Deprecated: The each() function is deprecated. This message will be suppressed on further calls in /home/zhenxiangba/zhenxiangba.com/public_html/phproxy-improved-master/index.php on line 456
JPS6250796B2 - - Google Patents
[go: Go Back, main page]

JPS6250796B2 - - Google Patents

Info

Publication number
JPS6250796B2
JPS6250796B2 JP54045204A JP4520479A JPS6250796B2 JP S6250796 B2 JPS6250796 B2 JP S6250796B2 JP 54045204 A JP54045204 A JP 54045204A JP 4520479 A JP4520479 A JP 4520479A JP S6250796 B2 JPS6250796 B2 JP S6250796B2
Authority
JP
Japan
Prior art keywords
yoke
legs
fast breeder
downwardly extending
breeder reactor
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
Application number
JP54045204A
Other languages
Japanese (ja)
Other versions
JPS54140079A (en
Inventor
Shiido Jofurii
Chesuwaasu Gurahamu
Richaado Hindo Jon
Hotsujison Donarudo
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 Power Co Ltd
Original Assignee
Nuclear Power 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 Nuclear Power Co Ltd filed Critical Nuclear Power Co Ltd
Publication of JPS54140079A publication Critical patent/JPS54140079A/en
Publication of JPS6250796B2 publication Critical patent/JPS6250796B2/ja
Granted legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/02Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
    • G21C1/03Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a coolant not essentially pressurised, e.g. pool-type reactors
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C13/00Pressure vessels; Containment vessels; Containment in general
    • G21C13/02Details
    • G21C13/024Supporting constructions for pressure vessels or containment vessels
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C5/00Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02Details
    • G21C5/10Means for supporting the complete structure
    • 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

  • 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)
  • Butt Welding And Welding Of Specific Article (AREA)

Description

【発明の詳細な説明】 本発明は、プール式の液体金属冷却型高速増殖
炉構造体に係る。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a pool type liquid metal cooled fast breeder reactor structure.

プール式の液体金属冷却型高速増殖炉構造体
は、1次容器内の液体金属冷却材のプールに沈め
られた核燃料集合体を備え、1次容器は収容室の
屋根構造体から懸架される。現存のプール式の液
体金属冷却型高速増殖炉は比較的小型のものであ
り、例えばスコツトランドのドーンレイ
(Dounreay)にある原形高速炉(PFR)として知
られている構造体は600MW(t)の出力を発生
する。このPFRの燃料集合体は一連の結合体に
よつて屋根構造体から支持されるが、新たに提案
された或る構造設計では、燃料集合体が1次容器
の壁から支持される。1300MW(t)原子炉につ
いての本出願人の特願昭52−96518号には、この
種の典型的な構造体が開示されており、燃料集合
体はスカートによつて1次容器の壁から堅固な底
部に支持される。1次容器及び堅固な底部はオー
ステナイト性のステンレススチールで製造され、
そして1次容器の場合には冷却材のプール及び燃
料集合体の重量により生じる死重を受け、且つ堅
固な底部の場合には燃料集合体の重量により生じ
る死重をを受ける。又、1次容器及び堅固な底部
は圧力負荷及び温度勾配の作用も受ける。更に、
これら構造体の溶接部も溶接工程により生ずる内
部ストレスを受ける。温度及び照射作用によつて
オーステナイト性金属の破砕強さ特性に変化が生
じるので、溶接部に小さな欠陥があつても急速に
クラツクを伝搬して構成成分の破滅的な障害を招
くことがあると懸念されている。このような欠陥
の大きさ及び進行速度は、定期的な検査によつて
障害の始まりを検出する従来型の手段ではオース
テナイト性のステンレススチール構造体の完全性
を充分に確保できないことを示唆している。それ
故、燃料集合体と屋根構造体との間の主荷重ライ
ンの部分を形成する構造体が少なくとも或る程度
の損傷に耐えるような別の設計原理を用いねばな
らないと考えられる。この原理が本発明の基礎を
構成する。
A pool liquid metal cooled fast breeder reactor structure includes a nuclear fuel assembly submerged in a pool of liquid metal coolant within a primary vessel, which is suspended from a containment chamber roof structure. Existing pool-type liquid metal cooled fast breeder reactors are relatively small; for example, the structure known as the prototype fast reactor (PFR) at Dounreay in Scotland has a power output of 600 MW (t). occurs. Although the PFR fuel assemblies are supported from the roof structure by a series of ties, one newly proposed structural design supports the fuel assemblies from the walls of the primary vessel. A typical structure of this type is disclosed in the applicant's Japanese Patent Application No. 52-96518 for a 1300 MW (t) nuclear reactor, in which the fuel assembly is separated from the wall of the primary vessel by a skirt. Supported by a solid bottom. The primary vessel and solid bottom are made of austenitic stainless steel;
In the case of a primary vessel, it receives the dead weight caused by the coolant pool and the weight of the fuel assembly, and in the case of a solid bottom, it takes the dead weight caused by the weight of the fuel assembly. The primary vessel and solid bottom are also subject to pressure loads and temperature gradients. Furthermore,
Welds in these structures are also subject to internal stresses caused by the welding process. Temperature and radiation effects alter the fracture strength properties of austenitic metals, so even small defects in welds can rapidly propagate through cracks and cause catastrophic failure of the components. There are concerns. The size and rate of progression of these defects suggests that conventional means of detecting the onset of failure through periodic inspection are insufficient to ensure the integrity of austenitic stainless steel structures. There is. Therefore, it is believed that other design principles must be used such that the structures forming part of the primary load line between the fuel assembly and the roof structure are resistant to at least some damage. This principle forms the basis of the invention.

