GB1172721A – Heat Insulation System in a Reactor Having Zirconium Alloy Pressure Tubes.
– Google Patents
GB1172721A – Heat Insulation System in a Reactor Having Zirconium Alloy Pressure Tubes.
– Google Patents
Heat Insulation System in a Reactor Having Zirconium Alloy Pressure Tubes.
Info
Publication number
GB1172721A
GB1172721A
GB01976/67A
GB1197667A
GB1172721A
GB 1172721 A
GB1172721 A
GB 1172721A
GB 01976/67 A
GB01976/67 A
GB 01976/67A
GB 1197667 A
GB1197667 A
GB 1197667A
GB 1172721 A
GB1172721 A
GB 1172721A
Authority
GB
United Kingdom
Prior art keywords
tube
gas
internal
reactor
pressure tube
Prior art date
1966-03-31
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
GB01976/67A
Inventor
Mario Montagnani
Flaviano Farfaletti-Casali
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.)
European Atomic Energy Community Euratom
Original Assignee
European Atomic Energy Community Euratom
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.)
1966-03-31
Filing date
1967-03-14
Publication date
1969-12-03
1967-03-14
Application filed by European Atomic Energy Community Euratom
filed
Critical
European Atomic Energy Community Euratom
1969-12-03
Publication of GB1172721A
publication
Critical
patent/GB1172721A/en
Status
Expired
legal-status
Critical
Current
Links
Espacenet
Global Dossier
Discuss
238000009413
insulation
Methods
0.000
title
abstract
3
229910001093
Zr alloy
Inorganic materials
0.000
title
1
OKTJSMMVPCPJKN-UHFFFAOYSA-N
Carbon
Chemical compound
[C]
OKTJSMMVPCPJKN-UHFFFAOYSA-N
0.000
abstract
2
229910052790
beryllium
Inorganic materials
0.000
abstract
2
ATBAMAFKBVZNFJ-UHFFFAOYSA-N
beryllium atom
Chemical compound
[Be]
ATBAMAFKBVZNFJ-UHFFFAOYSA-N
0.000
abstract
2
QCWXUUIWCKQGHC-UHFFFAOYSA-N
Zirconium
Chemical compound
[Zr]
QCWXUUIWCKQGHC-UHFFFAOYSA-N
0.000
abstract
1
229910052799
carbon
Inorganic materials
0.000
abstract
1
239000002826
coolant
Substances
0.000
abstract
1
229910002804
graphite
Inorganic materials
0.000
abstract
1
239000010439
graphite
Substances
0.000
abstract
1
238000009421
internal insulation
Methods
0.000
abstract
1
239000007788
liquid
Substances
0.000
abstract
1
230000005855
radiation
Effects
0.000
abstract
1
229910052726
zirconium
Inorganic materials
0.000
abstract
1
Classifications
G—PHYSICS
G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
G21C—NUCLEAR REACTORS
G21C11/00—Shielding structurally associated with the reactor
G21C11/08—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation
F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
F16L—PIPES; JOINTS OR FITTINGS FOR PIPES; SUPPORTS FOR PIPES, CABLES OR PROTECTIVE TUBING; MEANS FOR THERMAL INSULATION IN GENERAL
F16L59/00—Thermal insulation in general
F16L59/14—Arrangements for the insulation of pipes or pipe systems
F16L59/147—Arrangements for the insulation of pipes or pipe systems the insulation being located inwardly of the outer surface of the pipe
G—PHYSICS
G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
G21C—NUCLEAR REACTORS
G21C1/00—Reactor types
G21C1/04—Thermal reactors ; Epithermal reactors
G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
G—PHYSICS
G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
G21C—NUCLEAR REACTORS
G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
G21C15/20—Partitions or thermal insulation between fuel channel and moderator
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
G21C3/06—Casings; Jackets
G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
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
Abstract
1,172,721. Reactors. EUROPEAN ATOMIC ENERGY COMMUNITY. 14 March, 1967 [31 March, 1966], No. 11976/67. Heading G6C. In a nuclear reactor pressure tube, formed of zirconium or beryllium, thermal insulation is provided at both the inner and outer surfaces. The tube is thereby maintained between predetermined temperature limits within which it has acceptable mechanical properties under the working thermal and radiation conditions. The reactor coolant flowing within the tube is an organic liquid. The internal insulation may be of carbon or graphite and the external layer of a gas between the pressure tube and the surrounding calandria tube. In further embodiments, both internal and external gas layers provide the thermal insulation and the internal gas layer may be either annular or formed of gas-filled beryllium tubes at the inner wall of the pressure tube.
