JPS5847676B2 - Genshiroyounenriyoyouso - Google Patents
GenshiroyounenriyoyousoInfo
- Publication number
- JPS5847676B2 JPS5847676B2 JP50100568A JP10056875A JPS5847676B2 JP S5847676 B2 JPS5847676 B2 JP S5847676B2 JP 50100568 A JP50100568 A JP 50100568A JP 10056875 A JP10056875 A JP 10056875A JP S5847676 B2 JPS5847676 B2 JP S5847676B2
- Authority
- JP
- Japan
- Prior art keywords
- coolant
- fuel rods
- tubes
- annular
- orifices
- 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
Links
- 239000002826 coolant Substances 0.000 claims description 41
- 239000000446 fuel Substances 0.000 claims description 24
- 239000003758 nuclear fuel Substances 0.000 claims description 12
- 230000002093 peripheral effect Effects 0.000 claims description 12
- 239000006185 dispersion Substances 0.000 description 16
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 4
- 238000001816 cooling Methods 0.000 description 4
- 241000239290 Araneae Species 0.000 description 1
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- 238000013459 approach Methods 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 238000005452 bending Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 229910002804 graphite Inorganic materials 0.000 description 1
- 239000010439 graphite Substances 0.000 description 1
- JEGUKCSWCFPDGT-UHFFFAOYSA-N h2o hydrate Chemical compound O.O JEGUKCSWCFPDGT-UHFFFAOYSA-N 0.000 description 1
- 238000002347 injection Methods 0.000 description 1
- 239000007924 injection Substances 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 239000007921 spray Substances 0.000 description 1
- 230000000153 supplemental effect Effects 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/322—Means to influence the coolant flow through or around the bundles
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は、冷却材として軽水又は重水が使用される原子
炉用燃料要素組立体に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a fuel element assembly for a nuclear reactor in which light water or heavy water is used as a coolant.
燃料要素組立体の普通の形態では、核燃料棒はクラスタ
にして支持され、横グリッドによって間隔をへだてられ
、その結果、燃料棒の間の空間が副流路を形成し、原子
炉の主冷却材は燃料棒の長さ方向軸線と平行な方向にこ
の副流路を通る。In a common configuration of fuel element assemblies, nuclear fuel rods are supported in clusters and spaced apart by transverse grids, so that the spaces between the fuel rods form secondary flow passages and carry the reactor's main coolant. passes through this secondary channel in a direction parallel to the longitudinal axis of the fuel rod.
補助冷却のために、燃料棒のクラスタの中に補助冷却用
導管を置くことがこれまでに提案されている。It has previously been proposed to place auxiliary cooling conduits within clusters of fuel rods for auxiliary cooling.
これらの導管は多孔分散管であり、孔の明いた側壁およ
び塞がった一端を有し、その結果冷却材源との連結で、
補助冷却材の噴霧を、主冷却材の流れ方向と垂直に燃料
棒のクラスタの中へ噴出させる。These conduits are sparge tubes, having perforated side walls and one plugged end, so that in connection with the coolant source,
A spray of auxiliary coolant is injected into the cluster of fuel rods perpendicular to the flow direction of the main coolant.
本発明によれば、原子炉用燃料要素組立体は燃料棒のク
ラスタを有し、このクラスタは縦軸線のまわりの対称的
な多数の格子位置に環状列をなして支えられ、端が開放
し前記縦軸線と同軸である周囲壁を有し、燃料棒の間の
間隔は、燃料棒間に主冷却材の流れ道の作用をする副流
路が作られるように定められる。In accordance with the present invention, a fuel element assembly for a nuclear reactor has a cluster of fuel rods supported in an annular array at a number of symmetrical grid positions about a longitudinal axis and having open ends. The fuel rods have a peripheral wall coaxial with the longitudinal axis, and the spacing between the fuel rods is such that secondary channels are created between the fuel rods that act as flow paths for the main coolant.
副流路は相連結して燃料棒の環状列の間の多数の環状通
路およびこの環状通路と交わる多数の半径方向通路を形
戊する。The sub-channels interconnect to form a number of annular passages between the annular rows of fuel rods and a number of radial passages intersecting the annular passages.
