GB1457670A - Nuclear reactor fuel rod thermal simulator - Google Patents

Nuclear reactor fuel rod thermal simulator

Info

Publication number
GB1457670A
GB1457670A GB2571874A GB2571874A GB1457670A GB 1457670 A GB1457670 A GB 1457670A GB 2571874 A GB2571874 A GB 2571874A GB 2571874 A GB2571874 A GB 2571874A GB 1457670 A GB1457670 A GB 1457670A
Authority
GB
United Kingdom
Prior art keywords
electrode
tungsten
tube
fuel rod
insulators
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.)
Expired
Application number
GB2571874A
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.)
Varian Medical Systems Inc
Original Assignee
Varian Associates Inc
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 Varian Associates Inc filed Critical Varian Associates Inc
Publication of GB1457670A publication Critical patent/GB1457670A/en
Expired legal-status Critical Current

Links

Classifications

    • HELECTRICITY
    • H05ELECTRIC TECHNIQUES NOT OTHERWISE PROVIDED FOR
    • H05BELECTRIC HEATING; ELECTRIC LIGHT SOURCES NOT OTHERWISE PROVIDED FOR; CIRCUIT ARRANGEMENTS FOR ELECTRIC LIGHT SOURCES, IN GENERAL
    • H05B7/00Heating by electric discharge
    • H05B7/16Heating by glow discharge
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/001Mechanical simulators
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Lasers (AREA)

Abstract

1457670 Heating by glow discharge VARIAN ASSOCIATES 10 June 1974 [11 June 1973] 25718/74 Heading H5H A nuclear fuel rod thermal simulator comprises a stainless steel tube 16, a part of which 15 is hermetically sealed and is heatable by glow discharge. The part 15, bounded by insulators 17, 17<SP>1</SP>, contains a discharge sustaining gas (e.g. hydrogen or helium) at reduced pressure (e.g. 2À5 torr) and has a central electrode 18, the stainless steel tube 16, earthed, being the other electrode. Part 15 may be heated to 900‹ C. Tube 16 may have a liner 37, of tungsten, molybdenum or an alloy of one of these with a platinum metal. Electrode 18 may be a tungsten wire or a tungsten tube partially filled with silver that is vaporized at operating temperatures and acts as a heat pipe. Insulators 17, 17<SP>1</SP> may be of thorium dioxide and shaped at the facing ends to provide long current leakage paths. Thermocouple 23 has connecting leads 25; current supply to electrode 18 is via lead 22.
GB2571874A 1973-06-11 1974-06-10 Nuclear reactor fuel rod thermal simulator Expired GB1457670A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US36855973A 1973-06-11 1973-06-11

Publications (1)

Publication Number Publication Date
GB1457670A true GB1457670A (en) 1976-12-08

Family

ID=23451749

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2571874A Expired GB1457670A (en) 1973-06-11 1974-06-10 Nuclear reactor fuel rod thermal simulator

Country Status (4)

Country Link
JP (1) JPS5032389A (en)
DE (1) DE2427662A1 (en)
FR (1) FR2232821B3 (en)
GB (1) GB1457670A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4643866A (en) * 1983-08-24 1987-02-17 The Babcock & Wilcox Company Nuclear fuel pellet-cladding interaction test device and method modeling in-core reactor thermal conditions
CN108511093A (en) * 2018-04-16 2018-09-07 西安交通大学 A kind of PWR Fuel cluster high-temperature heating clamping experimental provision
CN110136853A (en) * 2019-05-14 2019-08-16 中国核动力研究设计院 A kind of fuel assembly impact test support device and its frequency adjustment method
CN111161897A (en) * 2019-12-27 2020-05-15 西北核技术研究院 High-power thick rod fuel element simulation device

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104078087B (en) * 2014-06-24 2016-05-25 西安交通大学 A kind of cluster testpieces of simulating Supercritical-Pressure Light Water Cooled Reactor fuel element
CN107240427B (en) * 2017-06-26 2018-03-20 中国核动力研究设计院 High temperature resistant cluster fuel assembly analogue means based on Diffusion Welding
CN112951458A (en) * 2019-12-10 2021-06-11 核工业西南物理研究院 Thermal shock experimental device for detecting air tightness of fusion device connecting part

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4643866A (en) * 1983-08-24 1987-02-17 The Babcock & Wilcox Company Nuclear fuel pellet-cladding interaction test device and method modeling in-core reactor thermal conditions
CN108511093A (en) * 2018-04-16 2018-09-07 西安交通大学 A kind of PWR Fuel cluster high-temperature heating clamping experimental provision
CN108511093B (en) * 2018-04-16 2019-05-03 西安交通大学 A kind of PWR Fuel cluster high-temperature heating clamping experimental provision
CN110136853A (en) * 2019-05-14 2019-08-16 中国核动力研究设计院 A kind of fuel assembly impact test support device and its frequency adjustment method
CN110136853B (en) * 2019-05-14 2022-02-01 中国核动力研究设计院 Fuel assembly impact test supporting device and frequency adjusting method thereof
CN111161897A (en) * 2019-12-27 2020-05-15 西北核技术研究院 High-power thick rod fuel element simulation device
CN111161897B (en) * 2019-12-27 2021-10-08 西北核技术研究院 High-power thick rod fuel element simulation device

Also Published As

Publication number Publication date
FR2232821A1 (en) 1975-01-03
FR2232821B3 (en) 1976-06-18
DE2427662A1 (en) 1975-01-02
JPS5032389A (en) 1975-03-29

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Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee