JPS61290382A - Liquid metal cooling fast breeder reactor - Google Patents
Liquid metal cooling fast breeder reactorInfo
- Publication number
- JPS61290382A JPS61290382A JP60131533A JP13153385A JPS61290382A JP S61290382 A JPS61290382 A JP S61290382A JP 60131533 A JP60131533 A JP 60131533A JP 13153385 A JP13153385 A JP 13153385A JP S61290382 A JPS61290382 A JP S61290382A
- Authority
- JP
- Japan
- Prior art keywords
- core
- liquid metal
- fast breeder
- coolant
- pressure plenum
- 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.)
- Granted
Links
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
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Manufacture And Refinement Of Metals (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〉
この発明は、一次冷却系冷却材に混入しているガスが炉
心中心部の燃料集合体領域に流入し難い構造を有する液
体金属冷却高速増殖炉（以下ｒＬＭＦＢＲＪと略記する
）に関するものである。[Detailed Description of the Invention] <Industrial Application Field> The present invention is directed to a liquid metal cooling fast breeder having a structure that prevents gas mixed in the primary cooling system coolant from flowing into the fuel assembly region in the center of the reactor core. This relates to a furnace (hereinafter abbreviated as rLMFBRJ).
〈従来の技術〉
第４図は従来のＬＭ Ｆ Ｂ Ｒの概略構造を示すもの
であり、一次冷却系冷却材（液体金属）は原子炉容器１
の冷却材入口配管２から高圧プレナム３に流入する。こ
の高圧プレナムを構成する炉心支持板４は、中心領域に
配置された炉心燃料集合体５およびその外周に配置され
たプランケラ１〜燃料集合体ざらにその外周に配置され
た可動遮蔽体（図示を省略）をモジュール７を介して支
持している。高圧プレナムに流入した冷却材はモジュー
ル７を経て炉心燃料集合体、プランケラ１〜燃料集合体
６；Ｊ３よび可動遮蔽体内を流通し、冷却材出口配管８
を経て原子炉容器１から流出する。<Prior art> Figure 4 shows the schematic structure of a conventional LM FBR, in which the primary cooling system coolant (liquid metal) is supplied to the reactor vessel 1.
The coolant flows into the high pressure plenum 3 from the coolant inlet pipe 2 . The core support plate 4 constituting this high-pressure plenum consists of a core fuel assembly 5 arranged in the central region, a plancher 1 arranged around the outer periphery of the core fuel assembly 5, a movable shield (not shown) arranged around the outer periphery of the fuel assembly (omitted) is supported via module 7. The coolant that has flowed into the high-pressure plenum passes through the module 7, flows through the core fuel assembly, the plankera 1 to fuel assembly 6; J3, and the movable shield, and then flows through the coolant outlet pipe 8.
It flows out from the reactor vessel 1 through .
〈発明が解決しようとする問題点〉
上述したごとき従来のＬＭＦＢＲにおいては、一次冷却
系冷却材にガスが混入して冷却材とともに高圧プレナム
３に流入した場合には、これらのガスは気泡となって高
圧プレナム内に均一に分配され、その多くは冷却材流旦
配分割合の大きい炉心燃料集合体内に流入する可能性が
ある。<Problems to be solved by the invention> In the conventional LMFBR as described above, when gases are mixed into the primary cooling system coolant and flow into the high pressure plenum 3 together with the coolant, these gases become bubbles. The coolant is evenly distributed within the high-pressure plenum, and much of it may flow into the core fuel assembly, which has a large coolant distribution ratio.
かようなガスが冷却材とともに炉心に流入すると、正の
反応度が体系に加わり、燃料溶融等の事故に至る危険が
生ずる。特に炉心燃料集合体へガスが流入した場合に、
最も大きい正の反応度を体系に与えることになる。If such gas flows into the reactor core together with the coolant, positive reactivity will be added to the system, creating the risk of fuel meltdown or other accidents. Especially when gas flows into the core fuel assembly,
It will give the system the greatest positive reactivity.