原子炉用燃料組立体は、クラスタの中に補助冷却材を噴
出するための多数の多孔分散管を有し、多孔分散管の1
つは前記縦軸線と合致し(この多孔分散管を中央分散管
と呼ぶことにする)、残りの多孔分散管は補助冷却を効
果的に行なわしめるために共通の環状通路上の周囲位置
に配置される(この多孔分散管を周囲分散管と呼ぶこと
にする)。A nuclear reactor fuel assembly has a number of sparge tubes for injecting auxiliary coolant into the cluster, one of the sparge tubes being one of the sparge tubes.
One of the sparge tubes coincides with the longitudinal axis (this sparger tube will be referred to as the central sparger tube), and the remaining sparger tubes are arranged at peripheral positions on a common annular passage for effective auxiliary cooling. (This porous dispersion tube will be referred to as the peripheral dispersion tube).
前記残りの環状通路のうちの少なくとも幾つかは周囲壁
に冷却材を向けるような方向の補助冷却材噴出孔を有し
、これによって周囲壁を効果的に冷却することができる
。At least some of the remaining annular passages have auxiliary coolant orifices oriented to direct coolant toward the surrounding wall, thereby effectively cooling the surrounding wall.
周囲分散管の補助冷却材噴出孔は、すべての分散管に共
通した多数の軸線位置に間隔をあけて配置され、どのレ
ベルにおいても隣接する多孔分散管の孔が交互に周囲壁
の方に、又その分散管を通る半径方向に対して傾斜して
向けられ、されによって補助冷却材の一様な噴出を保証
する。The auxiliary coolant orifices of the peripheral distribution tubes are spaced at a number of axial positions common to all distribution tubes, with the holes of adjacent distribution tubes at any level alternating toward the peripheral wall. It is also oriented obliquely to the radial direction through the distribution tube, thereby ensuring uniform jetting of the auxiliary coolant.
周囲壁は熱溜めの作用をする金属チューブの形態をした
ものでもよく、このチューブは幾つかの周囲分散管から
チューブに向けて噴出された冷却材によって冷却される
。The surrounding wall may be in the form of a metal tube acting as a heat sink, which tube is cooled by coolant jetted towards it from several surrounding distribution tubes.
周知のように、クラスタをなす核燃料棒を、これが通る
多数のセルを有するグリッドを用いて位置決めするのが
普通のやり方である。As is well known, it is common practice to position clusters of nuclear fuel rods using a grid having a number of cells through which they pass.
本発明では、分散管の孔の軸方向間隔をグリッドの間隔
に関して決めるのが有利であり、噴出孔をグリッドに隣
接して位置決めし、これにより燃料棒の冷しにくい熱ス
ポットの可能性を減少させる。In the present invention, it is advantageous to determine the axial spacing of the holes in the dispersion tube with respect to the spacing of the grid, positioning the orifices adjacent to the grid, thereby reducing the possibility of hard-to-cool hot spots on the fuel rods. let
開放端付管状壁は、その長さ方向軸線と直角な横断面が
円形であっても多角形であっても良く、環状の列をなす
核燃料棒、補助冷却材用の中央分散管および多数の周囲
分散管を包含するクラスタを囲む。The open-ended tubular wall may be circular or polygonal in cross-section perpendicular to its longitudinal axis and has an annular array of nuclear fuel rods, a central distribution tube for auxiliary coolant and a number of Surround the cluster containing the peripheral dispersion tube.
前記周囲分散管は管状壁に最も近い燃料棒の2つの環状
列の間の環状通路の中に設置される。The peripheral distribution tube is installed in an annular passage between the two annular rows of fuel rods closest to the tubular wall.
これらの分散管の噴出孔は、交互に、クラスタの中心を
通る長さ方向軸線から遠ざかる外方に向けられ又軸線に
向って内方に傾むけられる。The orifices of these dispersion tubes are alternately oriented outwardly away from the longitudinal axis passing through the center of the cluster and inwardly oriented toward the axis.
中央に位置せる分散管は、分散管のまわりに3個の噴出
孔を等間隔をなして有し、その相対位置は一方の位置と
次の位置との間では60°ずらされる。The centrally located dispersion tube has three orifices equidistantly spaced around the dispersion tube, the relative positions of which are offset by 60° from one position to the next.
