JPH0439637B2 - - Google Patents
Info
- Publication number
- JPH0439637B2 JPH0439637B2 JP58174998A JP17499883A JPH0439637B2 JP H0439637 B2 JPH0439637 B2 JP H0439637B2 JP 58174998 A JP58174998 A JP 58174998A JP 17499883 A JP17499883 A JP 17499883A JP H0439637 B2 JPH0439637 B2 JP H0439637B2
- Authority
- JP
- Japan
- Prior art keywords
- neutron
- shielding member
- deceleration
- heat insulating
- shielding
- 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 - Lifetime
Links
- 239000000446 fuel Substances 0.000 claims description 24
- 238000001514 detection method Methods 0.000 claims description 23
- 239000002826 coolant Substances 0.000 claims description 8
- 230000004992 fission Effects 0.000 claims description 8
- 239000003758 nuclear fuel Substances 0.000 claims description 6
- 230000003111 delayed effect Effects 0.000 claims description 4
- 238000006073 displacement reaction Methods 0.000 claims description 4
- 239000000463 material Substances 0.000 description 4
- 239000011358 absorbing material Substances 0.000 description 3
- 239000000835 fiber Substances 0.000 description 3
- 238000001816 cooling Methods 0.000 description 2
- 230000005251 gamma ray Effects 0.000 description 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 1
- 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 1
- 150000001722 carbon compounds Chemical class 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 229910002804 graphite Inorganic materials 0.000 description 1
- 239000010439 graphite Substances 0.000 description 1
- 238000009413 insulation Methods 0.000 description 1
- 230000009191 jumping Effects 0.000 description 1
- 229910001338 liquidmetal Inorganic materials 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 239000012188 paraffin wax Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 229920003002 synthetic resin Polymers 0.000 description 1
- 239000000057 synthetic resin Substances 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
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
［発明の技術分野］
本発明は原子炉容器に開口する配管から流出す
る冷却材に含まれる核分裂生成物の量を遅発中性
子検出法で測定し、原子炉容器内に配設される核
燃料の破損を検出する破損燃料検出装置に関す
る。Detailed Description of the Invention [Technical Field of the Invention] The present invention uses a delayed neutron detection method to measure the amount of fission products contained in the coolant flowing out from piping opening into the reactor vessel. The present invention relates to a damaged fuel detection device for detecting damage to nuclear fuel installed in a nuclear fuel.
［発明の技術的背景］
第１図は破損燃料検出装置の配設される高速増
殖炉を示すもので、図において符号１は炉心２を
収容する原子炉容器を示しており、この原子炉容
器１の上端開口部は遮蔽プラグ３により遮蔽され
ている。[Technical Background of the Invention] Fig. 1 shows a fast breeder reactor in which a damaged fuel detection device is installed. The upper end opening of 1 is shielded by a shielding plug 3.
この原子炉容器１は、例えばコンクリート遮蔽
壁４で囲まれた原子炉室内に収容されており、こ
の遮蔽壁４に穿設される貫通孔５には炉心２内の
核分裂による熱エネルギを得た例えば液体金属ナ
トリウムからなる１次冷却材を図示しない熱交換
器に移送する１次系配管６が挿通されている。 The reactor vessel 1 is housed in a reactor chamber surrounded by, for example, a concrete shielding wall 4, and a through hole 5 formed in the shielding wall 4 receives thermal energy from nuclear fission within the reactor core 2. For example, a primary system piping 6 for transferring a primary coolant made of liquid metal sodium to a heat exchanger (not shown) is inserted therethrough.
この１次系配管６は、遮蔽壁４の外側において
例えばコの字形状に屈曲した後、図示しない熱交
換器に接続される。１次系配管６のコの字形状底
部には、１次配管６を流れる冷却材に含まれる核
分裂生成物の量を測定する破損燃料検出装置７が
配設されている。 This primary system piping 6 is bent into, for example, a U-shape outside the shielding wall 4, and then connected to a heat exchanger (not shown). A damaged fuel detection device 7 that measures the amount of fission products contained in the coolant flowing through the primary pipe 6 is disposed at the U-shaped bottom of the primary pipe 6 .
