JP2003066181A - Structure of moderator in moderation type instrument for measuring neutron spectrum - Google Patents

Structure of moderator in moderation type instrument for measuring neutron spectrum

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Publication number
JP2003066181A
JP2003066181A JP2001253812A JP2001253812A JP2003066181A JP 2003066181 A JP2003066181 A JP 2003066181A JP 2001253812 A JP2001253812 A JP 2001253812A JP 2001253812 A JP2001253812 A JP 2001253812A JP 2003066181 A JP2003066181 A JP 2003066181A
Authority
JP
Japan
Prior art keywords
moderator
neutrons
neutron
thermal
energy
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
Application number
JP2001253812A
Other languages
Japanese (ja)
Other versions
JP4670068B2 (en
Inventor
Yoshihiko Tanimura
嘉彦 谷村
Jun Saegusa
純 三枝
Michio Yoshizawa
道夫 吉澤
Makoto Yoshida
真 吉田
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.)
Japan Atomic Energy Agency
Original Assignee
Japan Atomic Energy Research Institute
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Filing date
Publication date
Application filed by Japan Atomic Energy Research Institute filed Critical Japan Atomic Energy Research Institute
Priority to JP2001253812A priority Critical patent/JP4670068B2/en
Publication of JP2003066181A publication Critical patent/JP2003066181A/en
Application granted granted Critical
Publication of JP4670068B2 publication Critical patent/JP4670068B2/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

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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

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  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Measurement Of Radiation (AREA)

Abstract

PROBLEM TO BE SOLVED: To provide a moderation type instrument for measuring neutron spectrum where a position-sensitive type thermal neutron detector is located in a neutron moderator and which measures the distribution of the energy of neutrons in a radiation field where neutrons that have various levels of energy exist. SOLUTION: The structure of a moderator in the measuring instrument is characterized in that the instrument can measure the position where neutrons are converted into thermal neutrons with high sensitivity by replacing a portion of the moderator on the surface side where the neutrons are incident, with a material whose hydrogen density is low and which has low performance of neutron moderation to enlarge the difference in the positions where the neutrons in a low-energy range are converted into the thermal neutrons and further, by placing a thermal neutron absorber in the moderator to restrain the thermal neutrons from diffusing.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【発明の属する技術分野】本発明は、様々なエネルギー
を持つ中性子が存在する放射線場において中性子エネル
ギー分布を測定する際に使用する減速型中性子スペクト
ル測定器の改良に関するものであり、中性子のエネルギ
ーを減衰させる減速材の構造を工夫することにより、低
エネルギー領域の中性子までエネルギーの測定を可能に
しようとするものである。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to an improvement of a moderator type neutron spectrum measuring instrument used for measuring a neutron energy distribution in a radiation field in which neutrons having various energies are present. By devising the structure of the moderator to be attenuated, the energy of neutrons in the low energy region can be measured.

【0002】[0002]

【従来の技術】減速型中性子スペクトル測定器とは図1
に示すように減速材と熱中性子を検出した位置が測定で
きる位置敏感型熱中性子検出器で構成されている。測定
器に入射した中性子は減速材の中を通り、次第にエネル
ギーを落とす。そして、最終的に熱中性子と呼ばれる非
常にエネルギーの低い中性子となる。図中に示すように
この熱中性子になる位置は入射したときの中性子エネル
ギーにより変化するため、どのような位置分布で熱中性
子が存在するかを測定することにより入射した中性子の
エネルギーが判る。そこで減速材の中心に、位置敏感型
熱中性子検出器を設置して減速材中での熱中性子分布を
測定できるような構造にしている。
2. Description of the Related Art What is a moderating neutron spectrum measuring device?
As shown in, it is composed of a moderator and a position-sensitive thermal neutron detector that can measure the position where the thermal neutron is detected. Neutrons incident on the measuring instrument pass through the moderator and gradually lose energy. And finally, it becomes a very low energy neutron called thermal neutron. As shown in the figure, the position of this thermal neutron changes depending on the neutron energy at the time of incidence, so the energy of the incident neutron can be found by measuring the position distribution in which the thermal neutron exists. Therefore, a position-sensitive thermal neutron detector is installed at the center of the moderator so that the thermal neutron distribution in the moderator can be measured.

