JPH03296693A - Fuel breakdown detector - Google Patents
Fuel breakdown detectorInfo
- Publication number
- JPH03296693A JPH03296693A JP2099215A JP9921590A JPH03296693A JP H03296693 A JPH03296693 A JP H03296693A JP 2099215 A JP2099215 A JP 2099215A JP 9921590 A JP9921590 A JP 9921590A JP H03296693 A JPH03296693 A JP H03296693A
- Authority
- JP
- Japan
- Prior art keywords
- neutron
- heat exchanger
- shielding body
- fuel
- detection device
- 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
Links
- 239000000446 fuel Substances 0.000 title claims abstract description 38
- 230000015556 catabolic process Effects 0.000 title abstract 2
- 238000001514 detection method Methods 0.000 claims abstract description 33
- 230000005251 gamma ray Effects 0.000 claims abstract description 17
- 238000001816 cooling Methods 0.000 claims description 12
- 230000003111 delayed effect Effects 0.000 abstract description 9
- 239000011810 insulating material Substances 0.000 abstract description 4
- 239000002826 coolant Substances 0.000 abstract description 3
- 230000035945 sensitivity Effects 0.000 abstract description 3
- 230000002093 peripheral effect Effects 0.000 abstract description 2
- 238000010276 construction Methods 0.000 abstract 2
- 239000007788 liquid Substances 0.000 description 8
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 6
- 229910052708 sodium Inorganic materials 0.000 description 6
- 239000011734 sodium Substances 0.000 description 6
- 238000010586 diagram Methods 0.000 description 5
- 238000009434 installation Methods 0.000 description 5
- 238000010521 absorption reaction Methods 0.000 description 2
- 238000006073 displacement reaction Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- NJPPVKZQTLUDBO-UHFFFAOYSA-N novaluron Chemical compound C1=C(Cl)C(OC(F)(F)C(OC(F)(F)F)F)=CC=C1NC(=O)NC(=O)C1=C(F)C=CC=C1F NJPPVKZQTLUDBO-UHFFFAOYSA-N 0.000 description 2
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 2
- NMFHJNAPXOMSRX-PUPDPRJKSA-N [(1r)-3-(3,4-dimethoxyphenyl)-1-[3-(2-morpholin-4-ylethoxy)phenyl]propyl] (2s)-1-[(2s)-2-(3,4,5-trimethoxyphenyl)butanoyl]piperidine-2-carboxylate Chemical compound C([C@@H](OC(=O)[C@@H]1CCCCN1C(=O)[C@@H](CC)C=1C=C(OC)C(OC)=C(OC)C=1)C=1C=C(OCCN2CCOCC2)C=CC=1)CC1=CC=C(OC)C(OC)=C1 NMFHJNAPXOMSRX-PUPDPRJKSA-N 0.000 description 1
- 230000000903 blocking effect Effects 0.000 description 1
- 230000008094 contradictory effect Effects 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 238000009413 insulation Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 230000000149 penetrating effect Effects 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
Abstract
Description
【発明の詳細な説明】 ［発明の目的］ （産業上の利用分野） 本発明は高速増殖炉における燃料破損検出装置に係る。[Detailed description of the invention] [Purpose of the invention] (Industrial application field) The present invention relates to a fuel failure detection device in a fast breeder reactor.
（従来の技術）
液体ナトリウム冷却型の高速増殖炉炉心を構成する燃料
の破損を検出する燃料破損検出装置としては、破損燃料
から冷却材である液体ナトリウム中に漏出する先行核か
ら放出される遅発中性子を検知し、これによって燃料破
損を検出する遅発中性子法による燃料破損検出装置が知
られている。(Prior art) A fuel failure detection device for detecting damage to the fuel constituting the core of a liquid sodium-cooled fast breeder reactor is a fuel failure detection device that detects failure of the fuel that constitutes the core of a liquid sodium-cooled fast breeder reactor. A fuel damage detection device using a delayed neutron method is known, which detects fired neutrons and thereby detects fuel damage.
