JPH04337500A - Nuclear fuel assembly monitoring system - Google Patents
Nuclear fuel assembly monitoring systemInfo
- Publication number
- JPH04337500A JPH04337500A JP3110357A JP11035791A JPH04337500A JP H04337500 A JPH04337500 A JP H04337500A JP 3110357 A JP3110357 A JP 3110357A JP 11035791 A JP11035791 A JP 11035791A JP H04337500 A JPH04337500 A JP H04337500A
- Authority
- JP
- Japan
- Prior art keywords
- nuclear fuel
- fuel assembly
- nuclear
- reactor
- data
- 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.)
- Withdrawn
Links
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 72
- 238000012544 monitoring process Methods 0.000 title claims abstract description 15
- 239000000463 material Substances 0.000 claims abstract description 17
- 238000013461 design Methods 0.000 claims abstract description 14
- 230000000704 physical effect Effects 0.000 claims abstract description 6
- 238000000034 method Methods 0.000 claims description 10
- 230000008569 process Effects 0.000 claims description 9
- 230000036541 health Effects 0.000 claims description 7
- 238000011156 evaluation Methods 0.000 claims description 6
- 230000000712 assembly Effects 0.000 description 9
- 238000000429 assembly Methods 0.000 description 9
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 8
- 238000004458 analytical method Methods 0.000 description 6
- 230000004992 fission Effects 0.000 description 6
- 238000000746 purification Methods 0.000 description 6
- 238000005253 cladding Methods 0.000 description 5
- 238000006243 chemical reaction Methods 0.000 description 4
- 238000010586 diagram Methods 0.000 description 4
- 238000005259 measurement Methods 0.000 description 4
- 239000000446 fuel Substances 0.000 description 3
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 2
- 229910045601 alloy Inorganic materials 0.000 description 2
- 239000000956 alloy Substances 0.000 description 2
- 238000009835 boiling Methods 0.000 description 2
- 239000008188 pellet Substances 0.000 description 2
- 238000010248 power generation Methods 0.000 description 2
- 125000006850 spacer group Chemical group 0.000 description 2
- 238000002076 thermal analysis method Methods 0.000 description 2
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 description 1
- 229910001093 Zr alloy Inorganic materials 0.000 description 1
- 238000000748 compression moulding Methods 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 238000005336 cracking Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000003628 erosive effect Effects 0.000 description 1
- 230000003203 everyday effect Effects 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- 229910052736 halogen Inorganic materials 0.000 description 1
- 150000002367 halogens Chemical class 0.000 description 1
- 229910052740 iodine Inorganic materials 0.000 description 1
- 239000011630 iodine Substances 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 229910052759 nickel Inorganic materials 0.000 description 1
- OOAWCECZEHPMBX-UHFFFAOYSA-N oxygen(2-);uranium(4+) Chemical compound [O-2].[O-2].[U+4] OOAWCECZEHPMBX-UHFFFAOYSA-N 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 229910052761 rare earth metal Inorganic materials 0.000 description 1
- 239000008234 soft water Substances 0.000 description 1
- 239000007921 spray Substances 0.000 description 1
- FCTBKIHDJGHPPO-UHFFFAOYSA-N uranium dioxide Inorganic materials O=[U]=O FCTBKIHDJGHPPO-UHFFFAOYSA-N 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)
Abstract
Description
【０００１】［発明の目的］[Object of the invention]
【０００２】0002
【産業上の利用分野】本発明は、原子炉で使用される原
子炉燃料集合体のモニタリングシステムに関する。BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a monitoring system for nuclear reactor fuel assemblies used in nuclear reactors.
【０００３】0003
【従来の技術】原子炉の構造は、全体を取り囲んでいる
原子炉圧力容器と、この原子炉圧力容器内の上下部に配
置される制御棒駆動機構、中性子計測器及び原子燃料集
合体等の炉内構造物と、上部炉心支持格子板、下部炉心
支持格子板、炉心スプレイランイ、再循環水ライン、主
蒸気ライン等から構成されている。[Prior Art] The structure of a nuclear reactor consists of a reactor pressure vessel surrounding the entire reactor pressure vessel, a control rod drive mechanism, a neutron measuring instrument, a nuclear fuel assembly, etc. arranged at the upper and lower parts of the reactor pressure vessel. It consists of reactor internals, upper core support grid plate, lower core support grid plate, core spray run, recirculation water line, main steam line, etc.