本発明によれば、プール式の液体金属冷却型高
速増殖炉構造体に於いて、1次容器は弧状セグメ
ントで形成された環状ヨークを合体し、このヨー
クは1次容器の外部に配置された第1の環状の一
連の結合ストラツプによつて収容室の屋根構造体
から懸架され、一方1次容器の内部で燃料集合体
がのせられる堅固な底部は第2の一連の結合スト
ラツプによつてヨークから支持され、ヨークは上
方及び下方に延びたレツグを有し、これらレツグ
は1次容器の上部及び下部外板によつて各々延び
ている。本発明は、収容室の屋根構造体と1次容
器及び堅固な底部との間の主荷重ラインにある溶
接部が不連続であり従つて溶接部にクラツクが生
じても損傷を1つの結合ストラツプに限定してし
まうように結合ストラツプを取り付けるという耐
損傷設計原理に基くものである。これらのストラ
ツプはその荷重が常時監視されそしてその障害を
容易に検出できる。溶接部のクラツクによつて2
つ或いはそれ以上のストラツプが同時に損傷を受
けることはまづあり得ないが、重大な事態になる
まで多数のストラツプへのクラツク損傷に耐え得
るように設計安全係数を考慮しておく。
According to the present invention, in a pool type liquid metal cooled fast breeder reactor structure, the primary vessel incorporates an annular yoke formed of arcuate segments, and this yoke is disposed outside the primary vessel. It is suspended from the roof structure of the containment chamber by a first annular series of tie straps, while the solid bottom on which the fuel assembly rests inside the primary vessel is yoke by a second series of tie straps. The yoke has upwardly and downwardly extending legs which are respectively extended by the upper and lower skins of the primary container. The present invention provides that the welds in the primary load line between the containment roof structure and the primary vessel and solid bottom are discontinuous and that any cracks in the welds will be prevented by one connecting strap. It is based on the damage-resistant design principle of attaching the connecting straps so that they are limited to These straps have their loads constantly monitored and failures easily detected. 2 due to cracks in welds
Although it is unlikely that one or more straps will be damaged at the same time, a design factor of safety should be considered to withstand crack damage to multiple straps until a critical event occurs.

好ましい構造に於いては、ヨークの弧状セグメ
ントが“K”字型断面の鍛造体又は押出体であ
り、そしてヨークは上方に延びた垂直レツグに固
定された結合ストラツプによつて収容室の屋根構
造体から懸架され、そして堅固な底部は下方に延
びた傾斜レツグに固定された結合ストラツプによ
つて支持され、一方下方に延びた垂直レツグ及び
上方に延びた傾斜レツグは各々1次容器の下部及
び上部外板に固定される。
In a preferred construction, the arcuate segments of the yoke are forgings or extrusions of "K" cross-section, and the yoke is connected to the roof structure of the containment chamber by means of tie straps secured to upwardly extending vertical legs. The bottom, which is suspended from the body and is rigid, is supported by tie straps secured to downwardly extending slanted legs, while downwardly extending vertical legs and upwardly extending slanted legs are respectively attached to the lower and upper portions of the primary container. Fixed to the upper skin.

