JPS59214795A - Neutron detector for measuring nuclear away from reactor - Google Patents
Neutron detector for measuring nuclear away from reactorInfo
- Publication number
- JPS59214795A JPS59214795A JP58089528A JP8952883A JPS59214795A JP S59214795 A JPS59214795 A JP S59214795A JP 58089528 A JP58089528 A JP 58089528A JP 8952883 A JP8952883 A JP 8952883A JP S59214795 A JPS59214795 A JP S59214795A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- neutron detector
- neutron
- away
- detector
- 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
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)
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】
この発明は原子炉の中性子モニタリングに関するもので
ある。DETAILED DESCRIPTION OF THE INVENTION This invention relates to neutron monitoring of nuclear reactors.
従来この柿の装置として第1図に示すものがあった。第
1図において(11は原子炉容器、(2)は原子炉容器
の高さ方向(X方向とする)の中性子束分布ψ伏)ヲ表
す曲線である。(3)に原子炉容器(11の高さの方向
と平行に配置された炉外核計測用4分割中性子検出器、
(41〜(7)は検出器(31内部に組込まれた検出素
子で、従来の装置ではこれら検出素子は互に等間隔にか
つ検出器(31の中心対称に配置される。すなわち、原
子炉容器(1)の底面位置e x = Or頂面位置f
x=tとすれば、素子141〜(7)の中心点位置は、
たとえば、それぞれ+15 、2t15 、3115゜
4t15 の位置にある。Conventionally, there was a persimmon device shown in Fig. 1. In FIG. 1, 11 is a reactor vessel, and (2) is a curve representing the neutron flux distribution ψ in the height direction (X direction) of the reactor vessel. (3) A four-part neutron detector for external nuclear measurement placed parallel to the height direction of the reactor vessel (11);
(41 to (7) are detection elements built into the detector (31); in conventional devices, these detection elements are arranged at equal intervals from each other and symmetrically with the center of the detector (31). Bottom position e x = Or top position f of container (1)
If x=t, the center point position of elements 141 to (7) is
For example, they are located at +15, 2t15, and 3115°4t15, respectively.
ところで、ψに)の形は7一リエ級数に分解して、第5
項以下を省略して
ψ(x)=C1stnπ−十C25in 2πT十C3
81n 3π7+ C45ln4π−=−= (11
とし、係数C1,c2. c3. C4を適当に定めれ
ば比較的よく近似することができる。式(1)の右辺第
1項乃至第4項を第2図に示すっ
第1図の例では、x = +15 、2t15 、31
15,4115の4点におけるψに)の値(それぞれ)
’ −V −)’ +1 2 3
y4とする)が検出素子fa ’、’ i5+ 、 1
61 、 +71により測定できるので
となり、この連立方程式(2)から係数C工l C21
C31C4′tl−決定することができる。従来の装置
は舅、上のように構成されているので、原子炉運転時に
重要な中性子束分布のアキシャルオフセット(axia
lof f seりを正確に測定するには適当でないと
いう欠点があった。アキシャルオフセットとはψ(幻の
分布範囲x=0乃至x=1においてx (t/2の部分
とx > L/2の部分とにおけるψ(劾のアンバラン
スを言い、これは第2図から明らかなように係数C2+
04 の値によって決定されるが、元来C2+04は
比較的小さな数であり、連立方程式(2)の各式におけ
るc2.’ c4の係数(stn2π;15. Sin
4π15.5ln6π15゜自8π15.l、(由4
π15.虐8π15.崗1次15.癲16π15)の間
には必ずしも顕著な差異がなく、従って連立方程式(2
)から決定したC2. C4の値は正確さが不充分であ
るという欠点があった。By the way, the form of
Omitting the following terms, ψ(x) = C1stnπ-10C25in 2πT0C3
81n 3π7+ C45ln4π−=−= (11) If the coefficients C1, c2, c3, and C4 are appropriately determined, a relatively good approximation can be achieved. In the example shown in Figure 1, x = +15, 2t15, 31
ψ at the four points of 15,4115 (respectively)
'-V-)' +1 2 3 y4) is the detection element fa', 'i5+, 1
61, +71, and from this simultaneous equation (2), the coefficient C C21
C31C4'tl-can be determined. Since the conventional equipment is configured as above, it is possible to avoid the axial offset (axia) of the neutron flux distribution, which is important during reactor operation.