【0003】従来の減速型中性子スペクトル測定器は、
図1に示すように一種類の減速材を用いており、中性子
を減速する性能の違う物質を組み合わせることや、熱中
性子を吸収する物質を減速材の中に入れるなどの工夫は
行われていない。このため、従来の測定器では低エネル
ギー領域の中性子のエネルギーを測定することは困難な
ものであった。
A conventional slow-down type neutron spectrum measuring instrument is
As shown in Fig. 1, one type of moderator is used, and no ingenuity has been made such as combining substances with different neutron moderating performance, or putting a substance that absorbs thermal neutrons into the moderator. . Therefore, it has been difficult to measure the energy of neutrons in the low energy region with the conventional measuring instrument.

【0004】[0004]

【発明が解決しようとする課題】減速材としてポリエチ
レンやパラフィンなどの中性子を減速させる性能の高い
物質を用いた場合、エネルギーの比較的低い中性子に対
して熱中性子に減速される位置の差は小さくなる。この
差を利用してエネルギー分布を求めるので、低いエネル
ギー領域の中性子でエネルギー分布を求めるのが困難と
なる。
When a substance having a high capability of slowing down neutrons such as polyethylene or paraffin is used as a moderator, the difference in the position where the thermal neutrons are slowed down is small with respect to the neutrons having relatively low energy. Become. Since the energy distribution is obtained using this difference, it is difficult to obtain the energy distribution with neutrons in the low energy region.

【0005】また、測定器に入射した中性子は熱中性子
にまで減速された後、減速材中を拡散する。そして、そ
の拡散距離は比較的長い。この熱中性子の拡散は、入射
中性子が熱中性子にまで減速された位置と、熱中性子検
出器で検出される位置をばらつかせることとなる(拡散
効果)。特に、熱中性子に減速される位置の差が小さい
比較的低いエネルギーの中性子に対してこの拡散効果は
顕著に現れる。このために低エネルギー領域の中性子に
対してエネルギー分布の測定が困難になる。以上二つの
課題を本発明により解決する。
Further, the neutrons incident on the measuring instrument are decelerated to thermal neutrons and then diffuse in the moderator. And the diffusion distance is relatively long. The diffusion of this thermal neutron causes the position where the incident neutron is decelerated to the thermal neutron and the position detected by the thermal neutron detector to scatter (diffusion effect). In particular, this diffusion effect appears remarkably for neutrons of relatively low energy in which the difference in position decelerated by thermal neutrons is small. This makes it difficult to measure the energy distribution for neutrons in the low energy region. The above two problems are solved by the present invention.

【0006】[0006]

【課題を解決するための手段】本発明は、減速材構造を
工夫することにより、減速型中性子スペクトル測定器の
低エネルギー領域の中性子に対するエネルギー測定性能
を改善するものである。性能の改善にあたり、測定器に
入射した低エネルギー領域の中性子が減速されて熱中性
子になる位置の差を大きく拡げること、及び減速されて
熱中性子となった中性子の減速材中での拡散効果を抑制
することの二点を実現するような工夫を行った。
The present invention is to improve the energy measuring performance of neutrons in the low energy region of a moderator neutron spectrum measuring instrument by devising a moderator structure. In improving the performance, neutrons in the low-energy region that are incident on the measuring instrument are decelerated to greatly expand the difference in the position where they become thermal neutrons, and the diffusion effect of the decelerated neutrons in the moderator to become thermal neutrons. We devised to realize the two points of suppression.

【0007】具体的には低エネルギー領域の中性子にお
いて熱中性子にまで減速される位置の差を拡げるため、
測定器の中性子入射面側に通常用いられるポリエチレン
やパラフィン減速材よりも水素密度が低い(中性子の減
速性能が低い)減速材を用いる。同時に高エネルギー領
域の中性子に対する減速性能を確保するため、反対側の
減速材にはポリエチレンやパラフィン等の水素密度が高
い(中性子の減速性能が高い)物質を用いる。熱中性子
の拡散効果に関しては、減速材中に熱中性子吸収材(カ
ドミウム、ホウ素など)を設置することにより抑制す
る。
Specifically, in order to widen the difference in the position where the neutrons in the low energy region are decelerated to thermal neutrons,
A moderator having a lower hydrogen density (lower neutron moderating performance) than the polyethylene or paraffin moderator normally used on the neutron incident surface side of the measuring instrument is used. At the same time, in order to secure moderation performance for neutrons in the high energy region, a material having a high hydrogen density (high neutron moderation performance) such as polyethylene or paraffin is used for the moderator on the opposite side. The diffusion effect of thermal neutrons is suppressed by installing a thermal neutron absorbing material (cadmium, boron, etc.) in the moderator.

