JPS61256281A - Nuclear fuel body - Google Patents

Nuclear fuel body

Info

Publication number
JPS61256281A
JPS61256281A JP60096607A JP9660785A JPS61256281A JP S61256281 A JPS61256281 A JP S61256281A JP 60096607 A JP60096607 A JP 60096607A JP 9660785 A JP9660785 A JP 9660785A JP S61256281 A JPS61256281 A JP S61256281A
Authority
JP
Japan
Prior art keywords
nuclear fuel
fuel assembly
graphite
protrusion
heat transfer
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
JP60096607A
Other languages
Japanese (ja)
Inventor
正幸 小島
梅野 誠
時田 雄次
昇 松村
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Heavy 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 Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Priority to JP60096607A priority Critical patent/JPS61256281A/en
Publication of JPS61256281A publication Critical patent/JPS61256281A/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

  • Organic Low-Molecular-Weight Compounds And Preparation Thereof (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】 (産業上の利用分野) 本発明は黒鉛ブロックを貫通した貫通孔内に挿入 支持
される核燃料体に関するものである。
DETAILED DESCRIPTION OF THE INVENTION (Industrial Field of Application) The present invention relates to a nuclear fuel assembly inserted and supported in a through hole penetrating a graphite block.

(従来の技術) 本件出願人がすでに提案したモールド型核燃料体を第7
,8図により説明すると、(1)が核燃料体の燃料コン
パクト、 (2)が同燃料コンパクト(1)を取り囲む
茶筒状黒鉛殻、(3)が同黒鉛殻(2)の外面に軸方向
に設けた突条で、同核燃料体が黒鉛ブロックを貫通した
貫通孔内に挿入、支持されるようになっている。また第
9,10図は、上記第7゜8図の核燃料体の他の例で、
軸方向に高さの高い3条の突条(3)とそれよりも低い
12条の突条(4)とが設けられている。
(Prior art) The molded nuclear fuel assembly already proposed by the applicant
, 8. To explain using Figure 8, (1) is the fuel compact of the nuclear fuel assembly, (2) is the brown cylinder-shaped graphite shell surrounding the fuel compact (1), and (3) is the graphite shell (2) with its outer surface extending in the axial direction. The provided protrusions allow the nuclear fuel assembly to be inserted and supported within the through hole that penetrates the graphite block. Figures 9 and 10 show other examples of the nuclear fuel assembly shown in Figures 7-8 above.
Three protrusions (3) with a high height and 12 protrusions (4) with a lower height are provided in the axial direction.

(発明が解決しようとする問題点) 前記第7,8図に示すモールド型核燃料体には。(Problem that the invention attempts to solve) In the molded nuclear fuel assembly shown in FIGS. 7 and 8 above.

複数の突条(フィン)(3)があり1同突条がない場合
に比べると、伝熱面積が増加して、核燃料体(1)から
黒鉛ブロンクの貫通孔(冷却孔)内を流れる冷却材への
伝熱量が増加するが、突条(フィン)(3)の数が少な
くて、伝熱量の増加をそれ程期待できない。また前記第
9.10図に示すモールド型核燃料体には、軸方向に高
さの高い3条の突条(3)とそれよりも低い12条の突
条(4)とがあり、突条がない場合に比べると、伝熱面
積がさらに増加して、核燃料体から冷却材への伝熱量が
増加するが、この場合には、流路断面積が少なくなり、
圧力損失一定の条件下では流速が減少して。
Compared to the case where there are multiple fins (3) and no single fin, the heat transfer area increases and cooling flows from the nuclear fuel body (1) through the through holes (cooling holes) of the graphite bronc. The amount of heat transferred to the material increases, but since the number of fins (3) is small, we cannot expect a significant increase in the amount of heat transferred. In addition, the molded nuclear fuel assembly shown in Figure 9.10 has three protrusions (3) with a high height in the axial direction and 12 protrusions (4) with a lower height. Compared to the case without it, the heat transfer area increases further and the amount of heat transferred from the nuclear fuel body to the coolant increases, but in this case, the cross-sectional area of the flow path decreases,
Under conditions of constant pressure drop, the flow rate decreases.

熱伝達効率が低下する。なお第11.12図に示すピン
インブロック型と称せられる核燃料体は。
Heat transfer efficiency decreases. The nuclear fuel assembly called the pinyin block type is shown in Fig. 11.12.

黒鉛殻(13)が機械加工により製作されるので、製作
コストを高めるという問題があった。なお同第11.1
2図の(11)は黒鉛ブロック、 (12)が核燃料体
、 (13)が黒鉛殻、 (14)が燃料コンパクト、
(15)が突条である。
Since the graphite shell (13) is manufactured by machining, there is a problem in that the manufacturing cost increases. Note that Section 11.1 of the same
In Figure 2, (11) is the graphite block, (12) is the nuclear fuel body, (13) is the graphite shell, (14) is the fuel compact,
(15) is the protrusion.