第２図はこのような破損燃料検出装置７を示す
もので、図において符号６は１次系配管を示して
いる。１次系配管６を囲繞して保温部材８が配設
されており、この保温部材８を囲繞し、かつ間隔
をおいて中性子減速遮蔽部材９が配設されてい
る。中性子減速遮蔽部材９の軸方向中央下部は断
面コの字形状に形成され、この部には中性子検出
器１０が配設されている。中性子検出器１０はγ
線遮蔽部材１１により囲繞されており、さらにこ
のγ線遮蔽部材１１は熱中性子吸収材１２により
囲繞されている。 FIG. 2 shows such a damaged fuel detection device 7, and in the figure, reference numeral 6 indicates the primary system piping. A heat insulating member 8 is disposed surrounding the primary system piping 6, and a neutron deceleration shielding member 9 is disposed surrounding the heat insulating member 8 and at intervals. The central lower part of the neutron deceleration shielding member 9 in the axial direction is formed into a U-shaped cross section, and a neutron detector 10 is disposed in this part. The neutron detector 10 has γ
It is surrounded by a radiation shielding member 11, and further, this gamma ray shielding member 11 is surrounded by a thermal neutron absorbing material 12.
以上のように構成された破損燃料検出装置７で
は、炉心２内に収容される核燃料が破損した場合
には、核分裂生成分が冷却材とともに１次配管６
を流通することとなるため、冷却材に含まれる核
分裂生成物から放出される遅発中性子を、この破
損燃料検出装置７により測定することにより核燃
料の破損を検出することができる。 In the damaged fuel detection device 7 configured as described above, when the nuclear fuel housed in the reactor core 2 is damaged, fission products are sent to the primary pipe 6 along with the coolant.
Therefore, damage to the nuclear fuel can be detected by measuring delayed neutrons emitted from the fission products contained in the coolant using the damaged fuel detection device 7.
［背景技術の問題点］
しかしながら、以上のように構成された破損燃
料検出装置７では、コンクリート遮蔽壁４の１次
系配管６を挿通する貫通孔５と１次系配管６との
間に多大な間隙が形成されているため、炉心２で
発生する中性子は、この間隙を通り破損燃料検出
装置７の保温部材８と中性子減速遮蔽部材９との
間の間隙を通つた後、中性子検出器１０に飛び込
むこととなる。[Problems with Background Art] However, in the damaged fuel detection device 7 configured as described above, there is a large amount of space between the through hole 5 through which the primary system piping 6 of the concrete shielding wall 4 is inserted and the primary system piping 6. Since a gap is formed, neutrons generated in the core 2 pass through this gap and pass through the gap between the heat insulating member 8 of the damaged fuel detection device 7 and the neutron deceleration shielding member 9, and then reach the neutron detector 10. I will jump into it.
この結果、燃料破損に伴つて１次系配管６を流
通する冷却材に含まれることとなつた核分裂生成
物から放出される遅発中性子を検出する中性子検
出器１０のＳ／Ｎ比が大幅に低下することとな
る。 As a result, the S/N ratio of the neutron detector 10, which detects delayed neutrons emitted from fission products that are included in the coolant flowing through the primary system piping 6 due to fuel failure, is significantly increased. This will result in a decline.
なお第２図において保温部材８と中性子減速遮
蔽部材９との間に形成される間隙は、１次系配管
６の振動および１次系配管６の熱膨張による移動
を考慮して形成されている。 Note that in FIG. 2, the gap formed between the heat retaining member 8 and the neutron deceleration shielding member 9 is formed in consideration of vibration of the primary system piping 6 and movement due to thermal expansion of the primary system piping 6. .
