JPS6010596B2 - Neutron detection device mounting structure - Google Patents

Neutron detection device mounting structure

Info

Publication number
JPS6010596B2
JPS6010596B2 JP51063237A JP6323776A JPS6010596B2 JP S6010596 B2 JPS6010596 B2 JP S6010596B2 JP 51063237 A JP51063237 A JP 51063237A JP 6323776 A JP6323776 A JP 6323776A JP S6010596 B2 JPS6010596 B2 JP S6010596B2
Authority
JP
Japan
Prior art keywords
detection device
mounting structure
device mounting
neutron detection
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
JP51063237A
Other languages
Japanese (ja)
Other versions
JPS52147296A (en
Inventor
誠 葛西
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.)
Toshiba Corp
Original Assignee
Tokyo Shibaura Electric 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 Tokyo Shibaura Electric Co Ltd filed Critical Tokyo Shibaura Electric Co Ltd
Priority to JP51063237A priority Critical patent/JPS6010596B2/en
Publication of JPS52147296A publication Critical patent/JPS52147296A/en
Publication of JPS6010596B2 publication Critical patent/JPS6010596B2/en
Expired 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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

【発明の詳細な説明】 本発明は商業炉、特に沸騰水型原子炉の局部出力領域中
性子検出集合体(以下LPRMと略称する)を有する中
性子検出装置取付構造に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a neutron detection device mounting structure having a local power range neutron detection assembly (hereinafter abbreviated as LPRM) for a commercial reactor, particularly a boiling water reactor.

IPRMは公知のように、炉内の中性子東情報を瞬時か
つ連続的に炉外へ達し、原子炉のより安全な運転、更に
は核燃料の効率的燃焼、すなわち燃料の経済性を図るた
めのモニターとして、原子炉炉心内の各所で多数個使わ
れるが、定検毎に行なわれるLPRM交換作業は特殊な
環境下なため放射線被曝は不可避なことが実情である。
そそれ故に交換作業における被爆量低減化が強く要望さ
れ、作業時間の規制、すなわち短時間の作業が最も一般
的に探られている。しかしながらこの方法は個人被曝量
は低減化できるが作業能率が低下するので人員の大量投
入の形となり、定検毎に行なわれる作業に対する人員確
保の点で大きな問題となっている。一般作業実績によれ
だ、LPRM交換作業は原子炉建屋の6階と原子炉圧力
容器の直下に設けられたべデスタルとの2個所で専用電
話等を使って同時に行なわれるが、ベデスタル内の雰囲
気の放射線量は150〜20印hR/hr(原子炉運開
後5年目実績)程度であり、法令で規定されている許容
被曝量を考慮すると、実動30分/日となり、約30名
の作業人員が必要となっている。
As is well known, IPRM is a monitor that instantly and continuously transmits neutron information inside the reactor to the outside of the reactor to ensure safer operation of the reactor and more efficient combustion of nuclear fuel, that is, fuel economy. Although large numbers of LPRMs are used at various locations within the reactor core, the reality is that radiation exposure is unavoidable as the LPRM replacement work that is carried out at every regular inspection is carried out under a special environment.
Therefore, there is a strong desire to reduce the amount of radiation exposure during replacement work, and regulation of work time, that is, short-time work is most commonly sought. However, although this method can reduce individual radiation exposure, it reduces work efficiency and requires a large number of personnel, which poses a major problem in terms of securing personnel for the work performed at each periodic inspection. According to general work records, LPRM replacement work is carried out simultaneously at two locations, on the 6th floor of the reactor building and in the vedestal located directly below the reactor pressure vessel, using dedicated telephones, etc. The radiation dose is approximately 150 to 20 hR/hr (actual results in the 5th year after the reactor started operation), and considering the permissible exposure amount stipulated by law, the actual operation time is 30 minutes/day, and approximately 30 people work. Personnel are needed.