(問題点を解決するための手段) 本発明は前記の問題点に対処するもので、黒鉛ブロック
を貫通した貫通孔内に挿入、支持される核燃料体におい
て、同核燃料体の燃料コンパクトを取り囲む茶筒状黒鉛
殻の外面に軸方向の突条と同軸方向の高さよりも低い周
方向の突条とを形成したことを特徴とする核燃料体に係
わり、その目的とする処は、圧力損失一定の条件下で熱
伝達効率を向上できる改良された核燃料体を供する点に
ある。
(Means for Solving the Problems) The present invention addresses the above-mentioned problems, and provides a tea caddy surrounding a fuel compact of a nuclear fuel assembly inserted and supported in a through hole penetrating a graphite block. The nuclear fuel element is characterized in that an axial protrusion and a circumferential protrusion lower than the height of the coaxial direction are formed on the outer surface of a graphite shell, and its purpose is to satisfy the condition of constant pressure loss. An object of the present invention is to provide an improved nuclear fuel assembly that can improve heat transfer efficiency under the following conditions.

本発明は前記のように黒鉛ブロックを貫通した貫通孔内
に挿入、支持される核燃料体において。
The present invention relates to a nuclear fuel assembly inserted and supported in a through hole penetrating a graphite block as described above.

同核燃料体の燃料コンパクトを取り囲む茶筒状黒鉛殻の
外面に軸方向の突条と同軸方向の憂さよりも低い周方向
の突条とを形成しており、黒鉛殻の周りに乱流が生じ、
突条の総伝熱面積が増大されることと相俟って、圧力損
失一定の条件下で熱伝達効率が向上される。
On the outer surface of the brown cylinder-shaped graphite shell surrounding the fuel compact of the nuclear fuel assembly, an axial protrusion and a circumferential protrusion lower than the coaxial direction are formed, causing turbulent flow around the graphite shell.
Combined with the increase in the total heat transfer area of the protrusions, the heat transfer efficiency is improved under conditions of constant pressure loss.

(実施例) 次に本発明の核燃料体を第1,2図に示す一実施例によ
り説明すると、 (23)が核燃料体で、同核燃料体(
23)か燃料コンパクト(31)と同燃料コンバクl−
(31)を取り囲む茶筒状黒鉛殻(32)と同茶筒状黒
鉛殻(32)の外面を軸方向に45°のピンチで設けら
れた突条(33)と同茶筒状黒鉛殻(32)の外面を周
方向に螺旋条に設けられた突条(34)とにより構成さ
れ1回周方向突条(34)の高さが上記軸方向突条(3
3)の高さよりも低くなっている。
(Embodiment) Next, the nuclear fuel assembly of the present invention will be explained using an embodiment shown in FIGS. 1 and 2. (23) is a nuclear fuel assembly, and the nuclear fuel assembly (
23) or Fuel Compact (31) and the same Fuel Combat l-
The brown cylindrical graphite shell (31) surrounds the brown cylindrical graphite shell (32), and the protrusion (33) is provided with a 45° pinch in the axial direction on the outer surface of the brown cylindrical graphite shell (32). The height of the circumferential protrusion (34) is the same as that of the axial protrusion (34).
It is lower than the height of 3).

また第3,4図は、上記周方向の突条(34)を螺旋状
にせずに軸線に対し直交状態に設けて環状にした以外、
上記第1,2図の実施例と同様に構成した他の実施例で
ある。
In addition, FIGS. 3 and 4 show that the circumferential protrusion (34) is not spiral but perpendicular to the axis and is annular.
This is another embodiment configured similarly to the embodiment shown in FIGS. 1 and 2 above.

上記核燃料体(23)は、第5.6図に示すように黒鉛
ブロック(21)を貫通した貫通孔(冷却孔)(22)
内に挿入されて、支持される。
The nuclear fuel assembly (23) has through holes (cooling holes) (22) penetrating the graphite block (21) as shown in Figure 5.6.
inserted into and supported.

(作用) 次に前記核燃料体の作用を説明する。黒鉛ブロック(2
1)の貫通孔(冷却孔) (22)の内周面と茶筒状黒
鉛殻(32)の外周面と軸方向突条(33)の外面とで
形成される平面形状扇状の流路を冷却材が流れる際5同
冷却材の流れか高さの低い周方向突条(34)により乱
されて、核燃料体(23)から冷却材への熱伝達が促進
される。
(Function) Next, the function of the nuclear fuel assembly will be explained. Graphite block (2
1) Through hole (cooling hole) Cools the planar fan-shaped flow path formed by the inner circumferential surface of (22), the outer circumferential surface of the tea cylinder-shaped graphite shell (32), and the outer surface of the axial protrusion (33). When the fuel flows, the flow of the coolant is disturbed by the low circumferential protrusions (34), promoting heat transfer from the nuclear fuel body (23) to the coolant.

(発明の効果) 本発明は前記のように黒鉛ブロックを貫通した貫通孔内
に挿入2支持される核燃料体において。
(Effects of the Invention) The present invention provides a nuclear fuel assembly that is inserted and supported in a through hole penetrating a graphite block as described above.