本発明によるプール式の液体金属冷却型高速増
殖炉の構造を1例として添付図面を参照して以下
に説明する。
The structure of a pool type liquid metal cooled fast breeder reactor according to the present invention will be described below as an example with reference to the accompanying drawings.

第1図はプール式の液体金属冷却型高速増殖炉
を示しており、これは1次容器3内の液体ナトリ
ウム冷却材のプール2に沈められた燃料集合体1
を有している。1次容器はその上部が開いてお
り、そして収容室4の屋根から懸架され、そして
複数個の冷却材ポンプ5と熱交換器6とが設けれ
ている。添付図面には冷却材ポンプ及び熱交換器
が1つづつしか示されていない。ダイヤグリツド
7aに装着されそして堅固な底部7によつて支持
された燃料集合体1は熱交換器と共に内部タンク
8に収容され、一方ダイヤグリツドに冷却材を送
るポンプ5はこの内部タンク8の外部に配置され
る。燃料集合体1は複数個の副集合体より成り、
これらの副集合体は至近離間されて横に並んだ配
列体としてダイヤグリツドから直立し、そして燃
料集合体は中性子シールド9によつて包囲され
る。制御棒10及び計装11が収容室の屋根を貫
通している。
FIG. 1 shows a pool type liquid metal cooled fast breeder reactor consisting of fuel assemblies 1 submerged in a pool 2 of liquid sodium coolant in a primary vessel 3.
have. The primary container has an open top, is suspended from the roof of the storage chamber 4, and is provided with a plurality of coolant pumps 5 and heat exchangers 6. Only one coolant pump and one heat exchanger are shown in the accompanying drawings. The fuel assembly 1 mounted on the grid 7a and supported by a solid bottom 7 is housed together with the heat exchanger in an internal tank 8, while the pump 5 for delivering coolant to the grid is located outside this internal tank 8. be done. The fuel assembly 1 consists of a plurality of sub-assemblies,
These subassemblies stand upright from the diamond in a closely spaced side-by-side array, and the fuel assembly is surrounded by a neutron shield 9. Control rods 10 and instrumentation 11 penetrate the roof of the containment chamber.

原子炉の運転中、ポンプ5により炉心タンクの
外部のプール領域から引き入れられた比較的冷た
い冷却材は、ダイヤグリツド7aにより燃料集合
体と熱交換状態でこの燃料集合体を通つて上方に
送られ、そして熱交換器6を通つてプールの外側
領域へと放出されて戻される。2次冷却材が収容
室の外部からプールの冷却材と熱交換状態で熱交
換器を通して流れるようにされそして蒸気発生装
置(図示せず)へと送られる。
During operation of the reactor, relatively cool coolant drawn from a pool area outside the core tank by the pumps 5 is directed upwardly through the fuel assembly in heat exchange with the fuel assembly by the diamond grid 7a; It is then discharged back to the outer area of the pool through the heat exchanger 6. A secondary coolant is caused to flow from outside the containment chamber in heat exchange with the pool coolant through a heat exchanger and to a steam generator (not shown).