【０００４】この原子炉で使用される原子燃料集合体は
、原子炉の形式で構造を異にするが、図２に沸騰水型原
子炉の原子燃料集合体Ａを示す。図２に示すように、横
断面が正方形のチャンネルボックス９内に、８×８列に
配列された原子燃料要素１０が、スペーサ１１でほぼ等
間隔に保持され、原子燃料要素１０の上下両端はそれぞ
れ上部タイプレート１２及び下部タイプレート１３で支
持されている。なお、原子燃料要素１０の上部端栓には
、スプリング１４が介装され、またチャンネルボックス
９の上部外側面には、案内バネ１５が設けられている。Nuclear fuel assemblies used in this nuclear reactor have different structures depending on the type of reactor, and FIG. 2 shows a nuclear fuel assembly A for a boiling water reactor. As shown in FIG. 2, nuclear fuel elements 10 arranged in 8×8 rows are held at approximately equal intervals by spacers 11 in a channel box 9 having a square cross section, and both upper and lower ends of the nuclear fuel elements 10 are They are supported by an upper tie plate 12 and a lower tie plate 13, respectively. A spring 14 is interposed in the upper end plug of the nuclear fuel element 10, and a guide spring 15 is provided on the outer surface of the upper part of the channel box 9.
【０００５】また、原子燃料要素１０は、図３に示すよ
うに、長尺の円筒状被覆管１６に二酸化ウラン粉末を円
柱状に圧縮成形して焼結原子燃料ペレット１７を多数個
装填し、プレナム部１８にスプリング１９を介装して被
覆管１６の上下両端を端栓２０、２１で気密に封止した
ものである。Further, as shown in FIG. 3, the nuclear fuel element 10 includes a long cylindrical cladding tube 16 filled with a large number of sintered nuclear fuel pellets 17 formed by compression molding uranium dioxide powder into a cylindrical shape. A spring 19 is interposed in the plenum portion 18, and both upper and lower ends of the cladding tube 16 are hermetically sealed with end plugs 20 and 21.
【０００６】原子力発電所で原子燃料要素１０を使用す
る時は、原子燃料要素１０を核***反応が有効に持続す
るような形状に、また発生した熱を有効に取り出せるよ
うに図２に示す様々形状にスペーサ１１で束ね、その両
端に上部タイプレート１２及び下部タンプレート１３を
取り付けた原子燃料集合体Ａとして使用する。原子燃料
集合体Ａは、原子力発電所の出力に応じて４本を１セル
として必要本数だけを、核***反応を熱に有効に変えら
れるような状態に組んで使用している。 従って、原
子燃料要素１０は、前記のような原子炉で約３００℃の
冷却水、中性子及び核***生成物に曝露された状態で、
原子炉の起動時や運転中の出力を変える時の出力変動に
応じた荷重を受ける。When the nuclear fuel element 10 is used in a nuclear power plant, the nuclear fuel element 10 is shaped to effectively sustain the nuclear fission reaction, and various shapes shown in FIG. 2 are used to effectively extract the generated heat. It is used as a nuclear fuel assembly A, which is bundled with spacers 11 and has an upper tie plate 12 and a lower tongue plate 13 attached to both ends thereof. Nuclear fuel assembly A is used by assembling only the necessary number of four fuels into one cell in accordance with the output of the nuclear power plant in such a way that the nuclear fission reaction can be effectively converted into heat. Therefore, the nuclear fuel element 10 is exposed to cooling water, neutrons, and fission products at about 300° C. in a nuclear reactor as described above.
It receives loads corresponding to output fluctuations when the reactor starts up or changes output during operation.
【０００７】このような条件で重畳効果を起こして原子
燃料要素１０が破損してしまうおそれがある。また、原
子燃料ペレットは、核***反応により核***生成物を放
出する。この核***生成物の中には、被覆管１６を浸食
するハロゲン元素、希土類元素が含まれている。[0007] Under such conditions, there is a risk that a superposition effect may occur and the nuclear fuel element 10 may be damaged. Nuclear fuel pellets also release fission products due to nuclear fission reactions. This fission product contains halogen elements and rare earth elements that corrode the cladding tube 16.
【０００８】これらの元素は、被覆管１６内面の傷等の
弱い箇所を優先的に浸食する。この浸食作用は、原子力
発電の運転中に発生する出力変動により加速され、つい
に被覆管１６に孔が明いてしまうおそれがあった。These elements preferentially erode weak spots such as scratches on the inner surface of the cladding tube 16. This erosion is accelerated by output fluctuations that occur during the operation of the nuclear power plant, and there is a fear that holes will eventually form in the cladding tube 16.