第３図は前記遅発中性子法による従来の燃料破損検出装
置の系統図、第４図は前記燃料破損検出装置における中
性子検出器周辺の構造を示す断面図である。FIG. 3 is a system diagram of a conventional fuel failure detection device using the delayed neutron method, and FIG. 4 is a sectional view showing the structure around the neutron detector in the fuel failure detection device.
第３図において、原子炉容器１、−法主冷却系中間熱交
換器２、−法主冷却系循環ボンプ３は順次−次配管４に
よって接続されている。前記−法主冷却系中間熱交換器
２は、二次系配管５を介して図示しない蒸気発生器と接
続されている。また、燃料破損検出装置６は前記二次配
管４中の中間熱交換器２と循環ポンプ３との間の部分に
設けられている。In FIG. 3, the reactor vessel 1, the main cooling system intermediate heat exchanger 2, and the main cooling system circulation pump 3 are sequentially connected by a sequential piping 4. The main cooling system intermediate heat exchanger 2 is connected to a steam generator (not shown) via a secondary system piping 5. Further, the fuel damage detection device 6 is provided in a portion of the secondary pipe 4 between the intermediate heat exchanger 2 and the circulation pump 3.
第４図において、第３図に示した燃料破損検出装置６が
設けられた一次配管４の外側部には、保温材層７が設け
られ、この保温材層７の外側に前記燃料破損検出装置６
が設けられている。燃料破損検出装置６はγ線遮蔽体８
に包囲された中性子検出器９と、前記配管４を貫通させ
る開口部１２を具え、前記中性子検出器９に対する中性
子の侵入を遮断する中性子遮蔽体１１とを具える。図中
、１０は配管４内を流れる液体ナトリウム、１３は前記
中性子遮蔽体１１を支持する架台、１４は前記保温材層
７に設けられ、前記中性子遮蔽体１１の開口部１２に対
向する咽喉部をそれぞれ示している。In FIG. 4, a heat insulating material layer 7 is provided on the outer side of the primary pipe 4 in which the fuel damage detection device 6 shown in FIG. 6
is provided. The fuel damage detection device 6 includes a γ-ray shield 8
The neutron detector 9 includes a neutron detector 9 surrounded by a neutron detector 9, and a neutron shield 11 having an opening 12 passing through the pipe 4 and blocking neutrons from entering the neutron detector 9. In the figure, 10 is liquid sodium flowing inside the pipe 4, 13 is a pedestal that supports the neutron shield 11, and 14 is a throat part provided in the heat insulating layer 7 and facing the opening 12 of the neutron shield 11. are shown respectively.
燃料破損の場合には、遅発中性子を放射する先行核が冷
却材である液体ナトリウム１０とともに管路４内を流れ
ることとなる。前記先行核の放射する遅発中性子は配管
４、γ線遮蔽体８を貫通して中性子検出器９に入射し、
ここで検出される。In the event of fuel failure, the leading nucleus emitting delayed neutrons will flow through the pipe 4 together with liquid sodium 10 as a coolant. The delayed neutrons emitted by the preceding nucleus penetrate the piping 4 and the γ-ray shield 8 and enter the neutron detector 9,
detected here.
この検出によって燃料破損を告知する警報が発せられる
。This detection causes an alarm to notify of fuel damage.
前記構成の従来の燃料破損検出装置６において。In the conventional fuel failure detection device 6 having the above configuration.
γ線遮蔽体８は配管４内を流れる液体ナトリウムが常時
放射するγ線が中性子検出器に入射するのを防止し、中
性子検出器９のバックグラウンドノイズを低減させるも
のである。また、中性子遮蔽体１１は燃料破損検出装置
６の最外側に設けられ、それを設置した室内にある遅発
中性子以外の中性子が中性子検出器９に入射するのを防
止し、同様にバックグラウンドノイズを低減させるもの
である。なお、γ線遮蔽体８はγ線を遮断することがで
き、中性子を透過させることができる鉛等によって構成
されている。The gamma ray shield 8 prevents gamma rays constantly emitted by the liquid sodium flowing in the pipe 4 from entering the neutron detector, and reduces background noise in the neutron detector 9. The neutron shield 11 is provided on the outermost side of the fuel failure detection device 6, and prevents neutrons other than delayed neutrons in the room where it is installed from entering the neutron detector 9, and also prevents background noise. This reduces the Note that the γ-ray shield 8 is made of lead or the like that can block γ-rays and transmit neutrons.
