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ES535427A0 - Un metodo de ensayar la interaccion entre pastillas y vaina de combustible nuclear. - Google Patents

Un metodo de ensayar la interaccion entre pastillas y vaina de combustible nuclear.

Info

Publication number
ES535427A0
ES535427A0 ES535427A ES535427A ES535427A0 ES 535427 A0 ES535427 A0 ES 535427A0 ES 535427 A ES535427 A ES 535427A ES 535427 A ES535427 A ES 535427A ES 535427 A0 ES535427 A0 ES 535427A0
Authority
ES
Spain
Prior art keywords
pills
interaction
testing
nuclear fuel
fuel pod
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
ES535427A
Other languages
English (en)
Other versions
ES8706281A1 (es
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.)
Babcock and Wilcox Co
Original Assignee
Babcock and Wilcox Co
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Babcock and Wilcox Co filed Critical Babcock and Wilcox Co
Publication of ES535427A0 publication Critical patent/ES535427A0/es
Publication of ES8706281A1 publication Critical patent/ES8706281A1/es
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/16—Details of the construction within the casing
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/001—Mechanical simulators
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F24—HEATING; RANGES; VENTILATING
    • F24S—SOLAR HEAT COLLECTORS; SOLAR HEAT SYSTEMS
    • F24S23/00—Arrangements for concentrating solar-rays for solar heat collectors
    • F24S23/12—Light guides
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F24—HEATING; RANGES; VENTILATING
    • F24S—SOLAR HEAT COLLECTORS; SOLAR HEAT SYSTEMS
    • F24S23/00—Arrangements for concentrating solar-rays for solar heat collectors
    • F24S23/30—Arrangements for concentrating solar-rays for solar heat collectors with lenses
    • 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
    • Y02E10/00—Energy generation through renewable energy sources
    • Y02E10/40—Solar thermal energy, e.g. solar towers
    • 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

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Sustainable Development (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Energy (AREA)
  • Thermal Sciences (AREA)
  • Chemical & Material Sciences (AREA)
  • Combustion & Propulsion (AREA)
  • Mechanical Engineering (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
ES535427A 1983-08-24 1984-08-24 Un metodo de ensayar la interaccion entre pastillas y vaina de combustible nuclear. Expired ES8706281A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US06/526,172 US4643866A (en) 1983-08-24 1983-08-24 Nuclear fuel pellet-cladding interaction test device and method modeling in-core reactor thermal conditions

Publications (2)

Publication Number Publication Date
ES535427A0 true ES535427A0 (es) 1987-06-01
ES8706281A1 ES8706281A1 (es) 1987-06-01

Family

ID=24096218

Family Applications (3)

Application Number Title Priority Date Filing Date
ES535427A Expired ES8706281A1 (es) 1983-08-24 1984-08-24 Un metodo de ensayar la interaccion entre pastillas y vaina de combustible nuclear.
ES557452A Expired ES9200013A1 (es) 1983-08-24 1987-03-16 Un aparato para ensayar la interaccion entre pastillas y vaina de combustible nuclear
ES557852A Expired ES9200014A1 (es) 1983-08-24 1988-09-16 Un aparato para ensayar la interaccion entre pastillas y vaina de combustible nuclear

Family Applications After (2)

Application Number Title Priority Date Filing Date
ES557452A Expired ES9200013A1 (es) 1983-08-24 1987-03-16 Un aparato para ensayar la interaccion entre pastillas y vaina de combustible nuclear
ES557852A Expired ES9200014A1 (es) 1983-08-24 1988-09-16 Un aparato para ensayar la interaccion entre pastillas y vaina de combustible nuclear

Country Status (6)

Country Link
US (1) US4643866A (es)
EP (1) EP0138340B1 (es)
KR (1) KR850001618A (es)
CA (1) CA1214340A (es)
DE (1) DE3463421D1 (es)
ES (3) ES8706281A1 (es)