【０００９】一方、原子炉周辺に、図４に示すように、
多くの計測器に取り付けられている。圧力計装としては
、主蒸気圧力２２、原子炉圧力２３、炉心差圧２４、温
度としては、給水温度２５、浄化系出口温度２６、浄化
系出口温度２７、再循環ループ入口温度２８、及び流量
としては、給水流量２９、浄化系流量３０、ジェットポ
ンプ吐出流量３１、再循環流量３２等が取り付けられて
いる。On the other hand, as shown in FIG. 4, around the nuclear reactor,
Attached to many measuring instruments. Pressure instrumentation includes main steam pressure 22, reactor pressure 23, core differential pressure 24, and temperatures include feed water temperature 25, purification system outlet temperature 26, purification system outlet temperature 27, recirculation loop inlet temperature 28, and flow rate. As such, a water supply flow rate 29, a purification system flow rate 30, a jet pump discharge flow rate 31, a recirculation flow rate 32, etc. are attached.
【００１０】また、原子炉炉心４０の中性子束測定は、
図５に線源領域中性子モニタ３３、中間領域中性子モニ
タ３４、部分時中性子モニタ３５が取り付けられている
。３６は制御棒である。[0010] Furthermore, the neutron flux measurement of the nuclear reactor core 40 is as follows:
In FIG. 5, a source area neutron monitor 33, an intermediate area neutron monitor 34, and a partial neutron monitor 35 are installed. 36 is a control rod.
【００１１】[0011]
【発明が解決しようとする課題】これらのデータは、プ
ロセス・コンピュータで処理され、原子炉運転データと
して出されているが、原子燃料集合体Ａのオンラインモ
ニタには、活用されていない。[Problems to be Solved by the Invention] These data are processed by a process computer and output as reactor operation data, but are not utilized for online monitoring of the nuclear fuel assembly A.
【００１２】また、原子燃料集合体Ａは、オフガスモニ
タの値の上昇として破損管理されているだけであり、オ
スガスが上昇時は原子燃料集合体Ａの破損が起こった時
である。Further, damage to the nuclear fuel assembly A is only managed by observing an increase in the off-gas monitor value, and when the male gas increases, this means that damage to the nuclear fuel assembly A has occurred.
【００１３】原子燃料集合体Ａは、原子炉運転ガイドに
折り込まれている出力上昇制限カーブにより破損を予防
しているだけで、オンライン監視されていない。[0013] The nuclear fuel assembly A is only prevented from being damaged by a power increase limit curve included in the reactor operation guide, and is not monitored on-line.
【００１４】本発明はかかる従来の問題点を解決するた
めになされたもので、その目的は、原子燃料集合体の健
全性を常時監視できるようにプロセスコンピュータのデ
ータを取り出し、原子燃料の特性データを組み合わせ確
率的信頼性評価を行いオンラインで原子燃料集合体の健
全性を監視することを可能とした原子燃料集合体モニタ
リングシステムを提供することにある。The present invention has been made to solve such conventional problems, and its purpose is to extract data from a process computer so as to constantly monitor the health of a nuclear fuel assembly, and to collect characteristic data of nuclear fuel. The purpose of this study is to provide a nuclear fuel assembly monitoring system that makes it possible to perform probabilistic reliability evaluations and monitor the health of nuclear fuel assemblies online.
【００１５】［発明の構成］[Configuration of the invention]
【００１６】[0016]
【課題を解決するための手段】本発明に係わる原子燃料
集合体モニタリングシステムは、原子炉内外に取り付け
られた中性子計測器及び各種の計測機器から得られる炉
心熱出力、炉心流量、炉心差圧、炉心入口サブクール等
を、オンライン・プロセス・コンピュータで処理した原
子炉運転データと、原子炉核熱設計データと、原子燃料
集合体設計データと、原子燃料集合体部品材料特性デー
タと、原子燃料集合体材料物性データと、原子燃料集合
体材使用実績データとを、コンピュータで統計的に評価
した確率的信頼性評価プログラムで評価を行い、原子燃
料集合体の健全性を常時原子炉中央制御室でモニタする
ものである。[Means for Solving the Problems] The nuclear fuel assembly monitoring system according to the present invention provides core thermal output, core flow rate, core differential pressure, and Reactor operation data, reactor nuclear thermal design data, nuclear fuel assembly design data, nuclear fuel assembly component material property data, and nuclear fuel assembly data processed by online process computers, such as core inlet subcooling, etc. Material property data and nuclear fuel assembly material usage data are evaluated using a probabilistic reliability evaluation program that statistically evaluates them using a computer, and the health of nuclear fuel assemblies is constantly monitored in the reactor central control room. It is something to do.
