UST921015I4 - Nuclear reactor corii cooling arrangement - Google Patents

Nuclear reactor corii cooling arrangement Download PDF

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Publication number
UST921015I4
UST921015I4 US921015DH UST921015I4 US T921015 I4 UST921015 I4 US T921015I4 US 921015D H US921015D H US 921015DH US T921015 I4 UST921015 I4 US T921015I4
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United States
Prior art keywords
nuclear reactor
systems
cooling arrangement
flow
corii
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Pending
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Publication of UST921015I4 publication Critical patent/UST921015I4/en
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • 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

Definitions

  • a core cooling system for a nuclear reactor having a plurality of primary fluid flow systems.
  • the reactor coolant flow from the primary systems is joined upon entering the pressure vessel. J ointure is accomplished in a common chamber causing high coolant flow velocities at low static pressures. If a pipe ruptures in one of the primary fluid flow systems, the low pressure in the common chamber minimizes leakage from the intact flow systems. This allows continuation of coolant flow through the nuclear core for a sufiicient length of time to eifectively eliminate the possibility of thermal damage.
  • NUCLEAR REACTOR CORE COOLING ARRANGEMENT Filed Sept. 13, 1972 5 Sheets-Sheet 1 April 16, 1974 A. H. REDDING I NUCLEAR REACTOR CORE COOLING ARRANGEMENT 5 Sheets-Shoot 2 Filed Sept. 13, 1972 OIVF April 16, 1974 I H REDDlNG TQZLGIS NUCLEAR REACTOR CORE COOLING ARRANGEMENT 5 Sheets-Sheet 3 Filed Sept. 13. 1972 new.
  • NUCLEAR REACTOR CORE COOLING ARRANGEMENT 5 Shbets-Sheot 4 4 6 8 10 I2 I4 I6 l8 T I ME (S ECONDS) A ril 16, 1974 A. H. REDDING NUCLEAR REACTOR CORE COOLING ARRANGEMENT 5 Shasta-Sheet 5 Filed Sept. 13.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Structures Of Non-Positive Displacement Pumps (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)

Abstract

D R A W I N G
A CORE COOLING SYSTEM FOR A NUCLEAR REACTOR HAVING A PLURALITY OF PRIMARY FLUID FLOW SYSTEMS. THE REACTOR COOLANT FLOW FROM THE PRIMARY SYSTEMS IS JOINED UPON ENTERING THE PRESSURE VESSEL. JOINTURE IS ACCOMPLISHED IN A COMMON CHAMBER CAUSING HIGH COOLANT FLOW VELOCITIES AT LOW STATIC PRESSURES. IF A PIPE RUPTURES IN ONE OF THE PRIMARY FLUID FLOW SYSTEMS, THE LOW PRESSURE IN THE COMMON CHAMBER MINIMIZES LEAKAGE FROM THE INTACT FLOW SYSTEMS. THIS ALLOWS CONTINUATION OF COLLANT FLOW THROUGH THE NUCLEAR CORE FOR A SUFFICIENT LENGTH OF TIE TO EFFECTIVELY ELIMINATE THE POSSIBILITY OF THERMAL DAMAGE.

Description

DEFENSIVE PUBLICATION UNITED STATES PATENT OFFICE Published at the request of the applicant or owner in accordance with the Notice of Dec. 16, 1969, 869 (LG. 687. The abstracts 0|. Defensive Publication applications are identified by distinctly numbered series and are arranged chronologically. The heading of each abstract indicates the number of pages of specification, including claims and sheets of drawings contained in the application as originally filed. The tiles 0! these applications are available to the public for inspection and reproduction may he purchased for 30 cents a sheet.
Defensive Publication applications have not been examined as to the merits of alleged invention. The Patent Ofllce makes no assertion as to the novelty of the disclosed subject matter.
PUBLISHED APRIL 16, 197% 921 O.Gr. 867
T921,015 NUCLEAR REACTOR CORE COOLING ARRANGEMENT Arnold H. Redding, Export, Pa., assignor to Westinghouse Electric Corporation, Pittsburgh, Pa. Filed Sept. 13, 1972, Ser. No. 288,610 Int. Cl. G21c 15/18, 15/24 US. Cl. 176--38 5 Sheets Drawing. 15 Pages Specification A core cooling system for a nuclear reactor having a plurality of primary fluid flow systems. The reactor coolant flow from the primary systems is joined upon entering the pressure vessel. J ointure is accomplished in a common chamber causing high coolant flow velocities at low static pressures. If a pipe ruptures in one of the primary fluid flow systems, the low pressure in the common chamber minimizes leakage from the intact flow systems. This allows continuation of coolant flow through the nuclear core for a sufiicient length of time to eifectively eliminate the possibility of thermal damage.
April 16, 1974 A. H. REDDING I I T921,015
NUCLEAR REACTOR CORE COOLING ARRANGEMENT Filed Sept. 13, 1972 5 Sheets-Sheet 1 April 16, 1974 A. H. REDDING I NUCLEAR REACTOR CORE COOLING ARRANGEMENT 5 Sheets-Shoot 2 Filed Sept. 13, 1972 OIVF April 16, 1974 I H REDDlNG TQZLGIS NUCLEAR REACTOR CORE COOLING ARRANGEMENT 5 Sheets-Sheet 3 Filed Sept. 13. 1972 new.
A ril 16, 1974 Filed Sept. 13. 1972 PERCENT FLOW IOO A. H. REDDING T921,015
NUCLEAR REACTOR CORE COOLING ARRANGEMENT 5 Shbets-Sheot 4 4 6 8 10 I2 I4 I6 l8 T I ME (S ECONDS) A ril 16, 1974 A. H. REDDING NUCLEAR REACTOR CORE COOLING ARRANGEMENT 5 Shasta-Sheet 5 Filed Sept. 13. 1972 BOILING TEMPERATURE OF LIQUID SODIUM PEAK TEMPERATURE OF CLADDING A 5 G F E R U T A R E w G E m R D m D M m PL E SC W 6 mm mm H w %A AL R E F A Ho FAILURE TEMPERATURE OF FUEL, ELEMENT, CLADDING IOOO TIME (SECONDS) B G F 6 M D MD DA DL F W WW I OE D O L R S %W m wm U AE Q ER U I UEW FG T F 0 AM N O I REE ED ETG. E D P A TL E E w AC T V A R A R KT E N A0 M TM P E E a G R N wL M m% FF O O O m m EL mmPEmmaEmP 0 WWW O O m m IOOO TIME (SECONDS?
US921015D 1972-09-13 1972-09-13 Nuclear reactor corii cooling arrangement Pending UST921015I4 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US28861072A 1972-09-13 1972-09-13