【0008】熱中性子吸収材形状の決定に際して、あら
かじめ減速材に入射した中性子が熱中性子に減速される
位置の分布を入射する中性子のエネルギー毎に計算して
おく。そして計算で求められた熱中性子の減速材中での
入射軸方向及び径方向の分布形状より熱中性子吸収材の
形状を決定する。
In determining the shape of the thermal neutron absorber, the distribution of the positions where the neutrons that have entered the moderator are decelerated by the thermal neutrons is calculated for each energy of the incident neutrons. Then, the shape of the thermal neutron absorber is determined from the distribution shape of the thermal neutrons in the moderator in the incident axis direction and the radial direction obtained by calculation.

【0009】即ち、本発明は、中性子減速材中に位置敏
感型熱中性子検出器を配置した、様々なエネルギーを持
つ中性子が存在する放射線場で中性子エネルギー分布を
測定する減速型中性子スペクトル測定器において、前記
減速材の中性子入射面側の一部を水素密度が低く、中性
子の減速性能の低い物質に置き換えて、低エネルギー領
域の中性子が熱中性子に変換される位置の差を拡大する
ことにより、更に減速材中に熱中性子吸収材を配置して
熱中性子の拡散を抑制することにより、熱中性子への変
換位置を感度よく測定できることを特徴とする測定器の
減速材構造である。
That is, the present invention relates to a moderator type neutron spectrum measuring instrument in which a position-sensitive type thermal neutron detector is arranged in a neutron moderator and which measures a neutron energy distribution in a radiation field in which neutrons having various energies exist. , A low hydrogen density part of the neutron incident surface side of the moderator, by replacing the neutron moderating performance of a low substance, by expanding the difference in the position where neutrons in the low energy region are converted to thermal neutrons, Furthermore, the moderator structure of the measuring instrument is characterized in that the conversion position to thermal neutrons can be measured with high sensitivity by disposing a thermal neutron absorber in the moderator to suppress the diffusion of thermal neutrons.

【0010】[0010]

【発明の実施の形態】減速型中性子スペクトル測定器は
図1に示すような円柱形の中性子減速材の中心に位置敏
感型熱中性子検出器を配し、減速材中での熱中性子分布
の測定を可能にしたものである。そして、測定器に入射
する中性子のエネルギーにより減速材中における熱中性
子分布の形状が変化することを利用して中性子エネルギ
ーの測定を行う。
BEST MODE FOR CARRYING OUT THE INVENTION A moderator-type neutron spectrum measuring instrument is one in which a position-sensitive type thermal neutron detector is arranged at the center of a cylindrical neutron moderator as shown in FIG. 1 to measure the thermal neutron distribution in the moderator. Is made possible. Then, the neutron energy is measured by utilizing the fact that the shape of the thermal neutron distribution in the moderator changes due to the energy of the neutrons incident on the measuring instrument.

【0011】本発明では、上記減速型中性子スペクトル
測定器に関して、減速材構造の工夫を行うことにより、
低エネルギー領域の中性子でのエネルギー測定性能を向
上させる。減速材構造の工夫箇所は以下の二点である。
In the present invention, the moderator structure is devised for the moderator neutron spectrum measuring instrument described above,
Improve energy measurement performance with neutrons in the low energy region. There are the following two points in devising the moderator structure.

【0012】ポリエチレンやパラフィンなど水素密度の
高い物質では低エネルギー領域の中性子に対する減速性
能の差が小さいために、入射中性子が熱中性子に減速さ
れる位置の差が小さくなり、結果として、測定される熱
中性子分布の形状の変化が小さく、エネルギー測定が困
難となる。
Since substances having a high hydrogen density such as polyethylene and paraffin have a small difference in moderation performance with respect to neutrons in a low energy region, a difference in a position where incident neutrons are decelerated to thermal neutrons becomes small, and as a result, measurement is performed. The change in shape of the thermal neutron distribution is small, making energy measurement difficult.