また、前記架台１３はかなりの重量がある燃料破損検出
装置６の重量が配管４に作用しないようにするもので、
＃！料破損検呂装置の重量をプラント床面に支持す、る
ものである。Furthermore, the pedestal 13 prevents the weight of the fuel damage detection device 6, which is quite heavy, from acting on the pipe 4.
#! This is to support the weight of the material damage inspection device on the plant floor.
さらに、前記咽喉部１４は配管４を貫通させる中性子遮
蔽体１１の開口部１２をできるだけ小さくし、そこから
測定系内に直接入射してくる遅発中性子以外の中性子を
減少させ、バックグラウンドノイズを低減させるように
している。Furthermore, the throat part 14 makes the opening 12 of the neutron shield 11 that penetrates the pipe 4 as small as possible, reduces neutrons other than delayed neutrons that directly enter the measurement system from there, and reduces background noise. I'm trying to reduce it.
（発明が解決しようとする課題）
ところが、保温材層７、配管４、配管４内を流れる液体
ナトリウム等は中性子遮蔽効果が非常に小さいため、前
記のように保温材層７と開口部１２との間隙をできるだ
け小さくなるようにしても、前記開口部１２からの遅発
中性子以外の中性子の侵入を完全に避けることができず
、連発中性子の検出感度がある限度に抑えられてしまう
欠点があった・
また、前記開口部１２は前記のようにできるだけ小さい
ことが要求されるものであるにも拘らず、原子炉運転時
にその内部を流れる液体ナトリウムの温度変化により、
配管４はかなりの熱変位を示すのでそれに対処するため
前記開口部１２はある限度以下の大きさとすることは困
難である。また、配管４の据付誤差を吸収するためにも
ある程度の大きさは必要である。(Problem to be Solved by the Invention) However, since the neutron shielding effect of the heat insulating layer 7, the piping 4, and the liquid sodium flowing through the pipe 4 is very small, the insulating material layer 7 and the opening 12 are not connected to each other as described above. Even if the gap is made as small as possible, the intrusion of neutrons other than delayed neutrons from the opening 12 cannot be completely avoided, and there is a drawback that the detection sensitivity for continuous neutrons is suppressed to a certain limit. Additionally, although the opening 12 is required to be as small as possible as described above, due to temperature changes in the liquid sodium flowing inside the reactor during operation,
Since the piping 4 exhibits considerable thermal displacement, it is difficult to make the opening 12 smaller than a certain limit in order to cope with this. In addition, a certain size is necessary to absorb installation errors of the piping 4.
従って、前記開口部の形状、寸法は前記の互いに相反す
る要求を勘案した上で決定する必要があり、また前記開
口部１２を含む燃料破損検出装置６は製作上、据付上厳
しく管理するようにしなければならない。これ等は、燃
料破損検出装置のコストを上昇させる大きな原因となっ
ている。Therefore, the shape and dimensions of the opening must be determined by taking into account the conflicting requirements mentioned above, and the fuel failure detection device 6 including the opening 12 must be strictly controlled in manufacturing and installation. There must be. These factors are a major cause of increasing the cost of the fuel damage detection device.
本発明は上記の事情に基づきなされたもので、燃料破損
による先行核の放射する遅発中性子の検出感度が高くし
かも低コストの燃料破損検出装置を提供することを目的
としている。The present invention has been made based on the above-mentioned circumstances, and an object of the present invention is to provide a fuel failure detection device that has high sensitivity in detecting delayed neutrons emitted by preceding nuclei due to fuel failure and is low in cost.