補助冷却材用の中央分散管および周囲分散管の両方とも
噴出孔は好ましくは、多数の共通な軸方向位置即ちレベ
ルに設置される。The orifices of both the central distribution tube and the peripheral distribution tube for the auxiliary coolant are preferably located at a number of common axial locations or levels.
本発明の実施態様を一層完全に理解するために、本発明
を添附図面を参照して説明する。For a more complete understanding of embodiments of the invention, the invention will now be described with reference to the accompanying drawings.
先ず、第1図および第2図を参照すると、核燃料要素組
立体は、横グリッドによって第1組の格子位置で間隔を
へだてた平行状態に支持された核燃料棒2のクラスタ1
からなる。Referring first to FIGS. 1 and 2, a nuclear fuel element assembly includes a cluster 1 of nuclear fuel rods 2 supported in spaced apart parallel configurations at a first set of grid positions by a transverse grid.
Consisting of
上部グリッドは3で、下部グリッドは4で示してある。The top grid is marked 3 and the bottom grid is marked 4.
グリッド3と4の間には、多数の中間グリッドがあり、
そのうちの1つを5で示す。Between grids 3 and 4 there are a number of intermediate grids,
One of them is marked 5.
これらすべてのグリッドには燃料棒2で占められる第1
組の60個の格子位置があり、燃料棒の間の相互空間は
クラスタの軸線に対し同心環状通路および半径方向通路
の形態の副流路6(第2図)を構戊する。All these grids have a first grid occupied by fuel rods 2.
There are a set of 60 grid positions and the mutual spaces between the fuel rods define sub-channels 6 (FIG. 2) in the form of concentric annular passages and radial passages with respect to the axis of the cluster.
第2組の格子位置(本例では7個)は半径方向通路が環
状通路と交わる位置で副流路の或るものと一致し、補助
冷却材用の周囲分散管(導管)7と中央分散管8によっ
て占められる。A second set of grid positions (seven in this example) coincides with some of the secondary channels where the radial passages intersect with the annular passages, with peripheral distribution conduits (conduits) 7 and central distribution for the auxiliary coolant. occupied by tube 8.
分散管7,8はその下端が閉じられ、上端は、運転中補
助冷却材源Sに連結される冷却材マニホルド9と連通ず
る。The distribution tubes 7, 8 are closed at their lower ends and communicate at their upper ends with a coolant manifold 9 which is connected to an auxiliary coolant source S during operation.
分散管7,8はそれらの側壁に一連の孔7a ,8aを
有しているので、供給された冷却材は横方向に噴出され
る。The distribution tubes 7, 8 have a series of holes 7a, 8a in their side walls so that the supplied coolant is ejected laterally.
分散管8の閉鎖端の延長部はスパイダ10を支え、クラ
スクの下端取付部11はそのスパイダに取付けられる。The extension of the closed end of the dispersion tube 8 carries a spider 10 to which the lower end fitting 11 of the clasp is attached.
クラスタは圧力管14の中に吊下げられる。The cluster is suspended in pressure tube 14.
この圧力管は、圧力管原子炉では、大量減速材(例えば
黒鉛又は重水)を通して延びる多数のうちの1つである
。This pressure tube is one of many that run through a bulk moderator (eg graphite or heavy water) in a pressure tube reactor.
理解されるように、燃料棒の主冷却材は圧力管14の一
端から他端まで、クラスタを軸線方向に通る。As will be appreciated, the primary coolant for the fuel rods passes axially through the cluster from one end of the pressure tube 14 to the other.
この例では、圧力管は垂直であり、主冷却材の流れ方向
は矢印Aの方向に上向きである。In this example, the pressure tubes are vertical and the main coolant flow direction is upward in the direction of arrow A.
この主冷却材を補給するために、冷却材源Sで始まる補
助冷却材はマニホルド9に通じ、ここから分散管7,8
の中へ流入する。To replenish this main coolant, the auxiliary coolant starts at a coolant source S and leads to a manifold 9 from where it flows into distribution tubes 7, 8.
flows into the.