【0013】この解決策としてポリカーボネートなどポ
リエチレン等と比べて水素密度の低い物質を減速材とし
て用いて、低エネルギー領域の中性子に対する減速性能
の差を拡げることが考えられる。ところが、減速材全体
を水素密度の低いポリカーボネートのような物質に変え
てしまうと、高エネルギー領域の中性子に対して十分な
減速性能を得ることができなくなる。そこで、本発明の
測定器では、ポリカーボネート減速材(中性子入射側)
とポリエチレン減速材とを組み合わせることにより、高
エネルギー領域の中性子に対する減速性能を確保しつ
つ、低エネルギー領域の中性子の減速性能の差を拡げる
ような減速材構造を実現した。
As a solution to this problem, it is conceivable to use a substance having a lower hydrogen density than polyethylene or the like as a moderator to widen the difference in moderating performance for neutrons in the low energy region. However, if the moderator as a whole is changed to a substance such as polycarbonate having a low hydrogen density, it becomes impossible to obtain sufficient moderator performance for neutrons in the high energy region. Therefore, in the measuring instrument of the present invention, the polycarbonate moderator (neutron incident side)
A moderator structure that widens the difference in moderator performance of neutrons in the low energy region while ensuring moderator performance for neutrons in the high energy region has been realized by combining with and a polyethylene moderator.

【0014】減速されて熱中性子となった中性子は減速
材中で比較的長い距離を拡散により移動し、熱中性子と
なった位置と熱中性子検出器で測定される位置をばらつ
かせてしまう拡散効果が起こる。そこで、減速材中に熱
中性子吸収材を設置し、拡散による熱中性子を選択的に
除去することにより、拡散効果を抑制する。これによ
り、拡散効果が顕著になる低エネルギー領域の中性子に
対するエネルギー測定性能を向上させる。熱中性子吸収
材の形状に関しては、あらかじめ減速材に入射した中性
子が減速されて熱中性子となる位置を計算しておき、そ
の結果より最適な形状を求める。
The neutrons that have been decelerated into thermal neutrons move by diffusion over a relatively long distance in the moderator, and diffuse the positions where they become thermal neutrons and the positions measured by the thermal neutron detectors. The effect occurs. Therefore, the diffusion effect is suppressed by installing a thermal neutron absorber in the moderator and selectively removing thermal neutrons due to diffusion. This improves the energy measurement performance for neutrons in the low energy region where the diffusion effect becomes remarkable. Regarding the shape of the thermal neutron absorber, the position where the neutrons incident on the moderator are decelerated to become thermal neutrons is calculated in advance, and the optimum shape is obtained from the result.

【0015】[0015]

【実施例】中性子減速材として一般的によく用いられる
ポリエチレン減速材のみを用いた場合、つまり本発明に
よる減速材構造の工夫を行わなかった場合について、何
種類かのエネルギーの中性子を測定したときの測定器か
らの出力をシミュレーション計算した結果を図2に示
す。エネルギーにより測定器出力の形状が異なっている
ほど、エネルギーの測定性能が高いということを表して
いるが、100keV以下のエネルギー領域では形状の差が
ほとんどなく、エネルギー測定性能が良くないことがわ
かる。
[Example] When neutrons of several kinds of energy are measured when only a polyethylene moderator that is commonly used as a neutron moderator is used, that is, when the moderator structure according to the present invention is not devised FIG. 2 shows the result of the simulation calculation of the output from the measuring instrument. It is shown that the energy measurement performance is higher as the shape of the measuring instrument output changes depending on the energy, but there is almost no shape difference in the low energy region of 100 keV or less, indicating that the energy measurement performance is poor. .

【0016】そこで、図3に示すように100cmある減速
材のうち、中性子入射側40cmの減速材をポリエチレンよ
りも水素密度が低く、中性子減速性能の低いポリカーボ
ネートに置き換え、残りの60cmの減速材をポリエチレン
とした。そして、減速材中に熱中性子吸収材(本発明の
実施例ではカドミウムを用いた)を設置するなど、本発
明による減速材構造の工夫を施した場合についてのシミ
ュレーション計算を行った。
Therefore, as shown in FIG. 3, of the 100 cm moderator, the moderator on the neutron incident side 40 cm was replaced with a polycarbonate having a lower hydrogen density and lower neutron moderating performance than polyethylene, and the remaining 60 cm moderator was used. Polyethylene was used. Then, a simulation calculation was performed for a case where the moderator structure according to the present invention was devised, such as installing a thermal neutron absorber (using cadmium in the examples of the present invention) in the moderator.