将来各地で原子炉が稼動を開始し、定検が重なるように
なった場合0を想定すると人員確保が極めて困難になる
ことが明瞭である。原子炉連関後、運転時間と共に中性
子照射の影響で炉体構造物の放射化が進み、周囲の放射
線量が増大する煩向は避けられないので、LPRM自体
夕に蓄積される高汚染物質(以下クラッドと略称する)
の量を減らし、交換作業時の被爆量を少なくすることが
要望されている。
It is clear that if nuclear reactors start operating in various places in the future and periodic inspections begin to overlap, it will be extremely difficult to secure personnel if we assume zero. After being linked to a nuclear reactor, activation of the reactor body structure progresses due to the influence of neutron irradiation as the operating time progresses, and it is inevitable that the radiation dose in the surrounding area will increase. (abbreviated as clad)
There is a desire to reduce the amount of radiation exposure during replacement work.

LPR船こクラッドが蓄積すると考えられる個所を図面
をもとに詳述する。
The locations where crud is expected to accumulate on LPR ships will be explained in detail based on drawings.

第1図a,bにおいて0 11‘ま原子炉圧力容器、1
2は核燃料集合体、13はインコア案内管、14はLP
RM本体、45は合フランジ、16はパッキング、17
はフランジ固定用ボルト「 18‘まLPRM本体を固
定保持するための特殊ナットであり、図示のようにイン
コアタ案内管13をLPRM本体14との間隙にクラッ
ド19が、またLPRM本14の内部には検出器感度鮫
正に必要な鮫正用案内管14aと検出器14bとが収納
されており、それらの間にクラッド20が蓄積される。
これらクラッド19,20は原子炉の定常運転時に炉内
、すなわち炉水中を浮遊しながらついには下部にたまり
、その沈澱量は運転時間と共に増大することが知られて
いる。
In Figure 1 a and b, 0 11' reactor pressure vessel, 1
2 is a nuclear fuel assembly, 13 is an in-core guide tube, 14 is an LP
RM body, 45 is a mating flange, 16 is packing, 17
The flange fixing bolt "18' is a special nut for fixing and holding the LPRM main body. As shown in the figure, there is a clad 19 in the gap between the incoater guide tube 13 and the LPRM main body 14, and a cladding 19 inside the LPRM main body 14. A guide tube 14a for shark adjustment and a detector 14b necessary for detector sensitivity adjustment are housed, and cladding 20 is accumulated between them.
It is known that these cruds 19 and 20 float inside the reactor, that is, in the reactor water, during steady operation of the nuclear reactor and eventually accumulate in the lower part, and the amount of sedimentation increases with operating time.

クラツド19,20の蓄積される場所が交換作業時に、
作業者の頭の位置付近となることが作業を困難にしてい
る所以である。本発明は以上の事情に鑑みなされたもの
であり、クラッドの発生と蓄積とが避けられない事実で
あることから、クラッドの蓄積する場所を作業時に影響
を及ぼさない範囲まで離すことができる構造とし、これ
により被曝量の低減を確実に得るものである。
The place where cruds 19 and 20 are accumulated during replacement work,
The location near the worker's head makes the work difficult. The present invention was developed in view of the above circumstances, and since the occurrence and accumulation of crud is an unavoidable fact, the present invention is designed to have a structure that allows the location where crud accumulates to be separated to the extent that it does not affect the work. This ensures a reduction in radiation exposure.

以下図面をもとに本発明を詳述する。The present invention will be explained in detail below based on the drawings.

なお同一部分は同一符号で表わす。第2図a,b及び第
3図a,bにおいてLPRM本体1 1の内部の途中に
クラッドを蓄積させるための仕切板21を設け、この仕
切板21を固定保持するのにピン22が便わる。このピ
ン22所定位置に菱込まれた後、例えば溶接等により先
端部が溶着され、円周面の精かごを保ち仕切板21の完
全固定の役目を果している。この仕切板21の位置は交
換時を想定した場合、作業者より約6〜7m離れたとこ
ろに選び、これにより仕切板21の上部に蓄積するクラ
ツド20から直接の被曝を防ぐようにしている。
Note that the same parts are represented by the same symbols. In FIGS. 2a, b and 3 a, b, a partition plate 21 for accumulating crud is provided halfway inside the LPRM body 11, and pins 22 are used to securely hold this partition plate 21. . After this pin 22 is inserted into a predetermined position, the tip end is welded, for example, by welding, etc., and serves to completely fix the partition plate 21 while maintaining a fine cage on the circumferential surface. The position of this partition plate 21 is selected to be approximately 6 to 7 meters away from the operator when it is assumed to be replaced, thereby preventing direct exposure to radiation from the crud 20 that accumulates on the upper part of the partition plate 21.