GB01976/67A
1966-03-31
1967-03-14
Heat Insulation System in a Reactor Having Zirconium Alloy Pressure Tubes.
Expired
GB1172721A
(en)
Applications Claiming Priority (1)
Application Number
Priority Date
Filing Date
Title
IT1627466
1966-03-31
Publications (1)
Publication Number
Publication Date
GB1172721A
true
GB1172721A
(en)
1969-12-03
Family
ID=11148661
Family Applications (1)
Application Number
Title
Priority Date
Filing Date
GB01976/67A
Expired
GB1172721A
(en)
1966-03-31
1967-03-14
Heat Insulation System in a Reactor Having Zirconium Alloy Pressure Tubes.
Country Status (8)
Country
Link
US
(1)
US3434925A
(en)
BE
(1)
BE696295A
(en)
DE
(1)
DE1589723A1
(en)
ES
(1)
ES338116A1
(en)
GB
(1)
GB1172721A
(en)
IL
(1)
IL27613A
(en)
LU
(1)
LU53314A1
(en)
NL
(1)
NL6704546A
(en)
Families Citing this family (1)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
US4751021A
(en)
*
1985-12-30
1988-06-14
Aar Corporation
Bendable sheet material
Family Cites Families (6)
* Cited by examiner, † Cited by third party
Publication number
Priority date
Publication date
Assignee
Title
DE736342C
(en)
*
1934-11-28
1943-06-12
Alfol Dyckerhoff Fa
Heating element made of metallic plates or foils arranged at a distance from one another
BE565765A
(en)
*
1957-03-19
DE1108340B
(en)
*
1958-05-14
1961-06-08
Siemens Ag
Thermal insulation made up of layers for the moderator boiler of a nuclear reactor
DE1250932B
(en)
*
1962-01-31
1900-01-01
BE630214A
(en)
*
1962-04-17
1900-01-01
US3231339A
(en)
*
1963-09-13
1966-01-25
Gas Council
Thermally insulated reaction vessels
1967
1967-03-14
GB
GB01976/67A
patent/GB1172721A/en
not_active
Expired
1967-03-15
IL
IL27613A
patent/IL27613A/en
unknown
1967-03-16
ES
ES338116A
patent/ES338116A1/en
not_active
Expired
1967-03-16
US
US623634A
patent/US3434925A/en
not_active
Expired – Lifetime
1967-03-29
LU
LU53314D
patent/LU53314A1/xx
unknown
1967-03-30
NL
NL6704546A
patent/NL6704546A/xx
unknown
1967-03-30
DE
DE19671589723
patent/DE1589723A1/en
active
Pending
1967-03-30
BE
BE696295D
patent/BE696295A/xx
unknown
Also Published As
Publication number
Publication date
IL27613A
(en)
1970-12-24
NL6704546A
(en)
1967-10-02
ES338116A1
(en)
1970-02-01
US3434925A
(en)
1969-03-25
LU53314A1
(en)
1967-05-29
BE696295A
(en)
1967-09-01
DE1589723A1
(en)
1970-04-09
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Legal Events
Date
Code
Title
Description
1970-04-15
PS
Patent sealed [section 19, patents act 1949]
1972-10-11
PLNP
Patent lapsed through nonpayment of renewal fees