【００１７】原子燃料集合体に使用されているジルコニ
ウム合金、鉄・クロウニウム・コッケル合金、ニッケル
基合金等の材料は、中性子照射量、温度サイクル、荷重
サイクルに応じた、クリープ、疲労、靭性、亀裂発生、
亀裂進展、破損データが整っている。Materials used in nuclear fuel assemblies, such as zirconium alloys, iron-curonium-Cockel alloys, and nickel-based alloys, exhibit creep, fatigue, toughness, and cracking depending on the amount of neutron irradiation, temperature cycles, and load cycles. occurrence,
Crack growth and damage data are available.
【００１８】一方、軟水炉、ガス炉、高速中性子増炉及
び実験炉にあって原子炉の核反応を制御するために中性
子計測系や原子炉安全系の計装が取り付けられている。
これらのプロセス・コンピュータで処理され原子炉安全
運転に供されている。原子炉心及び周辺部に取り付けら
れた計測器からのデータ、燃焼速度、ゼノン濃度、ヨウ
素濃度、相対水密度、線出力密度、出力、限界出力密度
等が求められ、これらの値から中性子照射量、温度サイ
クル及び荷重サイクルが求められる。この求めた値と前
記材料特性データ、物性データ、原子燃料集合体使用実
績データ、原子燃料集合体構造・熱設計データ及び原子
炉核熱設計データを確率的信頼性評価手法で評価し、そ
の健全性を常時監視できるようにし、原子炉の信頼性を
向上させる。On the other hand, in soft water reactors, gas reactors, fast neutron reactors, and experimental reactors, neutron measurement systems and reactor safety system instruments are installed to control nuclear reactions in the reactors. It is processed by these process computers and used for safe reactor operation. Data from measuring instruments installed in the reactor core and surrounding areas, such as burning rate, xenone concentration, iodine concentration, relative water density, linear power density, power, and critical power density, are obtained, and from these values, the neutron irradiation amount, Temperature and load cycles are required. This obtained value, the material property data, physical property data, nuclear fuel assembly usage record data, nuclear fuel assembly structural/thermal design data, and reactor nuclear thermal design data are evaluated using a probabilistic reliability evaluation method, and the soundness of the nuclear fuel assembly is evaluated using a probabilistic reliability evaluation method. This will enable constant monitoring of reactor performance and improve the reliability of nuclear reactors.
【００１９】[0019]
【作用】原子力発電は、プロセス・コンピュータからの
熱出力等の５３項目の原子炉運転データを出力する。こ
のデータを活用し、原子燃料集合体の健全性のオンライ
ン・モニタをする。その方法は、原子燃料集合体の弾性
・非弾性解析、疲労解析、クリープ解析、熱解析の原子
燃料集合体設計データと、原子燃料集合体部品材料特性
データと、原子燃料集合体部材材料特性データと、原子
燃料集合体材料物性データと、原子燃料集合体使用実績
データと、原子炉核熱設計データと、原子炉運転データ
とを、確率的信頼性評価手法を取り入れたプログラムに
組み入れて、原子燃料集合体のオンラインモニタリング
（ＣＲＴ常時監視）できるようにし、原子力発電の信頼
性を向上させることができる。[Operation] Nuclear power generation outputs 53 items of reactor operation data such as heat output from the process computer. Utilize this data to monitor the health of nuclear fuel assemblies online. The method is based on the nuclear fuel assembly design data of elastic/inelastic analysis, fatigue analysis, creep analysis, and thermal analysis of the nuclear fuel assembly, the material property data of the nuclear fuel assembly parts, and the material property data of the nuclear fuel assembly parts. , nuclear fuel assembly material physical property data, nuclear fuel assembly usage data, reactor nuclear thermal design data, and reactor operation data are incorporated into a program that incorporates a probabilistic reliability evaluation method. It enables online monitoring of fuel assemblies (constant CRT monitoring) and improves the reliability of nuclear power generation.
【００２０】[0020]
【実施例】以下、本発明の実施例を図面に基づいて説明
する。Embodiments Hereinafter, embodiments of the present invention will be explained based on the drawings.