また、中性子検出器１０のノイズとなるバツク
グランド中性子の90％以上は、この間隙または密
度の低い保温部材８や１次系配管６内部を通り中
性子検出器１０に到達する。 Further, 90% or more of the background neutrons that cause noise in the neutron detector 10 reach the neutron detector 10 through this gap or through the low-density heat insulating member 8 and the inside of the primary system piping 6.
［発明の目的］
本発明はかかる従来の事情に対処してなされた
もので、バツクグランド中性子の中性子検出器へ
の飛び込みを防止し、中性子検出器のＳ／Ｎ比を
従来に比べ大幅に向上することのできる破損燃料
検出装置を提供しようとするものである。[Object of the Invention] The present invention has been made in response to such conventional circumstances, and it prevents background neutrons from jumping into a neutron detector, and significantly improves the S/N ratio of the neutron detector compared to the conventional one. The present invention aims to provide a damaged fuel detection device capable of detecting damaged fuel.
［発明の概要］
すなわち本発明は、原子炉容器に開口する配管
から流出する冷却材に含まれる核分裂生成物の量
を測定し前記原子炉容器内に配設される核燃料の
破損を検出する破損燃料検出装置において、前記
配管を囲繞して配設された保温部材の外側に設置
される中性子検出器と、前記保温部材および前記
中性子検出器を間隔をおいて囲繞する第１の中性
子減速遮蔽部材と、前記第１の中性子減速遮蔽部
材と前記保温部材との間の間〓を、少なくとも前
記中性子検出器の両側において閉塞するように配
設された中性子減速遮蔽部材であつて、前記配管
の熱変位および振動に応じて変形可能に構成され
た第２の中性子減速遮蔽部材とを備えたことを特
徴とする破損燃料検出装置である。[Summary of the Invention] That is, the present invention provides a method for detecting damage to nuclear fuel disposed within the reactor vessel by measuring the amount of fission products contained in the coolant flowing out from a pipe opening into the reactor vessel. In the fuel detection device, a neutron detector is installed outside a heat insulating member disposed surrounding the pipe, and a first neutron deceleration shielding member surrounds the heat insulating member and the neutron detector at a distance. and a neutron deceleration shielding member disposed to close a gap between the first neutron deceleration shielding member and the heat insulating member at least on both sides of the neutron detector, This is a damaged fuel detection device characterized by comprising a second neutron deceleration shielding member configured to be deformable in response to displacement and vibration.
［発明の実施例］
以下本発明の詳細を図面に示す一実施例につい
て説明する。[Embodiment of the Invention] The details of the present invention will be described below with reference to an embodiment shown in the drawings.
第３図および第４図は本発明の一実施例の破損
燃料検出装置を示すもので、図において符号１５
は保温部材８と外側中性子減速遮蔽部材９（第１
の中性子減速遮蔽部材）との間〓を遮蔽する中性
子減速遮蔽部材（第２の中性子減速遮蔽部材）を
示している。 3 and 4 show a damaged fuel detection device according to an embodiment of the present invention, and in the figures, reference numeral 15
The heat insulating member 8 and the outer neutron deceleration shielding member 9 (first
A neutron deceleration shielding member (a second neutron deceleration shielding member) is shown for shielding between the neutron deceleration shielding member and the neutron deceleration shielding member.
