JPH0460236B2 - - Google Patents
Info
- Publication number
- JPH0460236B2 JPH0460236B2 JP59002416A JP241684A JPH0460236B2 JP H0460236 B2 JPH0460236 B2 JP H0460236B2 JP 59002416 A JP59002416 A JP 59002416A JP 241684 A JP241684 A JP 241684A JP H0460236 B2 JPH0460236 B2 JP H0460236B2
- Authority
- JP
- Japan
- Prior art keywords
- fuel
- fuel rods
- rods
- gadolinia
- rod
- 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 - Lifetime
Links
- 239000000446 fuel Substances 0.000 claims description 125
- 229910052778 Plutonium Inorganic materials 0.000 claims description 15
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 claims description 15
- 231100000614 poison Toxicity 0.000 claims description 9
- 239000002574 poison Substances 0.000 claims description 8
- CMIHHWBVHJVIGI-UHFFFAOYSA-N gadolinium(iii) oxide Chemical compound [O-2].[O-2].[O-2].[Gd+3].[Gd+3] CMIHHWBVHJVIGI-UHFFFAOYSA-N 0.000 description 64
- 238000004519 manufacturing process Methods 0.000 description 11
- 229910052770 Uranium Inorganic materials 0.000 description 9
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 9
- 230000000712 assembly Effects 0.000 description 8
- 238000000429 assembly Methods 0.000 description 8
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 8
- 238000010586 diagram Methods 0.000 description 3
- 238000000034 method Methods 0.000 description 3
- 230000009257 reactivity Effects 0.000 description 3
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 description 2
- 238000010521 absorption reaction Methods 0.000 description 2
- 238000000465 moulding Methods 0.000 description 2
- 238000001228 spectrum Methods 0.000 description 2
- 229910000439 uranium oxide Inorganic materials 0.000 description 2
- 206010073306 Exposure to radiation Diseases 0.000 description 1
- 230000005262 alpha decay Effects 0.000 description 1
- SHZGCJCMOBCMKK-KGJVWPDLSA-N beta-L-fucose Chemical compound C[C@@H]1O[C@H](O)[C@@H](O)[C@H](O)[C@@H]1O SHZGCJCMOBCMKK-KGJVWPDLSA-N 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 230000007096 poisonous effect Effects 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 239000008234 soft water Substances 0.000 description 1
- 125000006850 spacer group Chemical group 0.000 description 1
- 230000002269 spontaneous effect Effects 0.000 description 1
- JFALSRSLKYAFGM-OIOBTWANSA-N uranium-235 Chemical compound [235U] JFALSRSLKYAFGM-OIOBTWANSA-N 0.000 description 1
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Inert Electrodes (AREA)
Description
【発明の詳細な説明】
〔発明の技術分野〕
本発明は燃料集合体、特にプルトニウムを富化
した燃料棒を有する燃料集合体に係る。TECHNICAL FIELD OF THE INVENTION The present invention relates to fuel assemblies, particularly fuel assemblies having plutonium-enriched fuel rods.
第１図は従来の燃料集合体の斜視図である。こ
の図において、断面方形状のチヤンネルボツクス
１内には、多数の燃料ペレツトを燃料被覆管内に
装填して成る多数の燃料棒２が格子状に配置され
ており、それらの燃料棒は上部タイプレート３、
下部タイプレート４によつて支持されている。ま
た、燃料棒２の中間部はスペーサ５により燃料棒
相互間およびチヤンネルボツクス１との間隔を維
持されている。
FIG. 1 is a perspective view of a conventional fuel assembly. In this figure, a large number of fuel rods 2 each having a large number of fuel pellets loaded into a fuel cladding tube are arranged in a grid in a channel box 1 having a rectangular cross section. 3,
It is supported by a lower tie plate 4. Further, the intermediate portions of the fuel rods 2 are maintained at a distance from each other and from the channel box 1 by spacers 5.
