FR2365184A1 - Procede d'accroissement de la reactivite dans des reacteurs nucleaires thermiques et epithermiques par l'utilisation d'elements lourds - Google Patents

Procede d'accroissement de la reactivite dans des reacteurs nucleaires thermiques et epithermiques par l'utilisation d'elements lourds

Info

Publication number
FR2365184A1
FR2365184A1 FR7628336A FR7628336A FR2365184A1 FR 2365184 A1 FR2365184 A1 FR 2365184A1 FR 7628336 A FR7628336 A FR 7628336A FR 7628336 A FR7628336 A FR 7628336A FR 2365184 A1 FR2365184 A1 FR 2365184A1
Authority
FR
France
Prior art keywords
epithermal
thermal
reactors
nuclear reactors
heavy elements
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.)
Granted
Application number
FR7628336A
Other languages
English (en)
Other versions
FR2365184B1 (fr
Inventor
Alvin Radkowsky
Ji-Peng Chien
Chao-Yie Yang
Horng-Ming Hsieh
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.)
Institute of Nuclear Energy Research
Original Assignee
Institute of Nuclear Energy Research
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 Institute of Nuclear Energy Research filed Critical Institute of Nuclear Energy Research
Publication of FR2365184A1 publication Critical patent/FR2365184A1/fr
Application granted granted Critical
Publication of FR2365184B1 publication Critical patent/FR2365184B1/fr
Granted legal-status Critical Current

Links

Classifications

    • 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
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/04Thermal reactors ; Epithermal reactors
    • 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
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/326Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
    • G21C3/328Relative disposition of the elements in the bundle lattice
    • 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
    • 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
    • Y10TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10STECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S376/00Induced nuclear reactions: processes, systems, and elements
    • Y10S376/90Particular material or material shapes for fission reactors
    • Y10S376/904Moderator, reflector, or coolant materials

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Particle Accelerators (AREA)
  • Production Of Liquid Hydrocarbon Mixture For Refining Petroleum (AREA)
  • Catalysts (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

Procédé d'accroissement de la réactiyité dans des réacteurs nucléaires thermiques et épithermiques par l'utilisation d'éléments lourds. Selon la présente invention, un accroissement de la réactivité dans des réacteurs thermiques et épithermiques peut être obtenu par l'utilisation d'éléments lourds disposés en des emplacements choisis dans les réacteurs et permettant d'obtenir, notamment, des réductions de coût de fonctionnement par réduction des quantités d'eau lourde nécessaires dans les réacteurs à modérateur à base d'eau lourde et par la réduction de l'enrichissement nécessaire dans les réacteurs à eau légère. Application à des réacteurs nucléaires thermiques et épithermiques.
FR7628336A 1976-09-15 1976-09-21 Procede d'accroissement de la reactivite dans des reacteurs nucleaires thermiques et epithermiques par l'utilisation d'elements lourds Granted FR2365184A1 (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US05/723,482 US4123328A (en) 1976-09-15 1976-09-15 Utilization of heavy elements in thermal and epithermal reactors

Publications (2)

Publication Number Publication Date
FR2365184A1 true FR2365184A1 (fr) 1978-04-14
FR2365184B1 FR2365184B1 (fr) 1979-01-12

Family

ID=24906458

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7628336A Granted FR2365184A1 (fr) 1976-09-15 1976-09-21 Procede d'accroissement de la reactivite dans des reacteurs nucleaires thermiques et epithermiques par l'utilisation d'elements lourds

Country Status (5)

Country Link
US (1) US4123328A (fr)
CA (1) CA1081375A (fr)
DE (1) DE2643092C3 (fr)
FR (1) FR2365184A1 (fr)
GB (1) GB1553980A (fr)