そしてLPRMの外周部、すなわちLPRM本体竃4と
ィンコア案内管13との間に蓄積するクラツドを上方で
蓄積する。即ちLPRM本体1 4はスプリング23で
下方に押圧されているガイドリング24を有し、スプリ
ング23、ガイドリング24は上下ストッパー25,2
6の間に保持されている。LPRM本体14の装着時に
はガイドリング24はィンコア案内管13の内面のテー
パ部27で面接触固定され、炉水中を浮遊するクラッド
19を図示のようにとらえ、クラツドのLPRMの下端
部への移動を防止している。本発明の一実施例について
更に付記すると、LPRMの主構成材がステンレス(S
US304)、仕切板、ピンおよびガイドリングも向く
ステンレス(SUS304)から成り、スリング23に
はインコネルX−750を使用することが望ましい。
The crud that accumulates on the outer periphery of the LPRM, that is, between the LPRM main body 4 and the inner core guide tube 13, is accumulated above. That is, the LPRM main body 14 has a guide ring 24 that is pressed downward by a spring 23, and the spring 23 and guide ring 24 are connected to upper and lower stoppers 25, 2.
It is held between 6 and 6. When the LPRM main body 14 is installed, the guide ring 24 is fixed in surface contact with the tapered part 27 on the inner surface of the in-core guide tube 13, catches the crud 19 floating in the reactor water as shown in the figure, and prevents the crud from moving to the lower end of the LPRM. It is prevented. To further note about one embodiment of the present invention, the main constituent material of the LPRM is stainless steel (S
The sling 23 is preferably made of Inconel X-750.

以上詳述した本発明の特徴を列挙すると次のようになる
。{1} 内部クラツド対策として設けた仕切板は機械
加工が比較的容易な上、取付けが簡単である。
The features of the present invention detailed above are enumerated as follows. {1} The partition plate provided as a countermeasure against internal cladding is relatively easy to machine and easy to install.

加えて被曝低減に寄与するところが極めて大である。【
2} 外部クラッド対策として探られたスプリング式ガ
イドリングは被曝低減効果の大なる点は‘1}と同様で
あるが、原子炉運転時のLPRMの振動等を軽減化させ
る役目も兼ねている。
In addition, it greatly contributes to reducing radiation exposure. [
2} The spring-type guide ring, which was explored as a countermeasure for external cladding, is similar to '1} in that it has a large radiation exposure reduction effect, but also serves to reduce vibrations of the LPRM during reactor operation.

‘3’被爆量低減効果大の割に材料費は無視できる程少
ないo
'3' Material costs are negligible despite the large effect of reducing radiation exposure.

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

第1図aは従釆のLPRMの装着部の要部断面図、同図
bはそのA部の拡大断面図、第2図aは本発明の実施例
を示す要部断面図、同図bはそのB−B線に沿う断面図
、第3図aはその一部切断部分図、同図bはそのC部の
拡大図である。 11…原子炉圧力容器、13・・・ィンコア案内管、1
4・・・LPRM本体、21・・・仕切板、23・・・
スプリング、24…ガイドリング、27…テ…パ部。 第1図 第2図 第3図
Figure 1a is a cross-sectional view of the main part of the attachment part of the secondary LPRM, Figure b is an enlarged cross-sectional view of part A, Figure 2a is a cross-sectional view of the main part showing the embodiment of the present invention, Figure b 3 is a sectional view taken along line B-B, FIG. 3a is a partially cutaway view, and FIG. 3b is an enlarged view of section C. 11... Reactor pressure vessel, 13... In-core guide pipe, 1
4... LPRM body, 21... Partition plate, 23...
Spring, 24...Guide ring, 27...Taper part. Figure 1 Figure 2 Figure 3