【００２１】図１は本発明に係わる原子燃料集合体モニ
タリングシステムを示す説明図である。沸騰水型原子炉
では、図４と同様に、主蒸気圧２２、原子炉圧力２３、
炉心差圧２４、給水温度２５、浄化系出口温度２６、浄
化系流量３０、再循環入口温度２８、給水流量２９、浄
化系入口温度２７、再循環流量３２等の計測器が取り付
けられており、原子炉運転中、常時、測定を行っている
。FIG. 1 is an explanatory diagram showing a nuclear fuel assembly monitoring system according to the present invention. In a boiling water reactor, as in FIG. 4, the main steam pressure 22, the reactor pressure 23,
Measuring instruments such as core differential pressure 24, feed water temperature 25, purification system outlet temperature 26, purification system flow rate 30, recirculation inlet temperature 28, feed water flow rate 29, purification system inlet temperature 27, recirculation flow rate 32, etc. are installed. Measurements are taken constantly during reactor operation.
【００２２】また、原子炉の運転管理データを取るため
に、図５と同様に、炉心に中性子計測器３３、３４、３
５が取り付けられている。In addition, in order to obtain operation management data of the nuclear reactor, neutron measuring instruments 33, 34, 3 are installed in the reactor core, as in FIG.
5 is attached.
【００２３】これらのデータは、原子炉プロセス・コン
ピュータで処理され、原子炉運転データ１として、１時
間毎、１日毎に出力されている。These data are processed by the reactor process computer and output as reactor operation data 1 every hour and every day.
【００２４】本実施例では、このプロセス・コンピュー
タから原子燃料集合体の監視に必要な炉心定数、炉心熱
水力データ等の原子炉運転データ１を取りだし、原子炉
核熱設計データ２と、原子燃料集合体の構成部品の材料
データ、部品の弾性・非弾性解析、疲労解析、クリープ
解析、熱解析の原子燃料集合体設計データ３と、原子燃
料集合体部品材料特性データ４と、原子燃料集合体材料
物性データ５と、原子燃料集合体使用実績データ６とを
、確率的信頼性評価手法を取り入れたプログラケム７に
組み入れて、原子燃料集合体Ａの健全性をオンラインモ
ニタリング（ＣＲＴ常時監視）８によって、原子炉の信
頼性を向上させる。In this embodiment, reactor operation data 1 such as core constants and core thermal hydraulic data necessary for monitoring nuclear fuel assemblies is taken out from this process computer, and reactor nuclear thermal design data 2 and nuclear Nuclear fuel assembly design data 3 for fuel assembly component parts material data, elastic/inelastic analysis of parts, fatigue analysis, creep analysis, and thermal analysis, nuclear fuel assembly parts material property data 4, and nuclear fuel assembly The health of nuclear fuel assembly A is monitored online (CRT constant monitoring) by incorporating physical property data of nuclear fuel assembly A5 and nuclear fuel assembly usage record data6 into Program Chem7 that incorporates a probabilistic reliability evaluation method. This will improve the reliability of the nuclear reactor.
【００２５】[0025]
【発明の効果】以上のように、本発明によれば、原子炉
プロセス・コンピュータのデータを基にした健全性をオ
ンラインで監視することができる。As described above, according to the present invention, the health of a nuclear reactor can be monitored online based on data from a nuclear reactor process computer.
【図１】本発明に係わる原子燃料集合体モニタリングシ
ステムを示す説明図である。FIG. 1 is an explanatory diagram showing a nuclear fuel assembly monitoring system according to the present invention.
【図２】原子燃料集合体を示す断面図である。FIG. 2 is a sectional view showing a nuclear fuel assembly.
【図３】原子燃料要素を示す断面図である。FIG. 3 is a cross-sectional view of a nuclear fuel element.
【図４】原子炉の核系統に取り付けられている計測器を
示す説明図である。FIG. 4 is an explanatory diagram showing measuring instruments installed in the nuclear system of a nuclear reactor.
【図５】中性子計測器及び制御棒の配置を示す原子炉炉
心図である。FIG. 5 is a nuclear reactor core diagram showing the arrangement of neutron measuring instruments and control rods.