第２図は、濃縮ウランのみを燃料とする従来の
燃料集合体の燃料棒の配置を示す。この図におい
て二重円は燃料棒をあらわし、その中に記入され
た数字１〜７、数字１を最高とし同７を最低とす
るU235の濃縮度、文字Ｗはウオータロツド、文字
Ｇは可燃性毒物であるガドリニアの濃度が１〜８
％のガドリニア燃料棒を示す。すなわち、数字１
は最高濃縮度燃料棒、２は高濃縮度燃料棒、数字
３〜５は中間濃縮度燃料棒、数字６は低濃縮度燃
料棒、数字７は最低濃縮度燃料棒である。なお、
図中CRは制御棒を示す。 FIG. 2 shows the arrangement of fuel rods in a conventional fuel assembly that uses only enriched uranium as fuel. In this figure, the double circles represent fuel rods, the numbers 1 to 7 are written inside them, the enrichment of U 235 is 1 (highest) and 7 (lowest), the letter W is water rod, and the letter G is flammable. The concentration of the poisonous gadolinia is 1 to 8.
% gadolinia fuel rods. i.e. number 1
is the highest enrichment fuel rod, 2 is the high enrichment fuel rod, numbers 3 to 5 are the intermediate enrichment fuel rods, number 6 is the low enrichment fuel rod, and number 7 is the lowest enrichment fuel rod. In addition,
In the figure, CR indicates a control rod.
燃料棒、ウオータロツドの数の和は64本であ
り、２本のウオータロツドＷは、チヤンネルボツ
クス１の制御棒に隣接しない隅角間を連ねる対角
線の中央に並んで配置されている。また最高濃縮
度燃料棒１は、前記対角線上のウオータロツドＷ
の隣の燃料棒配置位置を頂点とする正方形状に計
12本が配置され、高濃縮度燃料棒２は前記正方形
内の２つの燃料棒配置位置および前記正方形に隣
接し各辺の中央に対向するそれぞれ２つの燃料棒
配置位置計10本が配置されている。ガドリニア燃
料棒Ｇは、前記正方形周辺に配置した高濃縮度燃
料にそれぞれ隣接した配置位置に計８本が配置さ
れ、中間濃縮度燃料棒３は、高濃縮度燃料棒２お
よびガドリニア燃料棒Ｇを含む燃料棒の列を辺と
する正方形の頂点に配置されている。最外周の燃
料棒の列は、７，６，５，４，４，５，６，７と
なつている。 The total number of fuel rods and waterrods is 64, and the two waterrods W are arranged in the center of a diagonal line connecting the corners of the channel box 1 that are not adjacent to the control rods. Further, the highest enrichment fuel rod 1 is connected to the water rod W on the diagonal line.
Measured in a square shape with the apex at the fuel rod placement position next to
12 high enrichment fuel rods are arranged, and 10 high enrichment fuel rods 2 are arranged at two fuel rod arrangement positions within the square and two fuel rod arrangement positions adjacent to the square and facing each other in the center of each side. There is. A total of eight gadolinia fuel rods G are arranged at positions adjacent to the high enrichment fuels arranged around the square, and the intermediate enrichment fuel rods 3 connect the high enrichment fuel rods 2 and the gadolinia fuel rods G. It is placed at the apex of a square whose sides are the rows of fuel rods it contains. The outermost rows of fuel rods are 7, 6, 5, 4, 4, 5, 6, 7.
第３図は第２図の燃料集合体と反応度的にはほ
ぼ等価となるよう、プルトニウムを富化した燃料
棒（MOX燃料棒）を使用した燃料集合体の燃料
棒の配置を示す。数字１１〜１６はプルトニウム
の富化度を数字11を最高として示す。最高富化度
燃料棒１１は第２図における最高濃縮度燃料棒１
と同様に配置されている。しかし乍ら、ウオータ
ロツドＷに隣接する配置位置には、プルトニウム
を富化したガドリニア燃料棒Ｇが配置されてい
る。最高富化度燃料棒１１の配置された正方形の
外側の正方形を形成する配置位置には、制御棒
CRのタイロツドに近接した頂点をガドリニア燃
料棒Ｇとして、前記頂点からの二辺に頂点から順
にＧ、12、Ｇ、12、Ｇ、13の燃料棒を配置し、他
の二辺には前記頂点の対頂点から順にＧ、12、
Ｇ、12、Ｇ、13の燃料棒を配置する。最外周の燃
料棒の列は16、15、14、13、13、14、15、16とな
つている。 FIG. 3 shows the fuel rod arrangement of a fuel assembly using plutonium-enriched fuel rods (MOX fuel rods) so that the reactivity is almost equivalent to that of the fuel assembly shown in FIG. 2. Numbers 11 to 16 indicate the plutonium enrichment, with number 11 being the highest. The highest enrichment fuel rod 11 is the highest enrichment fuel rod 1 in FIG.