This method has the disadvantage that it is not suitable for accurately measuring lof f se. Axial offset is ψ (in the phantom distribution range x = 0 to x = 1, x (t/2 part and x > L/2 part). As is clear, the coefficient C2+
04, but C2+04 is originally a relatively small number, and c2.04 in each equation of simultaneous equations (2). ' Coefficient of c4 (stn2π; 15. Sin
4π15.5ln6π15°self8π15. l, (Yu 4
π15. Aggression 8π15. Gang 1st grade 15. There is not necessarily a significant difference between the equations (16π15), and therefore the simultaneous equations (2
) determined from C2. The C4 value had the disadvantage of insufficient accuracy.
この発明は上記のような従来のものの欠点金除去するた
めになされたもので、中性子分布のアキシャルオフセッ
トe算出するのに最も適当な位置に各検出素子の中心点
を配列することによシ、アキシャルオフセラ)k正確に
舞−出することができる炉外様計測用中性子検出器を提
供すること全目的としている。This invention was made in order to eliminate the drawbacks of the conventional method as described above, and by arranging the center point of each detection element at the most appropriate position for calculating the axial offset e of the neutron distribution, The overall purpose of this invention is to provide a neutron detector for measuring outside the reactor that can accurately emit neutrons.
以下この発明の災施例全図I]111VCついて説明す
る。Hereinafter, the 111VC of this invention will be explained.
第3図はこの発明の一実施例全示す祝ψ」図であって、
第1図と同一符号は同−又は相当部分を示し、(8;は
この発明の炉外様計測用中性子検出器で、検出器1B+
においては検出素子+41〜(7)の中心位置がそれぞ
れt/8 、 t/4 、3t/4 、7t/8となる
。したがってπx/L =π/8.π/4,3π/4,
7π/8となplこの4点におけるψ伏)の値をそれぞ
れy1□s ’11□ 。FIG. 3 is a diagram showing one embodiment of the present invention,
The same reference numerals as in FIG. 1 indicate the same or corresponding parts, and (8; is the neutron detector for measuring the outside of the reactor according to the present invention, and the detector 1B+
In this case, the center positions of the detection elements +41 to (7) are t/8, t/4, 3t/4, and 7t/8, respectively. Therefore, πx/L = π/8. π/4, 3π/4,
7π/8, and the value of ψ at these four points is y1□s '11□.
y 、y とすれば
13 14
となシ、C2* 04の係数は(thπ/4 、1 、
−1 。If y and y are 13 14, the coefficient of C2*04 is (thπ/4, 1,
-1.
−虐π:/4 ) 、 (1、0、0、1)と比較的顕
著に変化するので、係数02 + C4k比較的精度よ
く決定することができて、中性子束分布のアキシャルオ
フセラ)?正確に検出することができる5以上のように
この発明によれは、検出素子の中心点をt/8 、 L
/4 、31/4. ’It/8 に置いたので中性子
束分布のアキシャルオフセラ)’tl−正確に検出する
ことができる。- π:/4), (1, 0, 0, 1) changes relatively significantly, so the coefficient 02 + C4k can be determined with relative accuracy, and the axial offset of the neutron flux distribution)? According to the present invention, the center point of the detection element is set to t/8, L
/4, 31/4. Since it is placed at 'It/8, the axial offset of the neutron flux distribution)'tl- can be detected accurately.
