JP5435847B2 - 沸騰水型原子炉の蒸気系に関する応力を予測する方法 - Google Patents
沸騰水型原子炉の蒸気系に関する応力を予測する方法 Download PDFInfo
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- JP5435847B2 JP5435847B2 JP2007198406A JP2007198406A JP5435847B2 JP 5435847 B2 JP5435847 B2 JP 5435847B2 JP 2007198406 A JP2007198406 A JP 2007198406A JP 2007198406 A JP2007198406 A JP 2007198406A JP 5435847 B2 JP5435847 B2 JP 5435847B2
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- 238000000034 method Methods 0.000 title claims description 45
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims description 14
- 238000009835 boiling Methods 0.000 title claims description 10
- 238000012360 testing method Methods 0.000 claims description 65
- 238000004458 analytical method Methods 0.000 description 16
- 230000004044 response Effects 0.000 description 10
- 230000000875 corresponding effect Effects 0.000 description 9
- 230000002596 correlated effect Effects 0.000 description 8
- 238000005259 measurement Methods 0.000 description 6
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- 238000010586 diagram Methods 0.000 description 3
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- 238000013459 approach Methods 0.000 description 1
- 230000005540 biological transmission Effects 0.000 description 1
- 230000015556 catabolic process Effects 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 230000008878 coupling Effects 0.000 description 1
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- 238000005859 coupling reaction Methods 0.000 description 1
- 238000005336 cracking Methods 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000006731 degradation reaction Methods 0.000 description 1
- 238000004836 empirical method Methods 0.000 description 1
- 238000002474 experimental method Methods 0.000 description 1
- 230000016507 interphase Effects 0.000 description 1
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- 238000004088 simulation Methods 0.000 description 1
- 238000012795 verification Methods 0.000 description 1
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
-
- 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
Description
100 音響テストシステム
110 テスト設備
120 BWR縮尺モデル
130 ブロア
140 注入口配管
150 流量計
160 マフラ
170 RPV
175 RPV頂部ヘッド
180 蒸気乾燥器
190 主蒸気ライン
200 音響メッシュ
205 シェルメッシュ
210 要素
215 音響節点
Claims (9)
- 沸騰水型原子炉(BWR)の蒸気乾燥器にかかる応力を予測する方法であって、
BWR縮尺モデルの圧力変換器およびマイクロフォンの少なくとも1つを使用して、前記BWR縮尺モデルから圧力データを取得する段階であって、前記圧力データが経験データである、段階と、
BWR蒸気系の解析音響モデルを構築する段階と、
前記BWR蒸気系の解析音響モデルに前記経験データを入力することによって圧力推定値を生成する段階と、
前記BWR蒸気乾燥器の解析構造モデルを構築する段階と、
前記解析構造モデル及び前記圧力推定値を使用して、前記BWR蒸気乾燥器にかかる応力を予測する段階と、
を含む方法。 - 前記解析音響モデルを構築する段階が、縮尺モデルBWR蒸気領域の3次元仮想モデルを作成する段階を含むことを特徴とする請求項1に記載の方法。
- 前記解析音響モデルを構築する段階が、前記BWR縮尺モデルから取得したテストデータを該解析音響モデルから取得した結果と相関させる段階を含むことを特徴とする請求項1に記載の方法。
- 前記解析音響モデルを構築する段階が、前記相関させる段階に基づいて、前記テストデータが該解析音響モデルから取得した結果と実質的に一致するまで該解析音響モデルを修正する段階を含むことを特徴とする請求項3に記載の方法。
- 前記圧力推定値を生成する段階が、前記BWR蒸気領域の音響モードを計算する段階を含むことを特徴とする請求項2に記載の方法。
- 前記圧力推定値を生成する段階が、前記音響モードの数を前記経験データ点の数に等しくなるように減少させる段階をさらに含むことを特徴とする請求項5に記載の方法。
- 前記圧力推定値を生成する段階が、
前記減少させた数の音響モード及び前記経験データに基づいてモード級数展開係数を計算して、音響メッシュの各節点における該圧力推定値を生成する段階と、
前記BWR縮尺モデルに対して生成した前記圧力推定値をスケーリングして、実物大BWR蒸気領域を表現する段階と、
をさらに含むことを特徴とする請求項6に記載の方法。 - 前記BWR蒸気乾燥器の解析構造モデルを構築する段階が、
前記BWR蒸気乾燥器の3次元仮想モデルを作成する段階と、
有限要素メッシングアルゴリズムを使用して前記3次元仮想モデルを離散化して、前記BWR蒸気乾燥器の構造メッシュを生成する段階と、
を含むことを特徴とする請求項1に記載の方法。 - 前記BWR縮尺モデルに対して生成した前記圧力推定値をスケーリングして、実物大BWR蒸気領域を表現する段階と、
前記解析構造モデルの構造メッシュ上に前記スケーリング圧力推定値を投影する段階と、
をさらに含むことを特徴とする請求項8に記載の方法。
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US11/503,268 US8437445B2 (en) | 2006-08-14 | 2006-08-14 | Method for predicting stresses on a steam system of a boiling water reactor |
