JP4948966B2 - 沸騰水型原子炉の蒸気系統を試験するためのシステムおよび方法 - Google Patents
沸騰水型原子炉の蒸気系統を試験するためのシステムおよび方法 Download PDFInfo
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- JP4948966B2 JP4948966B2 JP2006288173A JP2006288173A JP4948966B2 JP 4948966 B2 JP4948966 B2 JP 4948966B2 JP 2006288173 A JP2006288173 A JP 2006288173A JP 2006288173 A JP2006288173 A JP 2006288173A JP 4948966 B2 JP4948966 B2 JP 4948966B2
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- 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
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
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- 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
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Description
Busan, "Flatter model technology", WL-TR-97-3074, Flight dynamic directorate, Wright Laboratory, 1998 Takahashi et al., "Evaluation of flow-Induced Vibration for fixed type Guide Rods of Shroud Head and Steam Dryer in ABWR", Proc. Of CONE 10 10th Internat. Conf. on Nuclear Engineering, Arlington, VA, April 14018, 2002.
100 音響学的試験システム
110 試験治具
120 BWRの縮尺模型
130 送風機
140 入口管
150 流量計
160 マフラ
170 縮尺版のRPV
175 トップヘッド
180 蒸気乾燥器
190 蒸気ライン
200 管長さ調整器
210 第1の管区画
220 第2の管区画
230 管長さ調整デバイス
240 長さ調整設定デバイス
250 基準線
260 第1のブラケット
270 第2のブラケット
280 Oリング(図示せず?)
300 リリーフ弁入口調整器
310 弁管
320 弁挿入部
330 弁挿入頂部
340 弁長さ設定デバイス
350 弁ハウジング
360 弁座
370 Oリングシール
400 タービン弁
500 タービン入口
700 リリーフ弁
800 主蒸気隔離弁
900 均圧ヘッダ
Claims (9)
- 沸騰水型原子炉(BWR)の蒸気乾燥器に見込まれる音響負荷を予測するためのシステムであって、
BWRの縮尺模型、
前記BWRの縮尺模型に空気流れを発生させるように構成された試験治具と、
システム挙動をモニタするように構成された前記BWRの縮尺模型に取り付けられた少なくとも1つの測定デバイスと、
を備え、
前記BWRの縮尺模型は、原子炉圧力容器と、蒸気乾燥器と、少なくとも1つの主蒸気ライン、の縮尺模型であり、
前記BWRの縮尺模型は、前記原子炉圧力容器と蒸気乾燥器と主蒸気ライン管(190)の縮尺模型ための、管長さ調整部(200)またはリリーフ弁入口長さ調整部(300)を含む調整可能構成要素を備えることを特徴とする音響負荷予測システム。 - 前記調整可能な構成要素が、第1の管区画(210)を第2の管区画(220)へ挿入し或いはこの第2の管区画(220)から抜き出して、前記管長さ調整部(200)の有効長を変更することを特徴とする請求項1記載の音響負荷予測システム。
- 前記試験治具が空気流を発生させるように構成された少なくとも1つの送風機(130)を備えることを特徴とする請求項1または2記載の音響負荷予測システム。
- 前記試験治具が、そこから前記縮尺模型に空気を搬送するように構成された入口管、および前記試験治具を前記縮尺模型に連結し、前記試験治具によって前記システムに入るノイズを低減するように構成されたマフラ(160)をさらに備え、前記入口管が空気を前記マフラに移送するようにも構成されたことを特徴とする請求項1乃至3のいずれかに記載の音響負荷予測システム。
- 前記少なくとも1つの測定デバイス(50)が、システム内の圧力変動を測定するように構成されたことを特徴とする請求項1記載の音響負荷予測システム。
- 前記少なくとも1つの測定デバイス(50)が、さらに、全システム空気流れ、前記縮尺模型内の絶対空気静圧、および前記システム内の空気温度のうちの少なくとも1つをモニタすることを特徴とする請求項1乃至5のいずれかに記載の方法。
- 前記少なくとも1つの主蒸気ラインが前記少なくとも1つの調整可能構成要素に結合され、この調整可能構成要素は、更に、調整可能な主蒸気隔離弁(800)、調整可能なタービン塞止弁(400)、および調整可能なタービン制御弁(400)から選択された少なくとも1つの調整可能な構成要素と連結するようになされたことを特徴とする請求項1記載の音響負荷予測システム。
- 沸騰水型原子炉(BWR)の蒸気乾燥器に見込まれる音響負荷を予測するための方法であって、
圧力容器と蒸気乾燥器と少なくとも1つの主蒸気ラインとを含む、評価対象のBWRの縮尺模型であって、少なくとも前記圧力容器と蒸気乾燥器と少なくとも1つの主蒸気ラインのいずれか1つのための管長調整部を含む縮尺模型を提供するステップと、
前記縮尺模型を通る空気流れを発生させるステップと、
評価されている前記BWRでのプラント動作に音響負荷がどのように影響を与えるか予測するために、前記縮尺模型のシステム挙動をモニタするモニタステップとを含み、
前記モニタステップは、前記縮尺模型に含まれる管長調整部を調整するステップを含むことを特徴とする音響負荷予測方法。 - モニタするステップが、前記システム内の圧力変動、全システム空気流れ、前記縮尺模型内の絶対空気静圧、および前記システム内の空気温度のうちの少なくとも1つをモニタするステップを含むことを特徴とする請求項8記載の方法。
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US11/261,489 | 2005-10-31 | ||
| US11/261,489 US8948334B2 (en) | 2005-10-31 | 2005-10-31 | System and method for testing the steam system of a boiling water reactor |
Publications (3)
| Publication Number | Publication Date |
|---|---|
| JP2007127633A JP2007127633A (ja) | 2007-05-24 |
| JP2007127633A5 JP2007127633A5 (ja) | 2009-12-10 |
| JP4948966B2 true JP4948966B2 (ja) | 2012-06-06 |
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| Application Number | Title | Priority Date | Filing Date |