そのため従来のＬＭＦＢＲでは、混入ガスの検出および
反応度を含む炉心特性の監視等の各種対策を施ず必要が
あった。Therefore, in the conventional LMFBR, it was necessary to take various measures such as detection of mixed gas and monitoring of core characteristics including reactivity.
また、中間熱交換器と二次冷却系を省略して一次冷却系
に直接蒸気発生器を設置する型式の二次系削除型ＬＭＦ
ＢＲでは、万一蒸気発生器において一次冷却材と水とが
反応した場合に多量のガスを発生し、このガスが一次冷
却水とともに高圧プレナムに流入する可能性があり、上
記したごとき各種対策が一層＠要となる。In addition, a secondary system deletion type LMF is a type in which the intermediate heat exchanger and secondary cooling system are omitted and a steam generator is installed directly in the primary cooling system.
In a BR, if the primary coolant and water react in the steam generator, a large amount of gas will be generated, and this gas may flow into the high-pressure plenum together with the primary cooling water, so the various countermeasures described above are necessary. It becomes even more important.
そこでこの発明の目的は、ＬＭＦＢＲの原子炉容器内の
高圧プレナムに万一ガスが流入した場合でも、これをで
きるだけ炉心周辺部の可動遮蔽体あるいはプランケラ１
〜燃料集合体領域に流入し易くし、炉心中心部の燃料集
合体領域には流入し難い構造を有するＬＭＦＢＲを提供
し、これによって、正の反応度の投入による燃″ＩＩ溶
融等の事故リスクを低減し、混入ガスの検出や炉心特性
の監視等に係る胴側系を簡略化することである。Therefore, an object of the present invention is to prevent gas from flowing into the high-pressure plenum in the reactor vessel of an LMFBR by using a movable shield or plancher in the periphery of the core as much as possible.
- Providing an LMFBR with a structure that allows fuel to easily flow into the fuel assembly region and prevent it from flowing into the fuel assembly region in the center of the core, thereby reducing the risk of accidents such as fuel II melting due to injection of positive reactivity. The aim is to simplify the shell-side systems involved in detecting mixed gas and monitoring core characteristics.
〈問題点を解決するだめの手段〉
づなわちこの発明によれば、一次冷却系冷却材が流入す
る高圧プレプムを原子炉容器内に配置した液体金属冷却
高速増殖炉において、前記高圧プレナムを構成する炉心
支持板をその中心部よりも周辺部が高くなるような円錐
形状とすることによって上記の目的を達成することがで
きる。<Means for solving the problem> According to the present invention, in a liquid metal cooled fast breeder reactor in which a high-pressure plenum into which a primary cooling system coolant flows is arranged in a reactor vessel, the high-pressure plenum is configured. The above object can be achieved by forming the core support plate into a conical shape such that the peripheral part is higher than the central part.
従来は水平方向に平面状に設けられていた炉心支持板を
、この発明におけるように円錐形状としたことによって
、高圧プレナムに流入した気泡は炉心の外周部、すなわ
ち可動遮蔽体ヤブランケッ１〜燃料集合体領域へ流入し
易く、中心部の炉心燃料集合体には流入し難くすること
ができるのである。この結果、正の反応度の炉心への投
入を抑制、低減することが可能となる。The core support plate, which was conventionally provided horizontally in a planar shape, is made into a conical shape as in the present invention, so that the air bubbles flowing into the high pressure plenum are distributed around the outer periphery of the core, that is, between the movable shield cover 1 and the fuel assembly. This makes it easier for the fuel to flow into the core fuel assembly in the central part of the reactor. As a result, it becomes possible to suppress and reduce the injection of positive reactivity into the reactor core.
〈実施例〉
以下に図面に示す実施例を参照してこの発明を詳述する
。第１図はこの発明のＬＭＦＢＲの概略構造を示してお
り、第４図における従来構造と同じ部材は、第４図と同
じ参照番号を付すことによって説明を省略する。<Embodiments> The present invention will be described in detail below with reference to embodiments shown in the drawings. FIG. 1 shows a schematic structure of the LMFBR of the present invention, and the same members as in the conventional structure in FIG. 4 are given the same reference numerals as in FIG. 4, and a description thereof will be omitted.