Publications (1)

Publication Number Publication Date
UST921015I4 true UST921015I4 (en) 1974-04-16

Family

ID=23107861

Family Applications (2)

Application Number Title Priority Date Filing Date
US921015D Pending UST921015I4 (en) 1972-09-13 1972-09-13 Nuclear reactor corii cooling arrangement
US05/550,905 Expired - Lifetime US4080252A (en) 1972-09-13 1975-02-18 Nuclear reactor core cooling arrangement

Family Applications After (1)

Application Number Title Priority Date Filing Date
US05/550,905 Expired - Lifetime US4080252A (en) 1972-09-13 1975-02-18 Nuclear reactor core cooling arrangement

Country Status (5)

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US (2) UST921015I4 (en)
JP (1) JPS5215757B2 (en)
DE (1) DE2345418A1 (en)
FR (1) FR2209173B1 (en)
GB (1) GB1417638A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107180659B (en) * 2017-05-09 2023-12-15 中广核研究院有限公司 Variable resistance type pipeline flow speed limiting device

Families Citing this family (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS585400B2 (en) * 1975-09-19 1983-01-31 株式会社日立製作所 Heat retention device for equipment or piping
GB2369236B (en) * 1980-02-22 2002-09-18 Rolls Royce & Associates Ltd Reactor vessel for a nuclear power generating system
US4412969A (en) * 1982-03-09 1983-11-01 Tilbrook Roger W Combination pipe rupture mitigator and in-vessel core catcher
US5267285A (en) * 1992-06-24 1993-11-30 Westinghouse Electric Corp. Apparatus for suppressing formation of vortices in the coolant fluid of a nuclear reactor and associated method
US7245689B2 (en) * 2003-06-18 2007-07-17 Mitsubishi Heavy Industries, Ltd Nuclear reactor internal structure
JP4786616B2 (en) * 2007-08-31 2011-10-05 三菱重工業株式会社 Reactor
CN105717545B (en) * 2016-02-22 2018-05-18 田志恒 It whether there is the device of liquid metal in a kind of monitoring pipeline
CN113432831B (en) * 2021-06-11 2022-04-05 西安交通大学 Integrated experimental device and experimental method for vortex entrainment phenomenon research

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3123533A (en) * 1964-03-03 Pressure relief device for neutronic reactors
NL126735C (en) * 1961-01-26
CH460536A (en) * 1965-07-30 1968-07-31 Gen Electric Pump device with a jet pump
US3621926A (en) * 1968-02-13 1971-11-23 Gen Electric Nuclear reactor coolant recirculation system
US3623948A (en) * 1968-04-25 1971-11-30 Babcock & Wilcox Co Pressurized-water nuclear reactor
JPS5147864B2 (en) * 1972-06-02 1976-12-17

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107180659B (en) * 2017-05-09 2023-12-15 中广核研究院有限公司 Variable resistance type pipeline flow speed limiting device

Also Published As

Publication number Publication date
US4080252A (en) 1978-03-21
FR2209173B1 (en) 1976-11-19
JPS5215757B2 (en) 1977-05-02
JPS4968199A (en) 1974-07-02
FR2209173A1 (en) 1974-06-28
DE2345418A1 (en) 1974-03-21
GB1417638A (en) 1975-12-10

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