GB1100298A - Improved system for eliminating thermal shocks in nuclear reactors - Google Patents

Improved system for eliminating thermal shocks in nuclear reactors

Info

Publication number
GB1100298A
GB1100298A GB187/66A GB18766A GB1100298A GB 1100298 A GB1100298 A GB 1100298A GB 187/66 A GB187/66 A GB 187/66A GB 18766 A GB18766 A GB 18766A GB 1100298 A GB1100298 A GB 1100298A
Authority
GB
United Kingdom
Prior art keywords
reactor
nuclear reactors
thermal
thermal shocks
jan
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
GB187/66A
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.)
Skoda np
Original Assignee
Skoda np
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 Skoda np filed Critical Skoda np
Publication of GB1100298A publication Critical patent/GB1100298A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • 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)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

1,100,298. Reactors. SKODA NARODNI PODNIK. 3 Jan., 1966 [3 Jan., 1965], No. 187/66. Heading G6C. In a system for eliminating thermal shocks in nuclear reactors, a thermal accumulator in the form of a grid or grating is permanently installed inside the reactor after the active zone of the reactor as considered in the direction of flow of the cooling medium. In the embodiment described, a metal grid is disposed either in the exit chamber of the reactor or in the connecting conduit between the reactor and a steam generator. A thermal shock is normally obtained when a reactor having low thermal inertia is adjusted, as by means of control rods, in particular as a result of an emergency shut-down, and the effect of this system is to delay the consequent abrupt temperature change of the cooling medium as it leaves the reactor.
GB187/66A 1965-01-03 1966-01-03 Improved system for eliminating thermal shocks in nuclear reactors Expired GB1100298A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CS365 1965-01-03

Publications (1)

Publication Number Publication Date
GB1100298A true GB1100298A (en) 1968-01-24

Family

ID=5331412

Family Applications (1)

Application Number Title Priority Date Filing Date
GB187/66A Expired GB1100298A (en) 1965-01-03 1966-01-03 Improved system for eliminating thermal shocks in nuclear reactors

Country Status (1)

Country Link
GB (1) GB1100298A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4022655A (en) * 1973-12-12 1977-05-10 Commissariat A L'energie Atomique Device for limiting accidental pressure overloads in a nuclear reactor confinement structure

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4022655A (en) * 1973-12-12 1977-05-10 Commissariat A L'energie Atomique Device for limiting accidental pressure overloads in a nuclear reactor confinement structure

Similar Documents

Publication Publication Date Title
GB1135826A (en) A pressure suppression system for nuclear reactor plants
GB887299A (en) Improvements in or relating to heat exchangers
GB1100298A (en) Improved system for eliminating thermal shocks in nuclear reactors
GB1166305A (en) Improvements in or relating to Vapor Generators.
GB1061848A (en) Control of a forced-flow,once-through boiler
GB1043500A (en) Improvements relating to nuclear reactors
GB1043271A (en) Control system
ES274107A1 (en) Monotube boiler feedwater and steam temperature control
GB1012615A (en) Improvements in and relating to nuclear reactor plants
GB930638A (en) Nuclear reactor fuel element channels
GB1161654A (en) Process for Sodium Heated Modules
FR1458624A (en) Improved method of pressure regulation and pressurizer including application
FR1274240A (en) Plant for the production of steam by the heat of an atomic cell
GB1176646A (en) Improvements in or relating to Nuclear Reactors.
GB1002347A (en) Stability improvement for nuclear reactor automatic control system
GB1041714A (en) Improvements in and relating to nuclear reactors
ES251740A1 (en) Improvements in or relating to plants including nuclear reactors
Gurwell et al. FABRICATION OF SWELLING RESISTANT URANIUM METAL FUEL RODS FOR THE CANADIAN WHITESHELL REACTOR, WR-1.
FR2361604A1 (en) Steam generator, partic. for nuclear reactor - uses mean liq. sodium temp. in controlling operating conditions to minimise thermal shock
GB911132A (en) Stabilizing system for nuclear reactors, particularly those operating with boiling water
CA669883A (en) Control of the cooling water system of condensers, for example in a steam turbine plant
GB1173450A (en) Improvements in or relating to Neutron Generators
GB1292940A (en) A thermostatic device particularly for controlling fluid flow in a nuclear fuel assembly
GB1041475A (en) Improvements in and relating to vapour generators
GB1131547A (en) Controlling the power of a nuclear reactor plant comprising steam generators