第1図は従来の装置を示す説明図、第2図は中性子束分
布のフーリエ分解全説明する図、第3図はこの発明の一
実施例を示す説明図である。
(1)・・・原子炉容器、(21・・・中性子束分布、
181・・・炉外様計測用中性子検出器。
尚、各図中同一符号は同−又は相当部分を示す、代理人
大 岩 増 雄
第1図
第2図
手続補正書(自発)
特許庁長官殿
2、発明の名称
炉外核計測用中性子検出器
3、補正をする者
事件との関係 特許出願人
住 所 東京都千代日」置火の内二丁目2番3号
名 称 (601)三菱電機株式会社代表者片山仁八
部
6、補正の内容
tl+ 明細裾の特許請求の範囲を別紙のとおり訂正
する。
(2) 明、fil 書第5頁第9行目「することが
できる。」とあるを「することができる。さらに、検出
器のt/2近傍には検出素子がないため、この部分に例
えば線源または中間領域の中性子検出益金容易に組込め
る%徴も有する。」と訂正する。
7、添付書類の目録
(11訂正した特許請求の範囲 1通(以上〕
別 紙
2、特許請求の範囲
原子炉容器の外部に、この原子炉容器の高さの方向に平
行に配置され、上記原子炉から放射される中性子束の上
記高さ方向の分布を測定するため4個の検出素子が設け
られる炉外核側測用中性子検出器において、上記原子炉
の底■の高さを0と個の検出素子の高さをそれぞれt/
8 、 t/4.31/4゜7t/8 としたことを
特徴とする炉外核計測用中性子検出器。FIG. 1 is an explanatory diagram showing a conventional device, FIG. 2 is a diagram fully explaining Fourier decomposition of a neutron flux distribution, and FIG. 3 is an explanatory diagram showing an embodiment of the present invention. (1)...Reactor vessel, (21...Neutron flux distribution,
181...Neutron detector for measurements outside the reactor. In addition, the same reference numerals in each figure indicate the same or corresponding parts. Agent: Masuo Oiwa Figure 1 Figure 2 Procedural amendment (voluntary) Commissioner of the Japan Patent Office 2 Name of the invention Neutron detection for core measurement outside the reactor 3. Relationship with the case of the person making the amendment Patent Applicant Address: Chiyohi, Tokyo 2-2-3 Okihi-no-uchi Name (601) Hitoshi Katayama, Representative of Mitsubishi Electric Corporation 8th Department 6, Amendment Content tl+ The claims at the bottom of the specification are corrected as shown in the attached sheet. (2) Akira, fil, page 5, line 9, "can do." should be replaced with "can do."Furthermore, since there is no detecting element near t/2 of the detector, there is no detecting element in this part. For example, it also has percentage characteristics that can be easily incorporated into neutron detection gains in the source or intermediate region.'' 7. List of attached documents (11 amended claims 1 copy (at least)) Attachment 2: Claims The above claims are arranged outside the reactor vessel, parallel to the height direction of the reactor vessel, In the outer core side neutron detector, which is equipped with four detection elements to measure the distribution of neutron flux emitted from the reactor in the height direction, the height of the bottom of the reactor is set to 0. The height of each detection element is t/
8. A neutron detector for nuclear measurement outside the reactor, characterized in that it has a t/4.31/4°7t/8.
Claims (1)
行に配置され、上記原子炉から放射される中性子束の上
記高さ方向の分布を測定するため4個の検出素子が設け
られる炉外核計画用中性子検出器において、上記原子炉
の底面の高さ金Oとし、上記原子炉の頂面の高さをtと
するとき、上記4個の検出素子の高さ全それぞれL/8
、 t/4 。 31/4.71/8 としたこと全特徴とする炉外核
計画用中性子検出器。[Claims] Four units arranged outside the reactor vessel in parallel to the height direction of the reactor vessel to measure the distribution of neutron flux emitted from the reactor in the height direction. In a neutron detector for an ex-core nuclear program, in which the height of the bottom of the reactor is O, and the height of the top of the reactor is t, the number of detection elements of the four detection elements is Total height L/8 each
, t/4. 31/4.71/8 Neutron detector for ex-core nuclear program with all the features.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP58089528A JPS59214795A (en) | 1983-05-20 | 1983-05-20 | Neutron detector for measuring nuclear away from reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP58089528A JPS59214795A (en) | 1983-05-20 | 1983-05-20 | Neutron detector for measuring nuclear away from reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS59214795A true JPS59214795A (en) | 1984-12-04 |
Family
ID=13973306
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP58089528A Pending JPS59214795A (en) | 1983-05-20 | 1983-05-20 | Neutron detector for measuring nuclear away from reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS59214795A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS6283696A (en) * | 1985-10-09 | 1987-04-17 | 三菱原子力工業株式会社 | Method of monitoring axial output distribution in reactor |
JP2008175692A (en) * | 2007-01-18 | 2008-07-31 | Nuclear Fuel Ind Ltd | Measuring method of axial power distribution of core |
-
1983
- 1983-05-20 JP JP58089528A patent/JPS59214795A/en active Pending
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS6283696A (en) * | 1985-10-09 | 1987-04-17 | 三菱原子力工業株式会社 | Method of monitoring axial output distribution in reactor |
JP2008175692A (en) * | 2007-01-18 | 2008-07-31 | Nuclear Fuel Ind Ltd | Measuring method of axial power distribution of core |
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