［発明の構成］
（１１題を解決するための手段）
本発明の燃料破損検出装置は、中性子検出器をγ線遮蔽
体で覆い、前記γ線遮蔽体の一面を除き中性子遮蔽体で
覆ってなるものを、γ線遮蔽体の露出した面を一次冷却
系中間熱交換器筺体外面に密着させて取り付けたことを
特徴とする。[Structure of the Invention] (Means for Solving Problem 11) The fuel damage detection device of the present invention includes a neutron detector covered with a gamma ray shield, and a neutron shield except one surface of the gamma ray shield. This is characterized in that the exposed surface of the gamma ray shield is attached in close contact with the outer surface of the primary cooling system intermediate heat exchanger housing.
（作用）
上記構成の本発明の燃料破損検出装置においては、−水
冷却系中間熱交換器に直接に取り付けられているため、
配管を貫通させるための開口部を設ける必要はない。(Function) In the fuel damage detection device of the present invention having the above configuration, - Since it is directly attached to the water cooling system intermediate heat exchanger,
There is no need to provide an opening for the piping to pass through.
従って、前記開口部の設置に伴う種々の問題は一掃され
る。Therefore, various problems associated with the installation of said openings are eliminated.
（実施例）
第３図と同一部分には同一符号を付した第１図は本発明
の一実施例を示す系統図、第２図は燃料破損検出装置の
中性子検出器周辺を拡大して示す断面図である。第１図
に示すように前記実施例においては、燃料破損検出装置
６は一次冷却系中間熱交換器２の側壁外周面上端近傍、
すなわち原子炉容器１からの配管４が一次冷却系中間熱
交換器２に接続する位置より若干上方の部位に設置され
ている。(Embodiment) The same parts as in Fig. 3 are given the same reference numerals. Fig. 1 is a system diagram showing one embodiment of the present invention, and Fig. 2 is an enlarged view of the vicinity of the neutron detector of the fuel failure detection device. FIG. As shown in FIG. 1, in the embodiment, the fuel damage detection device 6 is located near the upper end of the outer peripheral surface of the side wall of the intermediate heat exchanger 2 in the primary cooling system.
That is, the piping 4 from the reactor vessel 1 is installed at a position slightly above the position where it connects to the intermediate heat exchanger 2 of the primary cooling system.
第２図において、−水冷却系中間熱交換器２の筺体外周
面の前記部位には、ブラケット１５が突設されている。In FIG. 2, a bracket 15 is provided to protrude from the outer circumferential surface of the casing of the water-cooled intermediate heat exchanger 2. As shown in FIG.
また、中性子検出器９はγ線遮蔽体８に包囲埋設されて
おり、γ線遮蔽体８にはその一面を除き中性子遮蔽体１
１が覆われている。In addition, the neutron detector 9 is surrounded and buried in the γ-ray shield 8, and the neutron shield 8 includes the neutron shield 1 except for one side of the γ-ray shield 8.
1 is covered.
而して、燃料破損検出装置６は前記γ線遮蔽体８の露出
された１面を前記−水冷却系中間熱交換器２の保温材層
７に密着させて、前記ブラケット１５上に設置されてい
る。なお、図中１６は前記−水冷却系中間熱交換器２を
建屋に吊下支持するためのサポート胴を示している。The fuel damage detection device 6 is installed on the bracket 15 with the exposed one surface of the γ-ray shield 8 in close contact with the heat insulating material layer 7 of the water-cooled intermediate heat exchanger 2. ing. Note that 16 in the figure indicates a support shell for suspending and supporting the water-cooled intermediate heat exchanger 2 in a building.
上記構成の実施例にあっては、燃料破損検出装置が配管
４を貫通させるための開口を有せず、直接に一次冷却系
中間熱交換器２に取り付けられているため、前記開口部
の設置に伴う種々の問題は一掃される。In the embodiment with the above configuration, since the fuel damage detection device does not have an opening for penetrating the pipe 4 and is directly attached to the primary cooling system intermediate heat exchanger 2, it is difficult to install the opening. Various problems associated with this will be eliminated.