この補助冷却材の効果的な使用を保証するために、補助
冷却材噴出孔7a ,8aの特殊な配列がなされる。In order to ensure effective use of this auxiliary coolant, a special arrangement of the auxiliary coolant orifices 7a, 8a is made.
即ち、その配列模様は、クラスタの中の分散管の位置に
よって予め決定される。That is, the arrangement pattern is determined in advance by the position of the dispersion tube within the cluster.
第1には、噴出孔は、クラスタに沿う多数の共通レベル
で軸線方向に設置され、これらレベルは第1図および第
8a図にI■で表わしてある。First, the orifices are located axially at a number of common levels along the cluster, these levels being designated I■ in Figures 1 and 8a.
第2には、任意の1つの分散管の壁にある噴出孔の向き
はどのレベルでもクラスタの中の分散管の位置で決定さ
れる。Second, the orientation of the orifices in the wall of any one distribution tube at any level is determined by the distribution tube's position within the cluster.
第3には、周囲の分散管の噴出孔の少くともいくつかは
補助冷却材を圧力管の壁に直接当る軌道に沿うて差し向
けるべく方向ずけられる。Third, at least some of the orifices of the surrounding dispersion tubes are directed to direct the supplemental coolant along a trajectory directly against the wall of the pressure tube.
第4には、レベルI−[の軸方向位置はクラスタに沿う
温度プロファイル( temperature pro
file)によって決定されるが、普通はグリッド5の
位置に関係する。Fourth, the axial position of level I-[ is determined by the temperature profile along the cluster.
file), but is usually related to the position of grid 5.
補助冷却材用の周囲の分散管にある噴出孔の正しい向き
は、2種類の管(第5図)を持つことによって達成され
る。Correct orientation of the orifices in the peripheral distribution tubes for the auxiliary coolant is achieved by having two types of tubes (FIG. 5).
両種類ともに、噴出孔は、第6a図および第6b図に示
すように、レベルI■で交互に孔明けされる。In both types, the orifices are drilled alternately at level I, as shown in Figures 6a and 6b.
即ち、曲り方向と反対側に一対の孔17(第6b図)に
対して半径方向の孔16の中心を1個(第6a図)明け
る。That is, one hole 16 in the radial direction (FIG. 6a) is opened at the center of the pair of holes 17 (FIG. 6b) on the opposite side to the bending direction.
孔16を通る半径は分散管の曲り部20の方向と180
0の角度をなす。The radius passing through the hole 16 is 180 degrees from the direction of the bend 20 of the distribution tube.
Makes an angle of 0.
一対の孔17の中心を通る半径は曲り部の方向と70〜
85°の間の角度βをなす。The radius passing through the center of the pair of holes 17 is 70~
make an angle β between 85°.
これらの分散管は、噴出孔の模様がレベルi ,i,■
,■,■では第3図に示されている如くになるよう配列
される。These dispersion tubes have orifice patterns of levels i, i, ■
, ■, ■ are arranged as shown in FIG.
噴出孔の模様はレベルI,IV,■および■では第4図
に示されている如くになる。The pattern of the nozzle holes is as shown in FIG. 4 at levels I, IV, ■ and ■.
中央分散管8の噴出孔8aの向きは第7a図に示されて
いる如くであり、平面でみて600交互に変位させてあ
るので、第3図および第4図に示す夫々のレベルでの効
果が達成される。The direction of the ejection holes 8a of the central dispersion tube 8 is as shown in Fig. 7a, and since they are alternately displaced by 600 degrees when viewed from the plane, the effects at the respective levels shown in Figs. 3 and 4 are obtained. is achieved.
レベルI乃至■での孔を通る補助冷却材の噴出に加えて
、レベルXで表わしたクラスクの頂に一組の孔を設ける
のが有利である。In addition to the injection of auxiliary coolant through the holes at levels I to II, it is advantageous to provide a set of holes at the top of the clasp, designated at level X.
レベルXでは、周囲の分散管7は第6C図に示す如く1
200間隔をへだてた孔18を有し、中央分散管8はレ
ベルXでは第7b図に示す如<60°の等間隔をなす6
ヶの噴出孔19を有する。At level X, the surrounding dispersion pipes 7 are 1 as shown in FIG.