are arranged similarly. However, in a position adjacent to the water rod W, a plutonium-enriched gadolinia fuel rod G is arranged. Control rods are located at positions forming a square outside the square in which the highest enrichment fuel rods 11 are arranged.
The apex close to the tie rod of CR is the gadolinia fuel rod G, and fuel rods G, 12, G, 12, G, and 13 are arranged in order from the apex on two sides from the apex, and the other two sides are arranged at the apex. In order from the opposite vertex of G, 12,
Place G, 12, G, and 13 fuel rods. The outermost rows of fuel rods are 16, 15, 14, 13, 13, 14, 15, 16.
第２図、第３図からわかるように、MOX燃料
棒を使用した燃料集合体では通常のそれよりも、
ガドリニア燃料棒の本数が多くなつている。 As can be seen from Figures 2 and 3, fuel assemblies using MOX fuel rods have lower
The number of gadolinia fuel rods is increasing.
すなわち、一般にMOX燃料では、UO2燃料に
比し中性子スペクトルが硬いため、ガドリニアの
価値がUO2燃料の場合とかなり異り、ガドリニア
の中性子吸収断面積は熱群中性子エネルギに対し
て大きく勢外に対して小さいので、中性子スペク
トルが硬くなるガドリニアの反応度価値が下り、
同時にガドリニアの燃焼速度が遅くなる。 In other words, in general, MOX fuel has a harder neutron spectrum than UO 2 fuel, so the value of gadolinia is quite different from that of UO 2 fuel, and the neutron absorption cross section of gadolinia is much larger than that of thermal group neutron energy. Since it is smaller than
At the same time, the burning rate of gadolinia slows down.
そこでガドリニアによる反応度制御をUO2燃料
と同様に行うためには、ガドリニア濃度を低く
し、ガドリニア入り燃料棒の本数を多くする必要
がある。 Therefore, in order to control the reactivity using gadolinia in the same way as UO 2 fuel, it is necessary to lower the gadolinia concentration and increase the number of fuel rods containing gadolinia.
そこで、例えば第２図に示すUO2燃料のガドリ
ニアが3w／ｏ×８本であるのに対して、第３図
に示したMOX燃料棒では1.5w／ｏ×12となつて
いる。 Therefore, for example, the gadolinia of the UO 2 fuel shown in Fig. 2 is 3w/o x 8, while the MOX fuel rod shown in Fig. 3 is 1.5w/o x 12.
プルトニウムはα崩壊をするため、人体への内
部被曝を防止する必要があり、また崩壊、自発核
分裂によつて中性子、γ線を放出するため、遮蔽
装置が必要となる。従つて、MOX燃料は完全に
密閉された状態で成型加工することが必要であ
り、成型加工工程、設備等の保守点検について
UO2燃料の場合とは異る配慮を必要とする。 Since plutonium undergoes alpha decay, it is necessary to prevent internal exposure to radiation to the human body, and as plutonium emits neutrons and gamma rays through decay and spontaneous fission, shielding equipment is required. Therefore, it is necessary to mold MOX fuel in a completely sealed state, and maintenance and inspection of the molding process, equipment, etc.
Requires different considerations than for UO 2 fuel.