Claims (1)

【特許請求の範囲】[Claims] 1 原子炉圧力容器11内に設けられたインコア案内管
13の内側に局部出力領域中性子検出器集合体本体14
が挿通されてなる中性子検出装置取付構造において、上
記集合体本体14の内部の途中に仕切板21が設けられ
、且つ集合体本体14の外周部にスプリングで押圧され
るガイドリング24が設けられてなるとともに該ガイド
リング24が上記インコア案内管13の内面テーパ部2
7に接触され係止されてなることを特徴とする中性子検
出装置取付構造。
1 Local power range neutron detector assembly main body 14 is installed inside the in-core guide pipe 13 provided in the reactor pressure vessel 11.
In the neutron detection device mounting structure, a partition plate 21 is provided halfway inside the assembly body 14, and a guide ring 24 pressed by a spring is provided on the outer periphery of the assembly body 14. At the same time, the guide ring 24 is connected to the inner surface tapered portion 2 of the in-core guide tube 13.
7. A neutron detection device mounting structure, characterized in that the neutron detection device mounting structure is in contact with and locked by 7.
JP51063237A 1976-05-31 1976-05-31 Neutron detection device mounting structure Expired JPS6010596B2 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP51063237A JPS6010596B2 (en) 1976-05-31 1976-05-31 Neutron detection device mounting structure

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP51063237A JPS6010596B2 (en) 1976-05-31 1976-05-31 Neutron detection device mounting structure

Publications (2)

Publication Number Publication Date
JPS52147296A JPS52147296A (en) 1977-12-07
JPS6010596B2 true JPS6010596B2 (en) 1985-03-18

Family

ID=13223401

Family Applications (1)

Application Number Title Priority Date Filing Date
JP51063237A Expired JPS6010596B2 (en) 1976-05-31 1976-05-31 Neutron detection device mounting structure

Country Status (1)

Country Link
JP (1) JPS6010596B2 (en)

Also Published As

Publication number Publication date
JPS52147296A (en) 1977-12-07

Similar Documents

Publication Publication Date Title
US4416848A (en) Device for fixing a guide tube
JPH04268497A (en) Reactor-core instrumentaion apparatus in pressurized water reactor
JPH0644064B2 (en) Extension device for thimble guide in nuclear reactor
US4778647A (en) Vibration-damping extender for a thimble guide
US6091791A (en) Shroud attachment for a boiling water reactor
JPS6010596B2 (en) Neutron detection device mounting structure
JPH07325189A (en) Vibration monitor
JP3456783B2 (en) How to replace core shroud
Lubin et al. Analysis of internals vibration monitoring and loose part monitoring systems data related to the St. Lucie 1 thermal shield failure
JP2519316B2 (en) Repair method for long housing and repair structure
JPS6355496A (en) Nuclear reactor
JPS6339676Y2 (en)
JP2703969B2 (en) Closure device for neutron flux monitor housing
JPH10142369A (en) Boiling water reactor
JPH08233971A (en) Nuclear reactor core shroud and method for manufacturing and repairing it
JP3425217B2 (en) Sealing device for repairing pressure vessel penetration housing
JPH0346795B2 (en)
JPS58156Y2 (en) Shielding structure of reactor shielding wall opening
JPS6046489A (en) Pressure vessel for nuclear reactor
JPH02102490A (en) Supporting device for neutron flux monitor housing
Ting The safety evaluations of age-related-degradation of BWR-4 vessel internals in Taiwan nuclear power plant
JPH11133185A (en) Reactor bottom part shielding body for nuclear reactor preventive maintenance
KR830001692B1 (en) Guide tube fixture of reactor fuel assembly
JPS59102190A (en) Control rod drive mechanism
JPH0298695A (en) Method for repairing neutron flux monitor housing