同核燃料体の燃料コンパクトを取り囲む茶筒状黒鉛殻の
外面に軸方向の突条と同軸方向の高さよりも低い周方向
の突条とを形成しており、黒鉛殻の周りに乱流が生じ、
突条の総伝熱面積が増大されることと相俟って、圧力損
失一定の条件下で熱伝達効率を向上できる効果がある。
An axial protrusion and a circumferential protrusion lower than the coaxial height are formed on the outer surface of the tea cylinder-shaped graphite shell surrounding the fuel compact of the nuclear fuel assembly, and turbulent flow occurs around the graphite shell.
Combined with the increase in the total heat transfer area of the protrusions, this has the effect of improving heat transfer efficiency under conditions of constant pressure loss.

以上本発明を実施例について説明したが、勿論本発明は
このような実施例にだけ局限されるものでなく2本発明
の精神を逸脱しない範囲で種々の設計の改変を施しうる
ちのである。
Although the present invention has been described above with reference to embodiments, it goes without saying that the present invention is not limited to these embodiments, and may be modified in various ways without departing from the spirit of the present invention.

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

第1図は本発明に係わる核燃料体の一実施例を示す一部
縦断側面図、第2図は第1図の矢視■−■線に沿う横断
平面図、第3図は他の実施例を示す一部縦断側面図、第
4図は第1図の矢視IV−IV、腺に沿う横断平面図、
第5図は黒鉛ブロックを示す一部縦断側面図、第6図は
その平面図、第7図はすでに提案したモールド型核燃料
体の第8図の矢視■−■線に沿う−・部縦断側面図、第
8図は第7図の矢視■−■線に沿う一部横断平面図、第
9図はすでに提案した核燃料体の他の例の第10図の矢
視IX−IX線に沿う一部縦断側面図、第10図は第9
図の矢視X−X線に沿う一部横断平面図。 第11図は従来のビンインブロック型核燃料体の側面図
、第12図はその平面図である。 (21)・・・黒鉛ブロック、 (22)  ・・・貫
通孔、(23)・・・核燃料体、 (31)  ・・・
燃料コンパクト。 (32)・・・茶筒状黒鉛殻、 (33)  ・・・軸
方向の突条、 (34)  ・・・周方向の突条。
FIG. 1 is a partially longitudinal side view showing one embodiment of a nuclear fuel assembly according to the present invention, FIG. 2 is a cross-sectional plan view taken along the arrow ■-■ line in FIG. 1, and FIG. 3 is another embodiment. FIG. 4 is a cross-sectional plan view taken along the gland along arrow IV-IV in FIG.
Figure 5 is a partially longitudinal side view showing the graphite block, Figure 6 is its plan view, and Figure 7 is a longitudinal section of the already proposed molded nuclear fuel assembly along the arrow ■-■ line in Figure 8. A side view, FIG. 8 is a partial cross-sectional plan view taken along the line ■-■ in FIG. 7, and FIG. 9 is a partial cross-sectional plan view taken along the line IX-IX in FIG. 10 of another example of the nuclear fuel assembly already proposed. A partially longitudinal side view along the line, Figure 10 is the 9th
FIG. 3 is a partially cross-sectional plan view taken along line X-X in the figure. FIG. 11 is a side view of a conventional bin-in-block type nuclear fuel assembly, and FIG. 12 is a plan view thereof. (21)...Graphite block, (22)...Through hole, (23)...Nuclear fuel body, (31)...
Fuel compact. (32)...Tea cylinder-shaped graphite shell, (33)...Axis protrusion, (34)...Circumferential protrusion.

Claims (1)

【特許請求の範囲】[Claims] 黒鉛ブロックを貫通した貫通孔内に挿入、支持される核
燃料体において、同核燃料体の燃料コンパクトを取り囲
む茶筒状黒鉛殻の外面に軸方向の突条と同軸方向の高さ
よりも低い周方向の突条とを形成したことを特徴とする
核燃料体。
In a nuclear fuel assembly that is inserted and supported in a through hole penetrating a graphite block, the outer surface of a brown cylinder-shaped graphite shell surrounding the fuel compact of the nuclear fuel assembly has an axial protrusion and a circumferential protrusion that is lower than the coaxial height. A nuclear fuel body characterized by forming a column.
JP60096607A 1985-05-09 1985-05-09 Nuclear fuel body Pending JPS61256281A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60096607A JPS61256281A (en) 1985-05-09 1985-05-09 Nuclear fuel body

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60096607A JPS61256281A (en) 1985-05-09 1985-05-09 Nuclear fuel body

Publications (1)

Publication Number Publication Date
JPS61256281A true JPS61256281A (en) 1986-11-13

Family

ID=14169552

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60096607A Pending JPS61256281A (en) 1985-05-09 1985-05-09 Nuclear fuel body

Country Status (1)

Country Link
JP (1) JPS61256281A (en)

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