核燃料製造工場では、ウラン−235濃縮度別、
プルトニウム富化度別、ガドリニア棒の種類別に
製造ラインが設定されるが、ウラン燃料製造の場
合に比し、MOX燃料の製造設備は密閉されてお
り複雑化しているので、著しく高価である。従つ
て、MOX燃料棒の種類を極力少くし、製造ライ
ン数を減じることが望ましい。また、ガドリニア
棒の成型加工では、ガドリニア、酸化ウラン、酸
化プルトニウムの３種類の粉末を取扱うので、工
程、装置は一層複雑高価となる。 At nuclear fuel manufacturing plants, uranium-235 enrichment
Production lines are set up for each plutonium enrichment level and type of gadolinia rod, but compared to uranium fuel production, MOX fuel production equipment is sealed and complex, making it significantly more expensive. Therefore, it is desirable to minimize the types of MOX fuel rods and reduce the number of production lines. Furthermore, in the molding process of gadolinia rods, three types of powders are used: gadolinia, uranium oxide, and plutonium oxide, making the process and equipment more complicated and expensive.
さて、軽水炉用MOX燃料集合体の設計は大別
して、以下の２種類に分けられている。 Now, the design of MOX fuel assemblies for light water reactors can be roughly divided into the following two types.
第一の設計例は燃料集合体の制御棒から離れた
中央部分にMOX燃料（全本数の約1/2以下）を
使用し、外周部はUO2燃料棒を使用するアイラン
ド型設計であり、たとえば特願47−95833（特許公
報昭55−26437）に於て実例が示されている。こ
の場合は多数のUO2燃料棒を使用するため、可燃
性毒物（ガドリニア）をUO2燃料棒にのみ添加さ
せることが可能である。第２の設計例は燃料集合
体あたりのプルトニウム装荷量を極力増すため
に、すべての燃料棒にMOX燃料棒を使用するデ
イスクリート型設計である。この場合は、可燃性
毒物を含む燃料棒としてMOX燃料棒が使用され
ている。第３図に示したものはこれに含まれる。
また第１と第２の中間の設計意として、一部の燃
料棒としてUO2燃料棒を使用した設計も考えられ
ている。 The first design example is an island type design that uses MOX fuel (approximately 1/2 or less of the total number) in the central part of the fuel assembly away from the control rods, and uses UO 2 fuel rods in the outer periphery. For example, an example is shown in Japanese Patent Application No. 47-95833 (Patent Publication No. 55-26437). In this case, since a large number of UO 2 fuel rods are used, it is possible to add burnable poison (gadolinia) only to the UO 2 fuel rods. The second design example is a discrete design that uses MOX fuel rods for all fuel rods to maximize the plutonium loading per fuel assembly. In this case, MOX fuel rods are used as fuel rods containing burnable poisons. This includes what is shown in Figure 3.
Also, as an intermediate design between the first and second designs, a design using UO 2 fuel rods as some of the fuel rods is also being considered.
本発明は上記第２の設計のデイスクリート型設
計に関連する。 The present invention relates to the discrete design of the second design described above.
本発明はMOX燃料棒の種類数を減じることが
でき、可燃性毒物を含む燃料棒を密閉下で製造す
る必要のない燃料集合体を得ることを目的として
いる。
An object of the present invention is to obtain a fuel assembly that can reduce the number of types of MOX fuel rods and eliminates the need to manufacture fuel rods containing burnable poison under closed conditions.
本発明の燃料集合体は、プルトニウムを富化し
た燃料棒および可燃性毒物を添加した燃料棒を正
方形の格子状に配置したものにおいて、可燃性毒
物を添加した燃料棒にはプルトニウムを含まない
ものとし、且つ水ギヤツプ近傍に配置したことを
特徴とする。
The fuel assembly of the present invention is one in which plutonium-enriched fuel rods and fuel rods doped with a burnable poison are arranged in a square grid, where the fuel rods doped with a burnable poison do not contain plutonium. It is characterized by being placed near the water gap.
第３図に示した従来型のMOX燃料集合体に於
て単にガドリニア棒にプルトニウムを含ませない
場合、製造工程はより簡単化されることになる。
In the conventional MOX fuel assembly shown in FIG. 3, the manufacturing process would be simpler if the gadolinia rods did not contain plutonium.
本発明では、ガドリニア棒配置を工夫すること
により、更にMOX燃料棒種類を減して、製造コ
スト低下が達成できる。 In the present invention, by devising the arrangement of gadolinia rods, the types of MOX fuel rods can be further reduced, and manufacturing costs can be reduced.