【0017】熱中性子吸収用カドミウム板の形状に関し
ては以下の要領で決定した。あらかじめ、中性子が減速
材中で減速され、どの位置で熱中性子となったかを様々
な入射中性子エネルギーについて計算を行う。そして入
射軸方向の熱中性子分布のピーク位置と径方向の熱中性
子拡がりとの相関をとり、図4に示すようなグラフを作
成する。グラフより減速材中に設置する熱中性子吸収用
カドミウム板の形状を決定する。図5に示す本発明によ
る工夫を施した測定器の出力の計算結果を見ると、本発
明による減速材構造の工夫を行わなかった第2図の結果
と比べて100keV以下の入射中性子エネルギーに対する熱
中性子分布形状に差異が観測されている。このことか
ら、本発明により低エネルギー領域の中性子に対するエ
ネルギー測定性能が向上することがわかる。
The shape of the cadmium plate for absorbing thermal neutrons was determined according to the following procedure. In advance, it is calculated for various incident neutron energies where the neutrons are decelerated in the moderator and where they become thermal neutrons. Then, the correlation between the peak position of the thermal neutron distribution in the incident axis direction and the thermal neutron spread in the radial direction is obtained, and a graph as shown in FIG. 4 is created. The shape of the cadmium plate for thermal neutron absorption installed in the moderator is determined from the graph. Looking at the calculation results of the output of the measuring device devised according to the present invention shown in FIG. 5, the heat for incident neutron energy of 100 keV or less is compared with the result of FIG. 2 without devising the moderator structure according to the present invention. Differences are observed in the neutron distribution shape. From this, it is understood that the present invention improves the energy measurement performance for neutrons in the low energy region .

【0018】[0018]

【発明の効果】中性子入射側の一部の減速材をポリエチ
レンから水素密度が低く、中性子減速能の低い物質に変
えることにより入射中性子のエネルギーによる減速材中
における熱中性子束分布形状の差を拡げることができ
る。
EFFECTS OF THE INVENTION By changing a part of the moderator on the neutron incident side from polyethylene to a substance having a low hydrogen density and a low neutron moderating ability, the difference in the thermal neutron flux distribution shape in the moderator due to the energy of incident neutrons is widened. be able to.

【0019】また、減速材中に熱中性子吸収材を減速材
に中性子を入射したときの熱中性子束分布形状に応じた
形状で設置することにより、位置情報の確度を低下さ
せ、エネルギー測定性能を悪くする要因となる熱中性子
の拡散を抑制できる。
Further, by disposing the thermal neutron absorbing material in the moderator in a shape corresponding to the thermal neutron flux distribution shape when neutrons are incident on the moderator, the accuracy of position information is lowered and the energy measurement performance is improved. It is possible to suppress the diffusion of thermal neutrons, which causes deterioration.

【0020】これらの構造により減速型中性子スペクト
ル測定器で大きく感度を低下させることなく熱中性子分
布形状の中性子エネルギーによる差を大きくし、より低
エネルギーの中性子にまでエネルギー測定性能を向上さ
せることが可能となる。
With these structures, it is possible to increase the difference in the thermal neutron distribution shape due to the neutron energy without significantly lowering the sensitivity in the moderator type neutron spectrum measuring instrument, and to improve the energy measurement performance even for lower energy neutrons. Becomes

【図面の簡単な説明】[Brief description of drawings]

【図1】 従来の減速型中性子スペクトル測定器の構造
を示す図である。
FIG. 1 is a view showing a structure of a conventional slowdown type neutron spectrum measuring instrument.

【図2】 従来の中性子減速材として単純なポリエチレ
ン減速材を用いた場合の測定器出力の各エネルギーの中
性子に対する計算結果を示す図である。
FIG. 2 is a diagram showing calculation results for neutrons of respective energies of a measuring instrument output when a simple polyethylene moderator is used as a conventional neutron moderator.

【図3】 本発明による減速材構造の工夫を行った減速
型中性子スペクトル測定器の構造を示す図である。
FIG. 3 is a view showing a structure of a moderator type neutron spectrum measuring device in which the moderator structure is devised according to the present invention.

