでは、Gd
−157の組成比は16%でちるが、この比率が高い方
が本発明の効果が大きく、例えば50〜90−程度とす
ることが好ましい。Gd の同位体組成比が変化し、G
d−157e主なる成分としていても、ガドリニアの物
性値、例えば熱伝導率中UO,との両立性などは、天然
のものを用いていた時と変らない。但し、Ga−157
のσ1は240000パーンと大きいので、Gd2O3
のUO2への混入量はGd−157の存在割合に応じ、
多少、減少させる必要がある。
The feature of the present invention is that the isotopic composition ratio of Gd in this gadolinia is different from that of the natural one (Table 1), and that Gd-157 is the main component. In natural products, Gd
The composition ratio of -157 is set at 16%, but the higher the ratio, the greater the effect of the present invention, and it is preferable to set it to about 50 to 90, for example. The isotopic composition ratio of Gd changes, and G
Even if it is used as the main component of d-157e, the physical properties of gadolinia, such as thermal conductivity and compatibility with UO, are the same as when natural ones are used. However, Ga-157
Since σ1 of is as large as 240,000 Pans, Gd2O3
The amount of mixed into UO2 depends on the existence ratio of Gd-157,
It needs to be reduced somewhat.

〔発明の作用〕[Action of the invention]

本発明の燃料集合体中のガドリニア入り燃料−において
は、Gd−157t−主たる成分とするGdが用いられ
ている。
In the gadolinia-containing fuel in the fuel assembly of the present invention, Gd-157t-Gd is used as the main component.

Gd−157の中性子吸収断面積(6a ’) ti 
240,000バーンと十分、大きいので、中性子吸収
能力は十分であり、燃焼初期の反応度制御能力は十分で
あ少。Gd−157は中性子を吸収し、Gd−158に
転換していくが、Gd−158の吸収断面積は数バーン
と非常に小さいので、燃焼末期では、中性子はGdに殆
んど吸収されない。
Neutron absorption cross section of Gd-157 (6a') ti
Since it is sufficiently large at 240,000 burns, the neutron absorption capacity is sufficient, and the reactivity control capacity at the initial stage of combustion is sufficient. Gd-157 absorbs neutrons and converts them into Gd-158, but since the absorption cross section of Gd-158 is very small, only a few burns, at the final stage of combustion, almost no neutrons are absorbed by Gd.

#I3図に:Gd−157tはぼ100 %とLりGd
tOst。
#I3 diagram: Gd-157t is almost 100% and L is Gd
tOst.

UO,中に1%含有させた燃料棒を8本有する燃料集合
体の)(oo(無限増倍率)を示す。
)(oo (infinite multiplication factor)) of a fuel assembly having eight fuel rods containing 1% UO.

従来の天然Gdの一合と比べると、燃焼末期、例えばZ
OGWT)/T以降で1−Δに近く、反応度が高いこと
が判る。
Compared to the conventional combination of natural Gd, at the end of combustion, for example, Z
It can be seen that the reactivity is close to 1-Δ after OGWT)/T, and the reactivity is high.

なお、を述の例では、Uo!に混入するGd、0.の量
Yr115にへらせるので、燃料の熱伝導率がUO。
In addition, in the example mentioned above, Uo! Gd mixed in, 0. Since the amount of Yr is reduced to 115, the thermal conductivity of the fuel is UO.

のみの時と殆んど変らず、従来の見られ友Gd、O。It's almost the same as when it was only, Gd, O.

の混入による熱伝導率の悪化が緩和でき、燃料健食性の
肉とにもなっている。
The deterioration in thermal conductivity caused by the contamination of the meat can be alleviated, making it a healthy meat to eat as a fuel.

〔発明の効果〕〔Effect of the invention〕

本発明の燃料集合体では、燃焼初期では十分反応度が低
く、従来のGd入り燃料なみに抑えられておシ、一方、
燃焼末期ではGd同位体、特に従来微量に生成されてい
たGd−157の中性子吸収が防止され、中性子の無駄
食い、即ち反応度損失が防止できる。
In the fuel assembly of the present invention, the reactivity is sufficiently low at the early stage of combustion and can be suppressed to the level of conventional Gd-containing fuel.
At the final stage of combustion, neutron absorption of Gd isotopes, particularly Gd-157, which has conventionally been produced in trace amounts, is prevented, and wasteful consumption of neutrons, that is, loss of reactivity, can be prevented.

J:述の実施例では、反応度で1チΔに1即ち燃料費で
1091Gの向とがはかれ効果は大きい。また、Gd!
O,o混入量を減らすことができ、Gd、0.混入によ
る燃料の熱伝導率の悪化が緩和できる。
J: In the above-described embodiment, the reactivity is 1 in 1 inch Δ, that is, the fuel cost is 1091 G, and the effect is large. Also, Gd!
The amount of O, O mixed can be reduced, and Gd, 0. Deterioration of thermal conductivity of fuel due to contamination can be alleviated.

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

第1@は従来の燃料集合体の概略水平断面図、籐2図は
従来の燃料集合体のKoo(無限増倍率)の燃焼特性図
、第3図は本発明の燃料集合体のKoo(無限増倍率)
の燃焼特性図である。
Figure 1 is a schematic horizontal cross-sectional view of a conventional fuel assembly, Figure 2 is a Koo (infinite multiplication factor) combustion characteristic diagram of the conventional fuel assembly, and Figure 3 is a Koo (infinite multiplication factor) combustion characteristic diagram of the fuel assembly of the present invention. (multiplication factor)
FIG.

Claims (2)

【特許請求の範囲】[Claims] (1)  Gd−157を1111したGd會言有する
ことを特徴とする燃料集合体。
(1) A fuel assembly characterized by having a Gd ratio of 1111 compared to Gd-157.
(2)  k記濃縮されたGd は、燃料棒に収納され
ていることt−特徴とする特許請求の範囲第1項記載の
燃料集合体。
(2) The fuel assembly according to claim 1, wherein the enriched Gd is housed in a fuel rod.
JP57022683A 1982-02-17 1982-02-17 Fuel assembly Pending JPS58140673A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP57022683A JPS58140673A (en) 1982-02-17 1982-02-17 Fuel assembly

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP57022683A JPS58140673A (en) 1982-02-17 1982-02-17 Fuel assembly

Publications (1)

Publication Number Publication Date
JPS58140673A true JPS58140673A (en) 1983-08-20

Family

ID=12089657

Family Applications (1)

Application Number Title Priority Date Filing Date
JP57022683A Pending JPS58140673A (en) 1982-02-17 1982-02-17 Fuel assembly

Country Status (1)

Country Link
JP (1) JPS58140673A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5524033A (en) * 1993-05-18 1996-06-04 Kabushiki Kaisha Toshiba Nuclear fuel containing gadolinium
EP1093129A1 (en) * 1999-10-14 2001-04-18 Kabushiki Kaisha Toshiba Fuel assembly and nuclear reactor
JP2002148379A (en) * 2000-10-19 2002-05-22 Westinghouse Atom Ab Nuclear reactor first core

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5524033A (en) * 1993-05-18 1996-06-04 Kabushiki Kaisha Toshiba Nuclear fuel containing gadolinium
EP1093129A1 (en) * 1999-10-14 2001-04-18 Kabushiki Kaisha Toshiba Fuel assembly and nuclear reactor
US6445759B1 (en) 1999-10-14 2002-09-03 Kabushiki Kaisha Toshiba Fuel assembly and nuclear reactor
JP2002148379A (en) * 2000-10-19 2002-05-22 Westinghouse Atom Ab Nuclear reactor first core

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