At level
It has a number of nozzle holes 19.
中央管8の孔は他のあらゆるレベルI−Nでは120°
の間隔をもっている(第7a図)が、第3図および第4
図に示す如く周囲の分散管の孔に対して位相がずれてい
る。The hole in the central tube 8 is 120° at all other levels I-N.
(Figure 7a), but Figures 3 and 4
As shown in the figure, the phase is shifted with respect to the holes in the surrounding dispersion tubes.
レベルI−■の軸方向位置は好ましくは、中間グリッド
の位置およびクラスタに沿う温度分布によって影響され
る。The axial position of level I-■ is preferably influenced by the position of the intermediate grid and the temperature distribution along the cluster.
第8a図は、補助冷却材用の噴出孔がクラスタに沿うて
位置し、第8b図におけるグリッドの位置および温度分
布に関して正確に位相がずらされたレベルの相対位置を
示す。FIG. 8a shows the relative position of the levels in which the orifices for the auxiliary coolant are located along the cluster and are exactly out of phase with respect to the position of the grid and the temperature distribution in FIG. 8b.
般に、ほとんどのグリッドはグリッドのすぐ上に冷却材
の噴出部を有していることがわかる。In general, it can be seen that most grids have coolant jets just above the grid.
一般には又、各対の隣接したグリッド間にレベルがある
が、温度が最犬に近ずくところでは例外であって、一つ
の対の隣接したグリッド間に位置する2つのレベル■お
よび■で噴出される補助冷却材の噴出を有する。Generally, there is also a level between each pair of adjacent grids, except where the temperature approaches the maximum, erupting at two levels located between a pair of adjacent grids, ■ and ■. It has an auxiliary coolant jet.
第1図は一部を横断面で示した核燃料組立体の一般的な
配列を示す図、第2図は燃料棒の円形格子模様をなす燃
料組立体の一部概略平面図、第3図および第4図は補助
冷却材の相対的な噴出方向を示す図、第5図は補助冷却
材用の1つの周囲分散管の側面図、第6a ,6bおよ
び60図6上900回した第5図の線Via−VIa
, VIb−VlbおよびVIc−VIc“における横
断面図、第7a図および第7b図は、夫々レベルI乃至
■、レベルXにおける補助冷却材用中央分散管の横断面
図、第8a図および第8b図は、補助冷却材の噴出孔が
、燃料棒をクラスタに位置決めする中間グリッドに対し
て置かれるレベルを示す図である。
1・・・・・・クラスタ、2・・・・・・核燃料棒、6
・・・・・・副流路、7・・・・・・周囲分散管、8・
・・・・・中央分散管、7a,8a・・・・・・噴出孔
。FIG. 1 is a partial cross-sectional view showing a general arrangement of a nuclear fuel assembly; FIG. 2 is a partially schematic plan view of a fuel assembly with a circular lattice pattern of fuel rods; FIG. Figure 4 shows the relative jetting direction of the auxiliary coolant; Figure 5 is a side view of one circumferential distribution tube for the auxiliary coolant; Figures 6a, 6b and 60; line Via-VIa
, VIb-Vlb and VIc-VIc", FIGS. 7a and 7b are cross-sectional views of the central distribution tube for auxiliary coolant at levels I to II and level X, FIGS. 8a and 8b, respectively. The figure shows the level at which the auxiliary coolant orifices are placed relative to the intermediate grid that positions the fuel rods in clusters: 1...cluster, 2...nuclear fuel rods. ,6
... Sub-channel, 7 ... Surrounding dispersion pipe, 8.
...Central dispersion tube, 7a, 8a...Blowout hole.