第４図は本発明の一実施例を示す。この図中数
字１８〜２０は１８を最高として番号順にプルト
ニウムの富化度を示す。また、Ｇは3.0w／ｏ濃
縮度のウランに2.5w／ｏのガドリニアを含むガ
ドリニア棒、Ｗはウオータロツドを示す。この実
施例では、燃料棒配置位置の外側から２列目を辺
とする正方形の各頂点を除き、最高富化度の燃料
棒１８が配置され、前記各頂点には中富化度の燃
料棒１９が配置されている。また、最外側の列の
なす正方形の頂点には最低富化度の燃料棒２０
が、それに隣接した配置位置にはガドリニア棒Ｇ
がそれぞれ配置され、他の位置には中富化度の燃
料棒１９が配置されている。 FIG. 4 shows an embodiment of the present invention. In this figure, numbers 18 to 20 indicate the enrichment of plutonium in numerical order, with 18 being the highest. Further, G indicates a gadolinia rod containing 2.5 w/o of gadolinia in uranium enriched to 3.0 w/o, and W indicates a water rod. In this embodiment, the highest enrichment fuel rods 18 are arranged except for the vertices of a square whose sides are the second row from the outside of the fuel rod arrangement position, and the middle enrichment fuel rods 19 are arranged at each of the vertices. is located. In addition, the lowest enrichment fuel rods 20 are placed at the vertices of the square formed by the outermost row.
However, the gadolinia rod G is placed adjacent to it.
are arranged respectively, and medium enrichment fuel rods 19 are arranged at other positions.
上記構成の本発明にあつては、ガドリニア棒Ｇ
が中性子スペクトルの軟い水ギヤツプに沿つた位
置に配置されているため、ガドリニア棒１本当り
の中性子吸収量が増加し、第２図に示したウラン
燃料集合体の場合と同程度のガドリニア反応度を
得ることができる。さらに、水ギヤツプ周辺に生
ずる局所出力ピーキングが抑制されるので、
MOX燃料棒の種類を減じ、ガドリニア棒の本数
を減じることができる。 In the present invention having the above configuration, the gadolinia rod G
is located along the soft water gap of the neutron spectrum, the amount of neutron absorption per gadolinia rod increases, and the gadolinia reaction is similar to that in the case of the uranium fuel assembly shown in Figure 2. degree can be obtained. Furthermore, local output peaking that occurs around the water gap is suppressed, so
It is possible to reduce the number of gadolinia rods by reducing the types of MOX fuel rods.
この実施例では、第３図に示した燃料集合体に
比し、MOX燃料棒の種類数は３減少させること
ができるし、ガドリニア棒の本数は４減少させる
ことができる。 In this embodiment, compared to the fuel assembly shown in FIG. 3, the number of types of MOX fuel rods can be reduced by three, and the number of gadolinia rods can be reduced by four.
第５図は燃料集合体の無限増倍率と燃焼度との
関係を示し、この図中曲線Ａは第２図のウラン燃
料集合体、同Ｂは第３図のMOX燃料集合体、同
Ｃは第４図の実施例のMOX燃料集合体を示す。 Figure 5 shows the relationship between the infinite multiplication factor and burnup of a fuel assembly. In this figure, curve A is for the uranium fuel assembly in Figure 2, curve B is for the MOX fuel assembly in Figure 3, and curve C is for the MOX fuel assembly in Figure 3. The MOX fuel assembly of the embodiment of FIG. 4 is shown.
この図から本発明によるMOX燃料集合体は、
ウラン燃料集合体に近い反応度特性を示すことが
わかる。 From this figure, the MOX fuel assembly according to the present invention is
It can be seen that the reactivity characteristics are similar to those of uranium fuel assemblies.
また、燃料集合体の局所出力ピーキングと燃焼
度との関係を第６図に示す。曲線Ａ〜Ｃは第５図
と同様第２図、第３図、第４図の燃料集合体を示
す。この図から、本発明の燃料集合体において
は、MOX燃料棒の種類数を減じ乍ら、ウラン燃
料の局所出力ピーキングと同程度となることがわ
かる。 Further, FIG. 6 shows the relationship between local power peaking and burnup of the fuel assembly. Curves A to C represent the fuel assemblies of FIGS. 2, 3, and 4 as well as FIG. 5. This figure shows that in the fuel assembly of the present invention, although the number of types of MOX fuel rods is reduced, the local power peaking is comparable to that of uranium fuel.