第１図のこの発明の構造が第４図の従来構造と相違する
点は、原子炉容器１内に配置した高圧プレナム３を構成
する炉心支持板１４が、その中心部より周辺部が高くな
るような円錐形状となっている点である。この場合の円
錐形状は必ずしも正確な円錐面を有する必要はなく、最
も低いレベルにある頂点が高圧プレリム３側に位置し、
この頂点から放射方向に周辺部へ延びるに従ってレベル
が上っていくようなテーパー面を炉心支持板１４の高圧
プレナム側の面が有していればよい。The structure of the present invention shown in FIG. 1 is different from the conventional structure shown in FIG. 4 in that the core support plate 14 constituting the high-pressure plenum 3 disposed inside the reactor vessel 1 is higher at the periphery than at its center. It has a conical shape like this. The conical shape in this case does not necessarily have to have an accurate conical surface, and the apex at the lowest level is located on the high pressure prerim 3 side,
It is sufficient that the high-pressure plenum side surface of the core support plate 14 has a tapered surface whose level increases as it extends from the apex in the radial direction toward the periphery.
第２図は第１図におけるモジュール１７の部分を拡大し
て説明するものである。このモジュール１７は炉心支持
板１４の開口に嵌合する外筒１８内に挿入されて８３す
、通常７本の炉心燃料集合体５またはブランケット燃料
集合体６（第３図の断面図参照）の各々へ流母調節オリ
フィス１９を介して冷却材を分配する役割を有する。第
４図のごとき従来のＬＭＦＢＲにおいては、すべての炉
心領域において同一寸法、同一形状のモジュール７が用
いられているが、第１図および第２図に示したこの発明
においては、モジュール１７の全長を同一とし、モジュ
ールの球面座１７ａの位置を炉心支持板１４のテーパ一
度合（水平に対する角度θ）に対応するように炉心領域
に応じて変化ぎりごモジュールを使用している。かよう
なモジュール１７を用いることによって、炉心燃料集合
体およびブランケット燃料集合体６は第４図の従来のＬ
ＭＦＢＲと同じくすべて同一の長さとすることができる
。FIG. 2 is an enlarged view of the module 17 in FIG. 1. This module 17 is inserted into an outer cylinder 18 that fits into an opening in the core support plate 14, and is connected to the core fuel assemblies 5 or blanket fuel assemblies 6 (see the cross-sectional view in FIG. 3), which normally have seven core fuel assemblies 5 or blanket fuel assemblies 6. It has the role of distributing coolant to each via a fluid flow control orifice 19. In the conventional LMFBR as shown in FIG. 4, modules 7 of the same size and shape are used in all core regions, but in this invention shown in FIGS. 1 and 2, the entire length of the module 17 is is the same, and the position of the spherical seat 17a of the module is changed according to the core area so that it corresponds to the degree of taper of the core support plate 14 (angle θ with respect to the horizontal). By using such a module 17, the core fuel assembly and the blanket fuel assembly 6 can be replaced with the conventional L shown in FIG.
Like the MFBR, they can all be of the same length.
〈発明の効果〉
上述したような構造のこの発明のＬＭＦＢＲによれば、
一次系冷却材とともに高圧プレナムに流入したガスが、
さらに炉心燃料集合体へ流入するのを効果的に抑制する
ことができる。その結果、正の反応度の炉心への投入が
抑制されるため、燃料溶融等の事故の発生確率を小さく
することができ、安全性を高めた炉心構成をつくること
が可能となる。<Effects of the Invention> According to the LMFBR of this invention having the structure as described above,
The gas flowing into the high pressure plenum along with the primary coolant is
Furthermore, it is possible to effectively prevent the fuel from flowing into the core fuel assembly. As a result, since the injection of positive reactivity into the core is suppressed, the probability of occurrence of accidents such as fuel melting can be reduced, and it is possible to create a core configuration with increased safety.