1次容器3は第2図及び3図に詳細に示された
弧状セグメントから作られた環状ヨーク12を合
体しており、このヨークは1次容器の外部に配置
された第1の環状になつた一連の結合ストラツプ
14によつて収容室の屋根構造体から懸架され
る。燃料集合体及び堅固な底部は第2の一連の結
合ストラツプ15によつてヨークから支持され
る。ヨークは上方及び下方に延びたレツグを有
し、これらレツグは各々1次容器の上部及び下部
外板によつて延びている。さて第2図及び3図を
参照すれば、ヨークは鍛造又は押出成形されたK
字型区分の弧状セグメント13で構成されること
が明らかであり、これらセグメントは参照番号1
6で示したように端と端とでもつて突合せ溶接さ
れる。K字型区分の上方に延びた垂直レツグ17
は狭間付けされた上縁18を有し、結合ストラツ
プ14の端がその突出部に突合せ溶接される。下
方に延びた傾斜レツグ19はその下縁21に於い
て狭間付けされ、結合ストラツプ15の端がその
突出部に突合せ溶接される。K字型区分の下方に
延びた垂直レツグ22は厚みが次第に薄くなる下
部プレート23,24によつて延び、これらプレ
ートは多数のセグメントに亘つて長さ方向に延び
そしてこれらプレートには1次容器の半球状の底
領域25が取り付けられる。K字型区分の上方に
傾斜したレツグ26はプレート27,28によつ
て延び、これらプレートは山形断面の中間部材2
9と共に多数のセグメントに亘つて長さ方向に延
び、そして1次容器の垂直に向いた上部外板30
がプレート28に溶接される。大きな荷重を支え
るレツグ17,19は、溶接さるべき物質の厚み
を減少するため第2図及び3図に参照番号20で
示された様に隣接セグメントの対応レツグとの衝
接が軽減される。
The primary container 3 incorporates an annular yoke 12 made of arcuate segments shown in detail in FIGS. 2 and 3, which yoke forms a first annular structure located outside the primary container. It is suspended from the containment chamber roof structure by a series of tie straps 14. The fuel assembly and rigid bottom are supported from the yoke by a second series of tie straps 15. The yoke has upwardly and downwardly extending legs which are respectively extended by the upper and lower skins of the primary container. Now referring to Figures 2 and 3, the yoke is a forged or extruded K
It can be seen that it is composed of arcuate segments 13 of the letter-shaped section, these segments having the reference numeral 1
As shown in 6, the ends are also butt welded. Vertical leg 17 extending above the K-shaped section
has a tapered upper edge 18 to which the end of the connecting strap 14 is butt welded. The downwardly extending beveled leg 19 is wedged at its lower edge 21 and the end of the connecting strap 15 is butt welded to its protrusion. The downwardly extending vertical leg 22 of the K-shaped section is extended by lower plates 23, 24 of decreasing thickness, which extend longitudinally over a number of segments and which include a primary container. A hemispherical bottom area 25 is attached. The upwardly sloping legs 26 of the K-shaped section are extended by plates 27, 28, which are connected to the intermediate member 2 of chevron-shaped cross section.
a vertically oriented upper skin 30 of the primary container extending longitudinally over a number of segments with 9;
is welded to plate 28. Legs 17, 19, which carry large loads, are reduced in impact with corresponding legs of adjacent segments, as indicated by reference numeral 20 in FIGS. 2 and 3, to reduce the thickness of the material to be welded.

以上に述べた構造に於いては、燃料集合体及び
堅固な底部の大きな荷重が結合ストラツプ14,
15及びヨーク12によつて収容室の屋根構造体
から支持される。この荷重の経路は、結合ストラ
ツプ14,15とK字型区分のレツグ17及び1
9との間の端溶接部の様な間欠的な溶接部を含む
だけであり、従つて溶接部のクラツクが伝搬した
場合でも欠陥部の広がりは1つのストラツプに限
定される。1次容器のその他の継ぎ目溶接部や、
ヨークと1次容器の外板との溶接部は、連続的な
性質のものであるが、比較的軽い荷重しかかゝら
ず、重要な溶接ラインを構成するものではない。
In the construction described above, the large loads of the fuel assembly and solid bottom are transferred to the connecting straps 14,
15 and yoke 12 from the roof structure of the containment chamber. The path of this load is between the connecting straps 14, 15 and the legs 17 and 1 of the K-shaped section.
It only includes intermittent welds, such as the end welds between the straps 9 and 9, so that even if a crack in the weld propagates, the spread of the defect is limited to one strap. Other seam welds of the primary container,
Although the weld between the yoke and the primary vessel skin is continuous in nature, it is relatively lightly loaded and does not constitute a significant weld line.

