FR2034266A1 - Coolant circuit for gas-cooled, heavy water - moderated nuclear reactor - Google Patents

Coolant circuit for gas-cooled, heavy water - moderated nuclear reactor

Info

Publication number
FR2034266A1
FR2034266A1 FR6906106A FR6906106A FR2034266A1 FR 2034266 A1 FR2034266 A1 FR 2034266A1 FR 6906106 A FR6906106 A FR 6906106A FR 6906106 A FR6906106 A FR 6906106A FR 2034266 A1 FR2034266 A1 FR 2034266A1
Authority
FR
France
Prior art keywords
tube
coolant
pressure
cooled
gas
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.)
Pending
Application number
FR6906106A
Other languages
French (fr)
Inventor
Foulquier Henri
Thome Paul
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
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 Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Priority to FR6906106A priority Critical patent/FR2034266A1/en
Publication of FR2034266A1 publication Critical patent/FR2034266A1/en
Pending legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • 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
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G21C13/04—Arrangements for expansion and contraction
    • 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
    • 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

Each coolant tube has a calendar tube coaxially surrounding it, forming an annular space about the core material and coolant tube filled with a fluid e.g. CO2, at a pressure between that of the coolant within its tube and the moderator pressure around the calender tube. In the limit, the pressure is equal to the coolant pressure. Pref. the tube crossing the reactor core is of a Zr alloy and ends in a steel ferrule on a steel extension, on which is a stainless steel fixing sleeve.
FR6906106A 1969-03-05 1969-03-05 Coolant circuit for gas-cooled, heavy water - moderated nuclear reactor Pending FR2034266A1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR6906106A FR2034266A1 (en) 1969-03-05 1969-03-05 Coolant circuit for gas-cooled, heavy water - moderated nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR6906106A FR2034266A1 (en) 1969-03-05 1969-03-05 Coolant circuit for gas-cooled, heavy water - moderated nuclear reactor

Publications (1)

Publication Number Publication Date
FR2034266A1 true FR2034266A1 (en) 1970-12-11

Family

ID=9030131

Family Applications (1)

Application Number Title Priority Date Filing Date
FR6906106A Pending FR2034266A1 (en) 1969-03-05 1969-03-05 Coolant circuit for gas-cooled, heavy water - moderated nuclear reactor

Country Status (1)

Country Link
FR (1) FR2034266A1 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4808370A (en) * 1985-05-23 1989-02-28 Interatom Gmbh Connection of a hot gas line to the core barrel of a gas-cooled high-temperature nuclear reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4808370A (en) * 1985-05-23 1989-02-28 Interatom Gmbh Connection of a hot gas line to the core barrel of a gas-cooled high-temperature nuclear reactor

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