Claims (1)
環状列に並んで支えられた核燃料棒のクラスタを含み、
端が開放し前記縦軸線と同軸の周囲壁を有し、燃料棒の
間の間隔は燃料棒間に主冷却材の流れ道の作用をする副
流路を形戒するように定められ、前記副流路は相連結し
て燃料棒の環状列の間の同心環状通路およびこの環状通
路と交わる半径方向通路を形成し、補助冷却材を前記ク
ラスタの中に噴出するための多数の多孔分散管を有し、
該多孔分散管の1つは前記縦軸線と合致し、残りの多孔
分散管は共通の環状通路上の周囲位置に配置され、前記
残りの多孔分散管のうちの幾つかは冷却材を周囲壁に向
けるような方向の補助冷却材噴出孔を有する核燃料組立
体。 2 周囲位置に配置された前記残りの多孔分散管は補助
冷却材噴出孔を有し、この噴出孔は1つ置きの多孔分散
管が冷却材を周囲壁に向けるように方向付けられている
特許請求の範囲第1項記載の核燃料組立体。Claims: 1. A nuclear fuel rod comprising a cluster of nuclear fuel rods supported in an annular row at a plurality of lattice locations symmetrical about a longitudinal axis;
The fuel rods are open ended and have a peripheral wall coaxial with the longitudinal axis, the spacing between the fuel rods is determined to define a secondary flow path between the fuel rods that acts as a flow path for the main coolant, and The secondary channels interlock to form concentric annular passages between the annular rows of fuel rods and radial passages intersecting the annular passages, and a number of porous sparge tubes for injecting auxiliary coolant into the clusters. has
One of the sparge tubes is aligned with the longitudinal axis, the remaining sparge tubes are arranged in circumferential positions on a common annular passage, and some of the remaining sparge tubes direct the coolant to the surrounding wall. A nuclear fuel assembly having an auxiliary coolant orifice oriented such that it points toward. 2. The remaining sparge tubes arranged at peripheral locations have auxiliary coolant orifices, the orifices being oriented such that every other sparge tube directs the coolant toward the surrounding wall. A nuclear fuel assembly according to claim 1.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| GB36640/74A GB1511494A (en) | 1974-08-20 | 1974-08-20 | Nuclear reactor fuel elements |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5146693A JPS5146693A (en) | 1976-04-21 |
| JPS5847676B2 true JPS5847676B2 (en) | 1983-10-24 |
Family
ID=10389938
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP50100568A Expired JPS5847676B2 (en) | 1974-08-20 | 1975-08-19 | Genshiroyounenriyoyouso |
Country Status (4)
| Country | Link |
|---|---|
| JP (1) | JPS5847676B2 (en) |
| FR (1) | FR2282697A1 (en) |
| GB (1) | GB1511494A (en) |
| IT (1) | IT1041585B (en) |
Families Citing this family (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4225387A (en) * | 1978-03-07 | 1980-09-30 | Nuclear Power Company Limited | Liquid metal cooled past breeder nuclear reactors |
| US4657726A (en) * | 1984-06-22 | 1987-04-14 | Westinghouse Electric Corp. | Moderator control apparatus for a nuclear reactor fuel assembly |
| US4687621A (en) * | 1984-08-06 | 1987-08-18 | Westinghouse Electric Corp. | Nuclear fuel assembly with improved spectral shift-producing rods |
| US4683103A (en) * | 1985-02-12 | 1987-07-28 | Westinghouse Electric Corp. | Spectral shift apparatus and method for a nuclear reactor fuel assembly |
| US4755348A (en) * | 1987-01-12 | 1988-07-05 | General Electric Company | Cooled water rod (LOCA conditions) |
| US5255300A (en) * | 1991-07-30 | 1993-10-19 | Siemens Power Corporation | Fuel assembly for boiling water reactors |
-
1974
- 1974-08-20 GB GB36640/74A patent/GB1511494A/en not_active Expired
-
1975
- 1975-08-19 FR FR7525677A patent/FR2282697A1/en active Granted
- 1975-08-19 JP JP50100568A patent/JPS5847676B2/en not_active Expired
- 1975-08-19 IT IT69107/75A patent/IT1041585B/en active
Also Published As
| Publication number | Publication date |
|---|---|
| GB1511494A (en) | 1978-05-17 |
| FR2282697B1 (en) | 1982-03-26 |
| AU8387475A (en) | 1977-02-17 |
| IT1041585B (en) | 1980-01-10 |
| FR2282697A1 (en) | 1976-03-19 |
| JPS5146693A (en) | 1976-04-21 |
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