Families Citing this family (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4881247A (en) * 1982-03-25 1989-11-14 Westinghouse Electric Corp. Measuring nuclear fuel burnup
US4495136A (en) * 1982-05-11 1985-01-22 Westinghouse Electric Corp. Maximum power capability blanket for nuclear reactors
US4526741A (en) * 1983-06-10 1985-07-02 The United States Of America As Represented By The United States Department Of Energy Fuel assembly for the production of tritium in light water reactors
US4699756A (en) * 1985-08-08 1987-10-13 Westinghouse Electric Corp. Full length control rod employing axially inhomogeneous absorber materials for zero reactivity redistribution factor
US4818478A (en) * 1987-12-07 1989-04-04 Westinghouse Electric Corp. BWR fuel assembly mini-bundle having interior fuel rods of reduced diameter
US5442668A (en) * 1993-06-03 1995-08-15 Massachusetts Institute Of Technology Passive pressure tube light water cooled and moderated reactor
US20050069075A1 (en) * 2003-06-04 2005-03-31 D.B.I. Century Fuels And Aerospace Services, Inc. Reactor tray vertical geometry with vitrified waste control
EP2339589A1 (fr) * 2009-12-25 2011-06-29 Global Nuclear Fuel-Japan Co., Ltd. Assembagle de combustible
KR101533868B1 (ko) * 2012-07-24 2015-07-06 한국원자력연구원 중수로 핵연료 다발의 핵연료봉 구조
KR101744156B1 (ko) 2016-02-29 2017-06-07 (주)뉴클리어엔지니어링 개량형 중수로용 핵연료 다발

Family Cites Families (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2837477A (en) * 1945-02-16 1958-06-03 Fermi Enrico Chain reacting system
US2830944A (en) * 1945-08-28 1958-04-15 Eugene P Wigner Neutronic reactor
US2832733A (en) * 1946-04-23 1958-04-29 Szilard Leo Heavy water moderated neutronic reactor
US3048534A (en) * 1952-03-28 1962-08-07 Tonks Lewi Control means for neutronic reactors
GB948909A (en) * 1959-06-19 1964-02-05 Rolls Royce Improvements in or relating to nuclear reactors
NL279220A (fr) * 1962-06-04
US3255083A (en) * 1962-12-26 1966-06-07 Carl N Klahr Method of flux separation in nuclear reactors and structure therefor
US3351532A (en) * 1965-09-20 1967-11-07 Jr Harry F Raab Seed-blanket converter-recycle breeder reactor
US3523869A (en) * 1967-10-03 1970-08-11 Byk Gulden Lomberg Chem Fab Booster-source rods in heavy water moderated reactor
US3519535A (en) * 1968-01-24 1970-07-07 Westinghouse Electric Corp Nuclear fuel assembly with plural independent control elements and system therefor
US3849248A (en) * 1969-02-14 1974-11-19 Gen Electric Samarium compensation for nuclear reactor fuel

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
NEANT *

Also Published As

Publication number Publication date
GB1553980A (en) 1979-10-17
US4123328A (en) 1978-10-31
FR2365184B1 (fr) 1979-01-12
DE2643092B2 (de) 1980-05-08
DE2643092C3 (de) 1981-02-05
DE2643092A1 (de) 1978-04-06
CA1081375A (fr) 1980-07-08

Similar Documents

Publication Publication Date Title
FR2365184A1 (fr) Procede d'accroissement de la reactivite dans des reacteurs nucleaires thermiques et epithermiques par l'utilisation d'elements lourds
JPS53131835A (en) Reflecting objective lens
JPS5322495A (en) Automatic analyzer
JPS5436193A (en) Photo electric converter and its manufacture
JPS5263588A (en) Neutraon source for nuclear reactor
JPS5357388A (en) Nuclear reactor
JPS52130338A (en) Focusing point detectig means
JPS5327799A (en) Treating system for gas waste in light water type reactor
JPS53115494A (en) Fuel particle distribution measurement of nuclear fuel compact
JPS51148442A (en) Mode-distribution analytical method
JPS5420291A (en) Fast breeder
JPS5263594A (en) Method of measuring of degree of burn-up in nuclear reactor fuel
JPS5261697A (en) Fuel assembly for pressure tube type heavy water nuclear reactor
CH538200A (fr) Procédé de réglage de la puissance d'un groupe de piles à combustible, appareillage pour sa mise en oeuvre et application de ce procédé
JPS5293892A (en) Fuel assembly for reactor
JPS52112094A (en) Nuclear reactor
JPS5287595A (en) Fuel assembly of reactor
JPS51140895A (en) Process for producing hydrogen from water
JPS5352893A (en) Measuring method and device for reactivity of reactor fuel assembly
JPS5223962A (en) Process for representing an image by means of optical distance convers ion, and device therefore
JPS5362094A (en) Output distribution controlling method and device in reactor
JPS5352894A (en) Degree of burn-up measuring method in fuel assembly
JPS5331091A (en) Nuclear reactor
JPS51140559A (en) Impurities diffusing to iii-v group compound semi-conductor base plate
JPS5351392A (en) Method of supervising atomic pile output distribution

Legal Events

Date Code Title Description
TP Transmission of property
ST Notification of lapse