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| JP2006288173A Active JP4948966B2 (ja) | 2005-10-31 | 2006-10-24 | 沸騰水型原子炉の蒸気系統を試験するためのシステムおよび方法 |
Country Status (6)
| Country | Link |
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| US (1) | US8948334B2 (ja) |
| JP (1) | JP4948966B2 (ja) |
| KR (1) | KR101297534B1 (ja) |
| CH (1) | CH699377B1 (ja) |
| ES (1) | ES2319144A1 (ja) |
| TW (1) | TWI409825B (ja) |
Families Citing this family (4)
| 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 |
| US20140251020A1 (en) * | 2013-03-05 | 2014-09-11 | Ge-Hitachi Nuclear Energy Americas Llc | Method and apparatus for pipe pressure measurements |
| CN109920315B (zh) * | 2019-03-29 | 2019-11-08 | 济南大学 | 一种虚拟α粒子散射实验系统 |
| CN112967578A (zh) * | 2021-01-29 | 2021-06-15 | 重庆医药高等专科学校 | 一种可视化安全试验控制方法 |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| US3665964A (en) * | 1971-01-27 | 1972-05-30 | Westinghouse Electric Corp | Steam turbine control valve structure |
| JPS5847798A (ja) * | 1981-09-09 | 1983-03-19 | 象印チエンブロツク株式会社 | 電動チエンブロック |
| SU1229506A1 (ru) * | 1984-05-14 | 1986-05-07 | Всесоюзный научно-исследовательский и проектно-конструкторский институт промышленных гидроприводов и гидроавтоматики | Гаситель пульсаций давлени |
| EP0189033B1 (en) * | 1985-01-23 | 1989-03-15 | Westinghouse Electric Corporation | Steam generator wrapper accommodating tube support members of high thermal expansion coefficient material |
| JPS6332394A (ja) * | 1986-07-25 | 1988-02-12 | 株式会社東芝 | 原子炉建屋燃料交換床の換気空調方法 |
| JPS63311196A (ja) * | 1987-06-15 | 1988-12-19 | Hitachi Ltd | 蒸気乾燥器 |
| US5289901A (en) * | 1992-08-03 | 1994-03-01 | Otis Elevator Company | Hydraulic elevator pressure relief valve |
| JPH0682591A (ja) * | 1992-09-01 | 1994-03-22 | Hitachi Ltd | 気水分離器 |
| US5887043A (en) * | 1995-10-03 | 1999-03-23 | Atomic Energy Of Canada Limited Energie Atomique Du Canad | Passive emergency water system for water-cooled nuclear reactors |
| US5682410A (en) * | 1995-10-17 | 1997-10-28 | General Electric Company | Method for determining core flow rate and water temperature/density in boiling water reactor |
| JPH1085161A (ja) * | 1996-09-13 | 1998-04-07 | Mitsubishi Electric Corp | 電気掃除機 |
| DE19743333C2 (de) * | 1997-09-30 | 2002-02-28 | Framatome Anp Gmbh | Abblasevorrichtung und Verfahren zum Abblasen von Dampf |
| 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 |
| US6697447B1 (en) * | 1999-12-30 | 2004-02-24 | General Electric Company | Maximum extended load line limit analysis for a boiling water nuclear reactor |
| 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 |
| JP4607736B2 (ja) * | 2004-11-05 | 2011-01-05 | 株式会社日立製作所 | 沸騰水型原子炉 |
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- 2006-10-27 CH CH01715/06A patent/CH699377B1/de unknown
- 2006-10-30 KR KR1020060105858A patent/KR101297534B1/ko active Active
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| Publication number | Publication date |
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| JP2007127633A (ja) | 2007-05-24 |
| KR101297534B1 (ko) | 2013-08-16 |
| CH699377B1 (de) | 2010-02-26 |
| TW200733137A (en) | 2007-09-01 |
| ES2319144A1 (es) | 2009-05-04 |
| US20070098131A1 (en) | 2007-05-03 |
| US8948334B2 (en) | 2015-02-03 |
| KR20070046753A (ko) | 2007-05-03 |
| TWI409825B (zh) | 2013-09-21 |
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