［発明の効果］
上記から明らかなように本発明の燃料破損検出器は一次
冷却系中間熱交換器に直接に取り付けられているため、
配管を貫通させるための開口部を設ける必要はない。[Effects of the Invention] As is clear from the above, since the fuel damage detector of the present invention is directly attached to the intermediate heat exchanger of the primary cooling system,
There is no need to provide an opening for the piping to pass through.
従って、熱変位吸収、取付誤差吸収を可能とするための
要求と、バックグラウンドノイズを減少するための要求
との相反する要求に基づく開口部の形状、寸法の決定や
、燃料破損検出装置の製作、据付等を厳しく管理する必
要はなく、コストの低い燃料破損検出装置とすることが
できる。また、前記開口部によるバックグラウンドノイ
ズの上昇はなく、高精度の検出を行うことができる。Therefore, the shape and dimensions of the opening are determined based on the contradictory requirements of enabling thermal displacement absorption and installation error absorption, and the requirement of reducing background noise, and the fabrication of the fuel damage detection device. , there is no need to strictly control installation, etc., and a low-cost fuel damage detection device can be obtained. Further, there is no increase in background noise due to the opening, and highly accurate detection can be performed.
第１図は本発明の一実施例を示す系統図、第２図は燃料
破損検出装置の中性子検出器周辺を周辺を拡大して示す
断面図、第３図は前記遅発中性子法による従来の燃料破
損検出装置の系統図、第４図は前記燃料破損検出装置に
おける中性子検出器周辺の構造を示す断面図である。
１・・・・・・原子炉容器 ２・・・・・・−水冷却系
中間熱交換器 ３・・・・・・−次冷却系主循環ポンプ
４・・・・・・配管 ５・・・・・・二次系配管 ６
・・・・・・燃料破損検出装置７・・・・・・保温材層
８・・・・・・γ線遮蔽体 ９・・・・・・中性子検
出器 １０・・・・・・液体ナトリウム １１・・・・
・・中性子遮蔽体 １２・・・・・・開口部 １３・・
・・・・架台１４・・・・・・咽喉部 １５・・・・・
・ブラケット １６・・・・・・サポート胴Fig. 1 is a system diagram showing an embodiment of the present invention, Fig. 2 is a cross-sectional view showing the vicinity of the neutron detector of the fuel failure detection device in an enlarged manner, and Fig. 3 is a system diagram showing the neutron detector of the fuel failure detection device. FIG. 4, a system diagram of the fuel damage detection device, is a sectional view showing the structure around the neutron detector in the fuel damage detection device. 1... Reactor vessel 2... - Water cooling system intermediate heat exchanger 3... - Secondary cooling system main circulation pump 4... Piping 5... ...Secondary system piping 6
...Fuel damage detection device 7 ... Heat insulation layer 8 ... γ-ray shield 9 ... Neutron detector 10 ... Liquid sodium 11...
...Neutron shield 12...Opening 13...
... Frame 14 ... Throat 15 ...
・Bracket 16... Support body
Claims (1)
面を除き中性子遮蔽体で覆ってなるものを、γ線遮蔽体
の露出した面を一次冷却系中間熱交換器筺体外面に密着
させて取り付けたことを特徴とする燃料破損検出装置。A neutron detector is covered with a gamma ray shield, and the gamma ray shield is covered with the neutron shield except for one side, and the exposed surface of the gamma ray shield is tightly attached to the outer surface of the primary cooling system intermediate heat exchanger housing. A fuel damage detection device characterized in that it is installed with
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2099215A JPH03296693A (en) | 1990-04-17 | 1990-04-17 | Fuel breakdown detector |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2099215A JPH03296693A (en) | 1990-04-17 | 1990-04-17 | Fuel breakdown detector |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH03296693A true JPH03296693A (en) | 1991-12-27 |
Family
ID=14241434
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2099215A Pending JPH03296693A (en) | 1990-04-17 | 1990-04-17 | Fuel breakdown detector |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH03296693A (en) |
-
1990
- 1990-04-17 JP JP2099215A patent/JPH03296693A/en active Pending
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