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

第1図は本発明による液体金属冷却型高速増殖
炉の断面図、第2図は1次容器の内面の部分図、
そして第3図は1次容器の外面の部分図である。 1……燃料集合体、2……液体ナトリウム冷却
材のプール、3……1次容器、4……収容室、5
……冷却材ポンプ、6……熱交換器、7a……ダ
イヤグリツド、7……堅固な底部、8……内部タ
ンク、9……中性子シールド、10……制御棒、
12……環状ヨーク、13……弧状セグメント、
14,15……結合ストラツプ、17……上方に
延びた垂直レツグ、19……下方に延びた傾斜レ
ツグ、22……下方に延びた垂直レツグ、23,
24……下部プレート、25……1次容器の半球
状の底領域、26……上方に傾斜したレツグ、2
7,28……プレート、29……中間部材。
FIG. 1 is a sectional view of a liquid metal cooled fast breeder reactor according to the present invention, FIG. 2 is a partial view of the inner surface of the primary vessel,
FIG. 3 is a partial view of the outer surface of the primary container. 1...Fuel assembly, 2...Liquid sodium coolant pool, 3...Primary container, 4...Accommodation chamber, 5
...coolant pump, 6 ... heat exchanger, 7a ... diamond grid, 7 ... solid bottom, 8 ... internal tank, 9 ... neutron shield, 10 ... control rod,
12... annular yoke, 13... arcuate segment,
14, 15... Connecting strap, 17... Vertical leg extending upward, 19... Inclined leg extending downward, 22... Vertical leg extending downward, 23,
24... lower plate, 25... hemispherical bottom area of the primary container, 26... upwardly sloping legs, 2
7, 28... plate, 29... intermediate member.

Claims (1)

【特許請求の範囲】 1 コンクリートの収容室と、 上記収容室内に収容される液体アルカリ金属冷
却材のプールを含む1次容器と、 上記1次容器内にあり、核燃料集合体を支持す
る堅固な底部と、 上記冷却材のプールに沈められそして上記堅固
な底部によつて支持される核燃料集合体とを備
え、 上記1次容器は弧状セグメントから作られた環
状ヨークを合体し、このヨークは上記1次容器の
外部に配置された第1の環状の一連の結合ストラ
ツプによつて上記収容室の屋根構造体から懸架さ
れ、一方上記堅固な底部は第2の一連の結合スト
ラツプによつて上記ヨークから支持され、上記ヨ
ークは上方及び下方に延びたレツグを有し、これ
らレツグは1次容器の上部及び下部外板によつて
各々延びるようにされることを特徴とする液体金
属冷却型高速増殖炉構造体。 2 上記ヨークの弧状セグメントはK字型断面の
ものであり、上記ヨークはその上方に延びた垂直
レツグに固定された結合ストラツプによつて上記
収容室の屋根構造体から懸架され、上記堅固な底
部は下方に延びた傾斜レツグに固定された結合ス
トラツプによつて支持され、そして下方に延びた
垂直レツグ及び上方に延びた傾斜レツグは各々上
記1次容器の上部及び下部外板に固定される特許
請求の範囲第1項記載の高速増殖炉構造体。 3 上記ヨークの弧状セグメントの上方に延びた
垂直レツグ及び下方に延びた傾斜レツグの自由端
には狭間が付けられ、そしてその突出端に結合ス
トラツプの端が突合せ溶接される特許請求の範囲
第2項記載の高速増殖炉構造体。 4 上記弧状セグメントの上方に延びた垂直レツ
グ及び下方に延びた傾斜レツグは隣接セグメント
の対応レツグとの衝接触が軽減される特許請求の
範囲第3項記載の高速増殖炉構造体。 5 上記ヨークの上記弧状セグメントが鍛造体で
ある特許請求の範囲第4項記載の高速増殖炉構造
体。 6 上記ヨークの上記弧状セグメントが押出体で
ある特許請求の範囲第4項記載の高速増殖炉構造
体。
[Scope of Claims] 1. A concrete containment chamber; a primary vessel containing a pool of liquid alkali metal coolant contained within the containment chamber; and a nuclear fuel assembly submerged in the pool of coolant and supported by the solid bottom, the primary vessel incorporating an annular yoke made of arcuate segments, the yoke comprising: Suspended from the roof structure of the containment chamber by a first annular series of bonding straps located on the exterior of the primary vessel, while the rigid bottom is suspended from the yoke by a second series of bonding straps. a liquid metal cooled fast breeder, wherein the yoke has upwardly and downwardly extending legs, the legs being respectively extended by the upper and lower skins of the primary vessel. Furnace structure. 2 The arcuate segments of the yoke are of K-shaped cross-section, and the yoke is suspended from the roof structure of the containment chamber by means of tie straps fixed to vertical legs extending above the yoke and connected to the solid bottom of the yoke. is supported by a connecting strap secured to a downwardly extending sloping leg, and a downwardly extending vertical leg and an upwardly extending sloping leg are respectively secured to the upper and lower skins of the primary container. A fast breeder reactor structure according to claim 1. 3. The free ends of the upwardly extending vertical leg and the downwardly extending sloping leg of the yoke arcuate segment are slotted and the ends of the connecting straps are butt welded to their projecting ends. Fast breeder reactor structure described in Section 1. 4. The fast breeder reactor structure according to claim 3, wherein the upwardly extending vertical legs and the downwardly extending inclined legs of the arcuate segments are prevented from coming into contact with corresponding legs of adjacent segments. 5. The fast breeder reactor structure according to claim 4, wherein the arcuate segment of the yoke is a forged body. 6. The fast breeder reactor structure according to claim 4, wherein the arcuate segment of the yoke is an extrusion.
JP4520479A 1978-04-14 1979-04-13 Fast breeder cooled by liquefied metal Granted JPS54140079A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB1480978 1978-04-14