第１図はこの発明の実施例を示１説明図、第２図は第１
図のモジュール部分の拡大説明図、第３図は第２図■−
■線に沿う断面図、および第４図は従来のＬＭＦＢＲを
示ず説明図である。
１・・・原子炉容器、２・・・冷却材入口配管、３・・
・高圧プレナム、４．１４・・・炉心支持板、５・・・
炉心燃料集合体、６・・・プランケット燃料集合体、７
．１７・・・モジュール、８・・・冷却材出口配管、１
７ａ・・・モジュールの球面座。FIG. 1 is an explanatory diagram showing an embodiment of the present invention, and FIG.
An enlarged explanatory diagram of the module part in the figure, Figure 3 is Figure 2 -
The cross-sectional view taken along the line (2) and FIG. 4 are explanatory views without showing the conventional LMFBR. 1... Reactor vessel, 2... Coolant inlet piping, 3...
・High pressure plenum, 4.14...core support plate, 5...
Core fuel assembly, 6... Plunket fuel assembly, 7
．． 17...Module, 8...Coolant outlet piping, 1
7a...Module spherical seat.
Claims (1)
容器内に配置した液体金属冷却高速増殖炉において、前
記高圧プレナムを構成する炉心支持板をその中心部より
も周辺部が高くなるような円錐形状としたことを特徴と
する液体金属冷却高速増殖炉1. In a liquid metal-cooled fast breeder reactor in which a high-pressure plenum into which coolant flows into the primary cooling system is disposed inside the reactor vessel, the core support plate constituting the high-pressure plenum is made such that the peripheral part is higher than the central part. Liquid metal cooled fast breeder reactor characterized by its conical shape
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60131533A JPS61290382A (en) | 1985-06-17 | 1985-06-17 | Liquid metal cooling fast breeder reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60131533A JPS61290382A (en) | 1985-06-17 | 1985-06-17 | Liquid metal cooling fast breeder reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS61290382A true JPS61290382A (en) | 1986-12-20 |
| JPH0160798B2 JPH0160798B2 (en) | 1989-12-25 |
Family
ID=15060293
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60131533A Granted JPS61290382A (en) | 1985-06-17 | 1985-06-17 | Liquid metal cooling fast breeder reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS61290382A (en) |
-
1985
- 1985-06-17 JP JP60131533A patent/JPS61290382A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0160798B2 (en) | 1989-12-25 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US4762667A (en) | Passive reactor auxiliary cooling system | |
| US3893886A (en) | Removable diagrid for supporting the fuel assemblies of a nuclear reactor | |
| US4101377A (en) | Fast neutron reactor | |
| JPS61290382A (en) | Liquid metal cooling fast breeder reactor | |
| JPH0344273B2 (en) | ||
| JP4301604B2 (en) | Pressurized water reactor | |
| US4664876A (en) | Fast breeder reactor | |
| JP3446855B2 (en) | Sealing device for the upper shield of the HTGR and the control rod guide tube | |
| JPH11133172A (en) | Internal structure of fast breeding reactor | |
| JPS60113184A (en) | Core support structure for fast breeder reactor | |
| JPS6394191A (en) | Cold trap | |
| GB1405443A (en) | Nuclear reactor of the kind having built-in heat exchanger systems | |
| JPS6060297A (en) | Nuclear reactor cooling material circulating pump | |
| JPS61210991A (en) | Coolant distributing chamber structure of fast breeder reactor | |
| JPS6128891A (en) | Fast breeder reactor | |
| JPH01185485A (en) | Thermal protecting device of reactor vessel | |
| JPS62107035A (en) | Cold trap | |
| JPS63223491A (en) | Intermediate heat exchanger | |
| JPS63223490A (en) | Intermediate heat exchanger | |
| JPH04299299A (en) | Intermediate heat exchanger for fast breeder reactor | |
| JPS59114494A (en) | Lmfbr type reactor | |
| JPH01217292A (en) | Tank reactor | |
| JPS61213597A (en) | Heat exchanger for high temperature | |
| JPS59133487A (en) | Incore structure for liquid metal cooled type fast breeder | |
| JPS6036998A (en) | Cooling device for nuclear reactor |