US11/503,268 | 2006-08-14 |
Publications (2)
Publication Number | Publication Date |
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JP2008046120A JP2008046120A (ja) | 2008-02-28 |
JP5435847B2 true JP5435847B2 (ja) | 2014-03-05 |
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JP2007198406A Active JP5435847B2 (ja) | 2006-08-14 | 2007-07-31 | 沸騰水型原子炉の蒸気系に関する応力を予測する方法 |
Country Status (3)
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US (1) | US8437445B2 (ja) |
JP (1) | JP5435847B2 (ja) |
SE (1) | SE532923C2 (ja) |
Families Citing this family (5)
Publication number | Priority date | Publication date | Assignee | Title |
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US8437445B2 (en) | 2006-08-14 | 2013-05-07 | General Electric Company | Method for predicting stresses on a steam system of a boiling water reactor |
JP2009079906A (ja) * | 2007-09-25 | 2009-04-16 | Toshiba Corp | 振動評価装置及び方法 |
US8620643B1 (en) | 2009-07-31 | 2013-12-31 | Lester F. Ludwig | Auditory eigenfunction systems and methods |
JP6740167B2 (ja) * | 2017-04-20 | 2020-08-12 | 三菱日立パワーシステムズ株式会社 | タービンの組立方法、タービン組立支援システム及び制御プログラム |
GB201820356D0 (en) * | 2018-12-13 | 2019-01-30 | Expro North Sea Ltd | Methodology for analysis of valve dynamic closure performance |
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JPS58184585A (ja) | 1982-04-22 | 1983-10-28 | 株式会社東芝 | 原子炉格納容器内の異常検出装置 |
JPS63193061A (ja) | 1987-02-06 | 1988-08-10 | Hitachi Ltd | 振動音響異常判定方法 |
AU2683192A (en) * | 1991-09-17 | 1993-04-27 | General Physics International Engineering & Simulation, Inc. | Real time analysis of power plant thermohydraulic phenomenon |
JPH1114782A (ja) | 1997-06-19 | 1999-01-22 | Shikoku Electric Power Co Inc | 配管劣化評価方法及び装置 |
US5912933A (en) * | 1997-12-04 | 1999-06-15 | General Electric Company | Method and system for direct evaluation of operating limit minimum critical power ratios for boiling water reactors |
JP2002340726A (ja) | 2001-05-16 | 2002-11-27 | Toshiba Corp | 振動解析装置および振動解析方法 |
US7444246B2 (en) * | 2004-05-25 | 2008-10-28 | Bilanin Alan J | System and method for determining fluctuating pressure loading on a component in a reactor steam dome |
US8948334B2 (en) | 2005-10-31 | 2015-02-03 | General Electric Company | System and method for testing the steam system of a boiling water reactor |
JP4006014B2 (ja) | 2005-11-30 | 2007-11-14 | コンティニューム ダイナミックス,インコーポレイテッド | 原子炉蒸気ドームのコンポーネント上の変動圧力荷重を決定するためのシステムおよび方法 |
JP4430627B2 (ja) | 2006-02-28 | 2010-03-10 | 日立Geニュークリア・エナジー株式会社 | 沸騰水型原子炉の監視方法及びその監視プログラム |
US8009788B2 (en) | 2006-02-28 | 2011-08-30 | Hitachi, Ltd. | Monitoring method and monitoring program for boiling water reactor, and acoustic damping method for boiling water reactor |
US8437445B2 (en) | 2006-08-14 | 2013-05-07 | General Electric Company | Method for predicting stresses on a steam system of a boiling water reactor |
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2006
- 2006-08-14 US US11/503,268 patent/US8437445B2/en not_active Expired - Fee Related
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- 2007-07-31 JP JP2007198406A patent/JP5435847B2/ja active Active
- 2007-08-08 SE SE0701837A patent/SE532923C2/sv unknown
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Publication number | Publication date |
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SE0701837L (sv) | 2008-02-15 |
US20100260301A1 (en) | 2010-10-14 |
US8437445B2 (en) | 2013-05-07 |
JP2008046120A (ja) | 2008-02-28 |
SE532923C2 (sv) | 2010-05-11 |
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