GB2550439B - Method of relieving stress in graphite bricks of a gas-cooled nuclear reactor - Google Patents

Method of relieving stress in graphite bricks of a gas-cooled nuclear reactor

Info

Publication number
GB2550439B
GB2550439B GB1618568.8A GB201618568A GB2550439B GB 2550439 B GB2550439 B GB 2550439B GB 201618568 A GB201618568 A GB 201618568A GB 2550439 B GB2550439 B GB 2550439B
Authority
GB
United Kingdom
Prior art keywords
gas
nuclear reactor
relieving stress
cooled nuclear
graphite bricks
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.)
Active
Application number
GB1618568.8A
Other versions
GB2550439A (en
Inventor
Evgenievich Fedosovsky Mikhail
Igorevich Dunaev Vadim
Aleksandrovich Gurin Denis
Petit De Mange Edward
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.)
Diakont Advanced Technologies Inc
Original Assignee
Diakont Advanced Technologies 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 Diakont Advanced Technologies Inc filed Critical Diakont Advanced Technologies Inc
Publication of GB2550439A publication Critical patent/GB2550439A/en
Application granted granted Critical
Publication of GB2550439B publication Critical patent/GB2550439B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/04Thermal reactors ; Epithermal reactors
    • G21C1/06Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G21C1/10Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated
    • G21C1/12Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite reactor
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C5/00Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02Details
    • G21C5/08Means for preventing undesired asymmetric expansion of the complete structure ; Stretching devices, pins
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C5/00Moderator or core structure; Selection of materials for use as moderator
    • G21C5/12Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
    • G21C5/126Carbonic moderators
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C5/00Moderator or core structure; Selection of materials for use as moderator
    • G21C5/14Moderator or core structure; Selection of materials for use as moderator characterised by shape
    • G21C5/16Shape of its constituent parts
    • 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
GB1618568.8A 2016-10-07 2016-11-03 Method of relieving stress in graphite bricks of a gas-cooled nuclear reactor Active GB2550439B (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US201662405491P 2016-10-07 2016-10-07

Publications (2)

Publication Number Publication Date
GB2550439A GB2550439A (en) 2017-11-22
GB2550439B true GB2550439B (en) 2019-03-27

Family

ID=60155673

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1618568.8A Active GB2550439B (en) 2016-10-07 2016-11-03 Method of relieving stress in graphite bricks of a gas-cooled nuclear reactor

Country Status (1)

Country Link
GB (1) GB2550439B (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB201809736D0 (en) * 2018-06-14 2018-08-01 Cavendish Nuclear Ltd Graphite cores

Non-Patent Citations (4)

* Cited by examiner, † Cited by third party
Title
Engineering fracture mechanics 73, no. 3 (2006) Zou, Z., S. L. Fok, B. J. Marsden, and S. O. Oyadiji. "Numerical simulation of strength test on graphite moderator bricks using a continuum damage mechanics model." p318-330. *
International journal of impact engineering 32, no. 6 (2006) Kuroda, Masatoshi, Siu Lun Fok, Barry J. Marsden, and S. Olutunde Oyadiji. "Analyses of the multiple cracking behaviour of brittle hollow cylinders under internal pressure." pages 905-927. *
Nuclear Engineering and Design 235, no. 5 (2005) Kuroda, Masatoshi, Siu Lun Fok, Barry J. Marsden, and S. Olutunde Oyadiji. "Dynamics and generation of stress waves in cracked graphite moderator bricks." p557-573. *
Nuclear Engineering and Design 280 (2014) Wadsworth, M., Si Thu Kyaw, and Wei Sun. "Finite element modelling of the effect of temperature and neutron dose on the fracture behaviour of nuclear reactor graphite bricks." p1-7. *

Also Published As

Publication number Publication date
GB2550439A (en) 2017-11-22

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