【図4】 本発明の減速材中に設置する熱中性子吸収材
形状の決定例を示す図である。
FIG. 4 is a diagram showing an example of determining the shape of a thermal neutron absorbing material installed in the moderator of the present invention.

【図5】 本発明の減速材構造にした場合の減速型中性
子スペクトル測定器出力の各エネルギーの中性子に対す
る計算結果を示した図である。
FIG. 5 is a diagram showing calculation results for neutrons of respective energies of a moderator type neutron spectrum measuring instrument output when the moderator structure of the present invention is used.

───────────────────────────────────────────────────── フロントページの続き (72)発明者 吉澤 道夫 茨城県那珂郡東海村白方字白根2番地の4 日本原子力研究所東海研究所内 (72)発明者 吉田 真 茨城県那珂郡東海村白方字白根2番地の4 日本原子力研究所東海研究所内 Fターム(参考) 2G075 CA08 CA43 FA06 FA19 FA20 FC03 FC16    ─────────────────────────────────────────────────── ─── Continued front page    (72) Inventor Michio Yoshizawa             4 of 2 Shirane, Shikata, Tokai-mura, Naka-gun, Ibaraki Prefecture               Japan Atomic Energy Research Institute Tokai Research Center (72) Inventor Makoto Yoshida             4 of 2 Shirane, Shikata, Tokai-mura, Naka-gun, Ibaraki Prefecture               Japan Atomic Energy Research Institute Tokai Research Center F term (reference) 2G075 CA08 CA43 FA06 FA19 FA20                       FC03 FC16

Claims (2)

【特許請求の範囲】[Claims] 【請求項1】 減速型中性子スペクトル測定器におけ
る、減速性能の異なる複数の種類の減速材を組み合わせ
た減速材の構造。
1. A moderator structure in which a plurality of types of moderators having different moderating performances are combined in a moderator type neutron spectrum measuring instrument.
【請求項2】 減速型中性子スペクトル測定器におい
て、減速材中に適切な形状で熱中性子吸収材を設置した
減速材の構造。
2. The moderator neutron spectrum measuring instrument, wherein the moderator has a structure in which a thermal neutron absorber is installed in an appropriate shape in the moderator.
JP2001253812A 2001-08-24 2001-08-24 Moderator structure of moderator neutron spectrometer Expired - Fee Related JP4670068B2 (en)

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JP2007263783A (en) * 2006-03-29 2007-10-11 Toshiba Corp Device and method for measuring neutron flux, and reactor
JP2009204581A (en) * 2008-02-29 2009-09-10 Toshiba Corp Neutron measurement device and neutron measurement method
JP2011053218A (en) * 2009-09-02 2011-03-17 3833364 Canada Inc Neutron energy spectrometer
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JP2012052889A (en) * 2010-08-31 2012-03-15 Toshiba Corp Neutron measuring device
JP2013003104A (en) * 2011-06-21 2013-01-07 Toshiba Corp Subcriticality measuring apparatus and subcriticality measuring method
CN110018513A (en) * 2019-05-16 2019-07-16 东莞东阳光高能医疗设备有限公司 A kind of neutron spectrometer of polyhedral structure

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Publication number Priority date Publication date Assignee Title
JP2007263783A (en) * 2006-03-29 2007-10-11 Toshiba Corp Device and method for measuring neutron flux, and reactor
JP4690923B2 (en) * 2006-03-29 2011-06-01 株式会社東芝 Neutron flux measuring device, neutron flux measuring method, and nuclear reactor
JP2009204581A (en) * 2008-02-29 2009-09-10 Toshiba Corp Neutron measurement device and neutron measurement method
KR101058523B1 (en) 2008-12-08 2011-08-23 한국원자력연구원 Apparatus and method for measuring neutron energy distribution over a wide energy range
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JP2012052889A (en) * 2010-08-31 2012-03-15 Toshiba Corp Neutron measuring device
JP2013003104A (en) * 2011-06-21 2013-01-07 Toshiba Corp Subcriticality measuring apparatus and subcriticality measuring method
CN110018513A (en) * 2019-05-16 2019-07-16 东莞东阳光高能医疗设备有限公司 A kind of neutron spectrometer of polyhedral structure
CN110018513B (en) * 2019-05-16 2024-01-26 中国科学院高能物理研究所 Neutron spectrometer with polyhedral structure

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