Families Citing this family (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5260218A (en) * 1990-10-29 1993-11-09 Combustion Engineering, Inc. Autoclave corrosion test for zirconium alloys
US6228337B1 (en) * 1998-12-02 2001-05-08 Cameco Corporation Method for reducing uranium trioxide
FR2846139B1 (fr) * 2002-10-21 2005-02-18 Framatome Anp Procede de determination d'une valeur limite d'un parametre de fonctionnement d'un reacteur nucleaire, programme et support correspondants
KR100971914B1 (ko) * 2008-10-14 2010-07-22 한국원자력연구원 초고온 가스로의 동심축 이중관형 고온가스관의 설계방법
CN102597512B (zh) * 2009-07-20 2016-01-20 斯洛博丹·泰皮奇 发电设备
FR2988974B1 (fr) * 2012-04-02 2017-09-01 Commissariat Energie Atomique Dispositif pour generer un gradient eleve de temperature dans un echantillon de type combustible nucleaire
FR3011711B1 (fr) * 2013-10-03 2015-12-11 Commissariat Energie Atomique Dispositif pour generer un gradient eleve de temperature dans un echantillon de type combustible nucleaire
RU2581846C1 (ru) * 2015-03-02 2016-04-20 Российская Федерация от имени которой выступает Государственная корпорация по атомной энергии "Росатом" Способ испытания на совместимость порошка ядерного топлива с материалом оболочки твэла
CN113409963A (zh) * 2021-06-17 2021-09-17 中国核动力研究设计院 一种克服芯块包壳机械相互作用的燃料棒及燃料组件
CN113776936B (zh) * 2021-08-17 2022-10-28 中国原子能科学研究院 一种堆外模拟芯块包壳力学相互作用的试验装置
CN115112706B (zh) * 2022-06-23 2025-05-02 华南理工大学 模拟铅铋堆包壳熔化和碎片迁移的可视化实验装置及方法
CN115050493B (zh) * 2022-06-27 2024-08-09 中国核动力研究设计院 一种压水堆燃料棒包壳材料辐照考验方法
CN116612909B (zh) * 2023-05-30 2025-12-23 中广核研究院有限公司 核反应堆燃料棒束事故失效行为研究的实验装置及方法
CN119480178B (zh) * 2024-09-20 2025-08-05 中国核动力研究设计院 燃料棒pci性能风险评估方法、装置、存储介质及电子设备

Family Cites Families (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2656256A (en) * 1946-03-18 1953-10-20 Max L Yeater Method of testing a metallic sample
DE1248822B (es) * 1965-03-31
BE744908A (fr) * 1969-02-01 1970-07-01 Euratom Appareil pour l'etude de l'evolution de la structure de carbured'uranium soumis a un gradient thermique radial
DE2019663A1 (de) * 1970-04-23 1971-11-11 Siemens Ag Einrichtung zur Untersuchung der Waermeuebertragungsprobleme an Modellbrennstaeben von Kernreaktoren
DE2314650C3 (de) * 1973-03-23 1978-10-12 Kraftwerk Union Ag, 4330 Muelheim Verfahren und Einrichtung zur Auffindung defekter Brennstäbe
DE2427662A1 (de) * 1973-06-11 1975-01-02 Varian Associates Waermesimulator
US3988565A (en) * 1973-06-11 1976-10-26 Varian Associates Nuclear reactor fuel rod thermal simulator
US3916670A (en) * 1973-10-18 1975-11-04 Hobart Corp Analysis of comminuted meat products
DE2505645C2 (de) * 1975-02-11 1982-06-24 Brown Boveri Reaktor Gmbh Verfahren zum Lokalisieren defekter Brennstäbe eines Reaktorbrennelements
NO136429C (no) * 1976-02-12 1977-09-07 Atomenergi Inst For Fremgangsm}te og apparat for } bestemme den radiale avstand mellom brensel og den omgivende kapsling i en brenselsstav for kjernereaktorer.
FR2389202A1 (fr) * 1977-04-29 1978-11-24 Framatome Sa Cellule de ressuage pour le controle de l'etancheite d'assemblages d'elements combustibles et procede de controle correspondant
US4485284A (en) * 1982-01-11 1984-11-27 Advanced Moisture Technology, Inc. Apparatus and process for microwave moisture analysis

Also Published As

Publication number Publication date
EP0138340B1 (en) 1987-04-29
KR850001618A (ko) 1985-03-30
ES9200014A1 (es) 1989-03-01
ES9200013A1 (es) 1989-03-01
ES557852A0 (es) 1989-03-01
ES557452A0 (es) 1989-03-01
DE3463421D1 (en) 1987-06-04
EP0138340A1 (en) 1985-04-24
ES8706281A1 (es) 1987-06-01
CA1214340A (en) 1986-11-25
US4643866A (en) 1987-02-17

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