なお、本発明は上記実施例のみに限定されな
い。例えば、水ギヤツプ近傍に位置するコーナ部
の最低富化度のMOX燃料棒を酸化ウラン燃料棒
と置換えて、MOX燃料棒を２種類としてもよい
し、コーナ部および最外周のMOX燃料棒を酸化
ウラン燃料棒と置換えてMOX燃料棒を１種類と
してもよい。 Note that the present invention is not limited to the above embodiments. For example, the lowest enrichment MOX fuel rods in the corners near the water gap may be replaced with uranium oxide fuel rods, resulting in two types of MOX fuel rods, or the corner and outermost MOX fuel rods may be oxidized. One type of MOX fuel rod may be used instead of the uranium fuel rod.
上記から明らかなように、ガドリニア燃料棒の
配置、MOX燃料棒の配置を適切に選定すること
により、ガドリニア燃料棒の母材をウランのみと
しても差支えなくその本数も少くてよい。また
MOX燃料棒の種類も少くてすむ。従つて、ガド
リニア燃料棒の製造工程、装置は簡素化され、
MOX燃料棒の製造ラインも減じることができ、
燃料集合体の製造コストを著しく削減することが
できる。
As is clear from the above, by appropriately selecting the arrangement of the gadolinia fuel rods and the arrangement of the MOX fuel rods, it is possible to use only uranium as the base material of the gadolinia fuel rods, and the number of gadolinia fuel rods can be reduced. Also
Fewer types of MOX fuel rods are required. Therefore, the manufacturing process and equipment for gadolinia fuel rods are simplified,
The production line for MOX fuel rods can also be reduced.
The manufacturing cost of fuel assemblies can be significantly reduced.
第１図は燃料集合体の一部を切除して示す斜視
図、第２図、第３図はそれぞれ従来の燃料集合体
の模式的断面図、第４図は本発明一実施例の模式
的断面図、第５図は燃焼度と無限増倍率の関係を
示す線図、第６図は燃焼度と局所出力ピーキング
の関係を示す線図である。
１……チヤンネルボツクス、２……燃料棒。
FIG. 1 is a partially cut away perspective view of a fuel assembly, FIGS. 2 and 3 are schematic sectional views of conventional fuel assemblies, and FIG. 4 is a schematic diagram of an embodiment of the present invention. A cross-sectional view, FIG. 5 is a diagram showing the relationship between burnup and infinite multiplication factor, and FIG. 6 is a diagram showing the relationship between burnup and local power peaking. 1...Channel boxes, 2...Fuel rods.
Claims (1)
毒物を添加した燃料棒を正方形の格子状に配置し
たものにおいて、可燃性毒物を添加した燃料棒に
はプルトニウムを含まないものとし、且つ水ギヤ
ツプ近傍に配置したことを特徴とする燃料集合
体。1. Fuel rods enriched with plutonium and fuel rods doped with burnable poisons are arranged in a square grid, and the fuel rods doped with burnable poisons do not contain plutonium, and the fuel rods dotted with burnable poisons do not contain plutonium. A fuel assembly characterized in that:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59002416A JPS60146185A (en) | 1984-01-10 | 1984-01-10 | Fuel aggregate |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59002416A JPS60146185A (en) | 1984-01-10 | 1984-01-10 | Fuel aggregate |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS60146185A JPS60146185A (en) | 1985-08-01 |
| JPH0460236B2 true JPH0460236B2 (en) | 1992-09-25 |
Family
ID=11528641
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59002416A Granted JPS60146185A (en) | 1984-01-10 | 1984-01-10 | Fuel aggregate |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60146185A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP3419997B2 (en) * | 1996-06-26 | 2003-06-23 | 株式会社日立製作所 | Method of manufacturing fuel assembly and channel box for fuel assembly |
-
1984
- 1984-01-10 JP JP59002416A patent/JPS60146185A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS60146185A (en) | 1985-08-01 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| EXPY | Cancellation because of completion of term |