この中性子減速遮蔽部材１５は、破損燃料検出
装置の周囲に配設される外側中性子減速遮蔽部材
９の内側にかつ中性子検出器１０の両側に１次冷
却配管６の保温部材８を囲繞して配設される内側
中性子減速遮蔽部材１６、さらに配管の熱変位、
振動を吸収する為の弾性中性子遮蔽部材１７とか
ら構成されている。そして外側中性子減速遮蔽部
材９は中性子減速の大きい黒鉛またはパラフイン
や合成樹脂のような含水炭素化合物から構成され
ており、また内側中性子減速遮蔽部材１６は、例
えばB4C等の中性子吸収材あるいは外側中性子減
速遮蔽部材９と同様の素材から構成されている。 This neutron moderation shielding member 15 is disposed inside the outer neutron moderation shielding member 9 disposed around the damaged fuel detection device and on both sides of the neutron detector 10 so as to surround the heat insulating member 8 of the primary cooling pipe 6. The inner neutron deceleration shielding member 16 provided, furthermore, the thermal displacement of the piping,
It is composed of an elastic neutron shielding member 17 for absorbing vibrations. The outer neutron deceleration shielding member 9 is made of a hydrated carbon compound such as graphite, paraffin, or synthetic resin that has a large neutron deceleration, and the inner neutron deceleration shielding member 16 is made of a neutron absorbing material such as B 4 C or the outer It is made of the same material as the neutron deceleration shielding member 9.
弾性中性子遮蔽部材１７は、スポンジ状の中性
子減速吸収材又は布状またはメシユ状の中性子減
速遮蔽材（B4C含有繊維、LiF含有繊維、BN繊
維）よりなり、運転時と停止時の配管の熱変位
（約10cm）を考慮して、運転時に中性子減速遮蔽
部材９，１６と保温部材８との間の間隙を埋める
位置に保温部材８のまわりに巻かれる。また、こ
の弾性中性子遮蔽部材１７は、保温特性も有して
おり、保温部材中に埋設することも実施例の一つ
とする。 The elastic neutron shielding member 17 is made of a sponge-like neutron moderating/absorbing material or a cloth-like or mesh-like neutron moderating/shielding material (B 4 C-containing fiber, LiF-containing fiber, BN fiber), and is used to protect piping during operation and stop. Taking thermal displacement (approximately 10 cm) into consideration, it is wound around the heat insulating member 8 at a position that fills the gap between the neutron deceleration shielding members 9, 16 and the heat insulating member 8 during operation. Moreover, this elastic neutron shielding member 17 also has a heat-retaining property, and in one embodiment, it may be embedded in a heat-retaining member.
なお以上述べた部分を除いて第２図に示した破
損燃料検出装置と同様に構成されているので、同
一部分には同一符号を付して説明を省略する。 It should be noted that, except for the parts described above, the structure is the same as that of the damaged fuel detection device shown in FIG. 2, so the same parts are given the same reference numerals and the explanation thereof will be omitted.
以上のように構成された破損燃料検出装置で
は、従来保温部材８と外側中性子減速遮蔽部材９
との間隙または密度の低い保温部材８や一次冷却
配管６の内部を通り中性子検出器１０に飛び込ん
でいたバツクグランド中性子は、内側中性子減速
遮蔽部材１６、および弾性中性子遮蔽材１７によ
り遮蔽され、中性子検出器１０に飛び込むことは
なくなりＳ／Ｎ比を従来に比較し、２〜４倍向上
することができる。 In the damaged fuel detection device configured as described above, the conventional heat insulating member 8 and the outer neutron deceleration shielding member 9
The background neutrons that had flown into the neutron detector 10 through the gap between the inner neutron decelerating member 16 and the elastic neutron shielding member 17 through the low-density heat insulating member 8 or the inside of the primary cooling pipe 6 are blocked by the inner neutron moderation shielding member 16 and the elastic neutron shielding member 17, There is no need to jump into the detector 10, and the S/N ratio can be improved by 2 to 4 times compared to the conventional method.
この結果、破損燃料の検出精度が向上し、原子
炉事故の拡大を未然に防止することができる。 As a result, the accuracy of detecting damaged fuel is improved, and the spread of nuclear reactor accidents can be prevented.
［発明の効果］
以上述べたように本発明の破損燃料検出装置に
よれば、中性子検出器Ｓ／Ｎ比を従来に比べ大幅
に向上することができ、破損燃料の検出精度を大
幅に向上することができる。[Effects of the Invention] As described above, according to the damaged fuel detection device of the present invention, the neutron detector S/N ratio can be significantly improved compared to the conventional one, and the detection accuracy of damaged fuel can be greatly improved. be able to.