Publications (2)

Publication Number Publication Date
JPS54140079A JPS54140079A (en) 1979-10-30
JPS6250796B2 true JPS6250796B2 (en) 1987-10-27

Family

ID=10047868

Family Applications (1)

Application Number Title Priority Date Filing Date
JP4520479A Granted JPS54140079A (en) 1978-04-14 1979-04-13 Fast breeder cooled by liquefied metal

Country Status (3)

Country Link
JP (1) JPS54140079A (en)
DE (1) DE2915182A1 (en)
FR (1) FR2423033A1 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH045299U (en) * 1990-04-20 1992-01-17

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
IT1171247B (en) * 1983-11-09 1987-06-10 Nira Spa FAST NUCLEAR REACTOR SLAB IN REINFORCED CONCRETE

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH045299U (en) * 1990-04-20 1992-01-17

Also Published As

Publication number Publication date
JPS54140079A (en) 1979-10-30
FR2423033A1 (en) 1979-11-09
DE2915182A1 (en) 1979-10-31

Similar Documents

Publication Publication Date Title
US3105026A (en) Fuel elment for nuclear reactors
JPS6250796B2 (en)
US3079321A (en) Sodium deuterium reactor
US4294661A (en) Liquid metal cooled fast breeder nuclear reactor constructions
US6389094B1 (en) Integral forged shroud flange for a boiling water reactor
RU94015748A (en) CONCRETE CONTAINER
US4016035A (en) Fuel assembly support column for a nuclear reactor diagrid
EP0528672A1 (en) Reactor pressure vessel with forged nozzles
US9892806B2 (en) Space saver flanged joint for a nuclear reactor vessel
US5207977A (en) Reactor pressure vessel with forged nozzles
US4777012A (en) Gas cooled high temperature reactor charged with spherical fuel elements
FI118105B (en) Mantel weld joint for a boiler reactor
RU2234752C2 (en) Nuclear reactor fuel assembly
Takahashi et al. Construction of the Monju prototype fast breeder reactor
US4638768A (en) Steam generator tubesheet/channel head/centerstay assembly
US4534140A (en) Annular slab for closing the vessel of a fast neutron nuclear reactor
US6570950B1 (en) Nuclear plant containment with prefabricated component support structure
KR100385839B1 (en) Reactor vessel having upper and lover plane shaped head in the center section
Doctor Measurement challenges associated with irradiated reactor components
JPS6150274B2 (en)
Mohta et al. Structural integrity assessment of Calandria of standard 220 MWe PHWR for in-vessel corium retention without SAMG action
GB1597189A (en) Nuclear reactor fuel sub-assemblies
RU2059299C1 (en) Nuclear reactor and method of cleaning of fuel assemblies of nuclear reactor
Madarame et al. A CONCEPTUAL DESIGN OF LIB FUSION KHACTOR: UTLIF (2)
JPH0631795B2 (en) Spent fuel storage rack