１………原子炉運転データ
２………原子炉核熱設計データ
３………原子燃料集合体設計データ
４………原子燃料集合体部品材料特性データ５………原
子燃料集合体材料物性データ６………原子燃料集合体使
用実績データ７………確率的信頼性評価（ＰＲＡ）プロ
グラム８………原子燃料集合体モニタリング
Ａ………原子燃料集合体
３３、３４、３５…中性子計測器
３６………制御棒
４０………原子炉炉心1...Reactor operation data 2...Reactor nuclear thermal design data 3...Nuclear fuel assembly design data 4...Nuclear fuel assembly parts material property data 5...Nuclear fuel assembly material physical properties Data 6... Nuclear fuel assembly usage record data 7... Probabilistic reliability assessment (PRA) program 8... Nuclear fuel assembly monitoring A... Nuclear fuel assemblies 33, 34, 35... Neutron measurement Container 36...Control rod 40...Reactor core
Claims (1)
測器及び各種の計測機器から得られる炉心熱出力、炉心
流量、炉心差圧、炉心入口サブクール等を、オンライン
・プロセス・コンピュータで処理した原子炉運転データ
と、原子炉核熱設計データと、原子燃料集合体設計デー
タと、原子燃料集合体部品材料特性データと、原子燃料
集合体材料物性データと、原子燃料集合体材料使用実績
データと、コンピュータで統計的に評価した確率的信頼
性評価プログラムで評価を行い、原子燃料集合体の健全
性を常時原子炉中央制御室でモニタすることを特徴とす
る原子燃料集合体モニタリングシステム。Claim 1: A nuclear reactor in which core thermal output, core flow rate, core differential pressure, core inlet subcooling, etc. obtained from neutron measuring instruments and various measuring instruments installed inside and outside the reactor are processed by an online process computer. Operation data, reactor nuclear thermal design data, nuclear fuel assembly design data, nuclear fuel assembly parts material property data, nuclear fuel assembly material physical property data, nuclear fuel assembly material usage record data, and computer A nuclear fuel assembly monitoring system that performs evaluation using a probabilistic reliability evaluation program that is statistically evaluated, and constantly monitors the health of the nuclear fuel assembly in the reactor central control room.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP3110357A JPH04337500A (en) | 1991-05-15 | 1991-05-15 | Nuclear fuel assembly monitoring system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP3110357A JPH04337500A (en) | 1991-05-15 | 1991-05-15 | Nuclear fuel assembly monitoring system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH04337500A true JPH04337500A (en) | 1992-11-25 |
Family
ID=14533730
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP3110357A Withdrawn JPH04337500A (en) | 1991-05-15 | 1991-05-15 | Nuclear fuel assembly monitoring system |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH04337500A (en) |
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|---|---|---|---|---|
| US8313157B2 (en) | 2009-04-01 | 2012-11-20 | Ricoh Company, Limited | Inkjet recording apparatus |
| US8366257B2 (en) | 2008-12-03 | 2013-02-05 | Ricoh Company, Ltd. | Inkjet recording apparatus |
| US8596768B2 (en) | 2011-03-04 | 2013-12-03 | Seiko Epson Corporation | Liquid discharging apparatus and control method thereof |
| US8690301B2 (en) | 2011-03-04 | 2014-04-08 | Seiko Epson Corporation | Liquid discharging apparatus and control method thereof |
| CN111681789A (en) * | 2020-06-22 | 2020-09-18 | 中国核动力研究设计院 | Thermal hydraulic experimental device for closely-arranged rod bundle fuel assemblies |
-
1991
- 1991-05-15 JP JP3110357A patent/JPH04337500A/en not_active Withdrawn
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8366257B2 (en) | 2008-12-03 | 2013-02-05 | Ricoh Company, Ltd. | Inkjet recording apparatus |
| US8313157B2 (en) | 2009-04-01 | 2012-11-20 | Ricoh Company, Limited | Inkjet recording apparatus |
| US8596768B2 (en) | 2011-03-04 | 2013-12-03 | Seiko Epson Corporation | Liquid discharging apparatus and control method thereof |
| US8690301B2 (en) | 2011-03-04 | 2014-04-08 | Seiko Epson Corporation | Liquid discharging apparatus and control method thereof |
| US8939562B2 (en) | 2011-03-04 | 2015-01-27 | Seiko Epson Corporation | Liquid discharging apparatus and control method thereof |
| CN111681789A (en) * | 2020-06-22 | 2020-09-18 | 中国核动力研究设计院 | Thermal hydraulic experimental device for closely-arranged rod bundle fuel assemblies |
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Free format text: JAPANESE INTERMEDIATE CODE: A300 Effective date: 19980806 |