第１図は破損燃料検出装置を備えた高速増殖炉
を示す縦断面図、第２図は従来の破損燃料検出装
置の一実施例を示す縦断面図、第３図は本発明の
一実施例の破損燃料検出装置を示す縦断面図、第
４図は第３図の−線に沿う横断面図である。
１……原子炉容器、２……炉心、３……遮蔽プ
ラグ、４……遮蔽壁、５……貫通孔、６……１次
系配管、７……破損燃料検出装置、８……保温部
材、９……中性子減速遮蔽部材、１０……中性子
検出器、１１……ガンマ線遮蔽材、１２……熱中
性子遮蔽材、１５……中性子減速遮蔽部材、１６
……内側中性子減速遮蔽部材、１７……可動又は
弾性中性子遮蔽材。
FIG. 1 is a longitudinal sectional view showing a fast breeder reactor equipped with a damaged fuel detection device, FIG. 2 is a longitudinal sectional view showing an embodiment of a conventional damaged fuel detection device, and FIG. 3 is an embodiment of the present invention. FIG. 4 is a cross-sectional view taken along the - line in FIG. 3. FIG. 1...Reactor vessel, 2...Reactor core, 3...Shielding plug, 4...Shielding wall, 5...Through hole, 6...Primary system piping, 7...Damaged fuel detection device, 8...Heat insulation Member, 9... Neutron deceleration shielding member, 10... Neutron detector, 11... Gamma ray shielding material, 12... Thermal neutron shielding material, 15... Neutron deceleration shielding member, 16
...Inner neutron deceleration shielding member, 17...Movable or elastic neutron shielding member.
Claims (1)
材に含まれる核分裂生成物の量を遅発中性子検出
法で測定し前記原子炉容器内に配設される核燃料
の破損を検出する破損燃料検出装置において、 前記配管を囲繞して配設された保温部材の外側
に設置される中性子検出器と、 前記保温部材および前記中性子検出器を間隔を
おいて囲繞する第１の中性子減速遮蔽部材と、 前記第１の中性子減速遮蔽部材と前記保温部材
との間の間〓を、少なくとも前記中性子検出器の
両側において閉塞するように配設された中性子減
速遮蔽部材であつて、前記配管の熱変位および振
動に応じて変形可能に構成された第２の中性子減
速遮蔽部材と を備えたことを特徴とする破損燃料検出装置。[Claims] 1. Measure the amount of fission products contained in the coolant flowing out from the pipe opening into the reactor vessel using a delayed neutron detection method to detect damage to the nuclear fuel disposed within the reactor vessel. A neutron detector installed outside a heat insulating member disposed surrounding the piping, and a first neutron detector surrounding the heat insulating member and the neutron detector at intervals. a neutron deceleration shielding member; a neutron deceleration shielding member disposed to close a space between the first neutron deceleration shielding member and the heat insulating member at least on both sides of the neutron detector; A damaged fuel detection device comprising: a second neutron deceleration shielding member configured to be deformable in response to thermal displacement and vibration of piping.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58174998A JPS6066195A (en) | 1983-09-21 | 1983-09-21 | Damaged fuel detector |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58174998A JPS6066195A (en) | 1983-09-21 | 1983-09-21 | Damaged fuel detector |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6066195A JPS6066195A (en) | 1985-04-16 |
| JPH0439637B2 true JPH0439637B2 (en) | 1992-06-30 |
Family
ID=15988425
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58174998A Granted JPS6066195A (en) | 1983-09-21 | 1983-09-21 | Damaged fuel detector |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6066195A (en) |
-
1983
- 1983-09-21 JP JP58174998A patent/JPS6066195A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6066195A (en) | 1985-04-16 |
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