NL245961A - - Google Patents

Info

Publication number
NL245961A
NL245961A NL245961DA NL245961A NL 245961 A NL245961 A NL 245961A NL 245961D A NL245961D A NL 245961DA NL 245961 A NL245961 A NL 245961A
Authority
NL
Netherlands
Prior art keywords
fuel
grids
stainless steel
steel
contain
Prior art date
Application number
Other languages
English (en)
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.)
Publication date
Publication of NL245961A publication Critical patent/NL245961A/xx

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/06Casings; Jackets
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/02Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect
    • G21C7/04Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect of burnable poisons
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C7/00Control of nuclear reaction
    • G21C7/06Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/22Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material, e.g. by adding neutron-absorbing material to the coolant
    • 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)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
  • Treatment Of Steel In Its Molten State (AREA)
NL245961D 1958-03-14 NL245961A (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US72140458A 1958-03-14 1958-03-14
US77765358 US3103476A (en) 1958-03-14 1958-12-02 Fuel element with burnable poison within the cladding

Publications (1)

Publication Number Publication Date
NL245961A true NL245961A (fr) 1900-01-01

Family

ID=40336525

Family Applications (1)

Application Number Title Priority Date Filing Date
NL245961D NL245961A (fr) 1958-03-14

Country Status (7)

Country Link
US (1) US3103476A (fr)
BE (1) BE585200A (fr)
CH (1) CH359491A (fr)
DE (1) DE1176766B (fr)
FR (1) FR1242102A (fr)
GB (2) GB913655A (fr)
NL (1) NL245961A (fr)

Families Citing this family (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3427222A (en) * 1965-10-15 1969-02-11 Westinghouse Electric Corp Nuclear fuel elements
US3432389A (en) * 1966-07-25 1969-03-11 Combustion Eng Core design for nuclear reactor
NO117432B (fr) * 1968-04-06 1969-08-11 Atomenergi Inst For
US3625821A (en) * 1968-06-26 1971-12-07 Westinghouse Electric Corp Fuel-element coating containing burnable poison
DE3128652A1 (de) * 1981-07-20 1983-02-03 Interatom Internationale Atomreaktorbau Gmbh, 5060 Bergisch Gladbach Huellkasten mit distanzhaltern fuer schnelle brutreaktoren
FR2520916B1 (fr) * 1982-02-03 1986-04-18 Fragema Framatome & Cogema Assemblage combustible a poison consommable
US4640813A (en) * 1984-09-26 1987-02-03 Westinghouse Electric Corp. Soluble burnable absorber rod for a nuclear reactor
US4717534A (en) * 1985-02-19 1988-01-05 Westinghouse Electric Corp. Nuclear fuel cladding containing a burnable absorber
US4695476A (en) * 1985-06-06 1987-09-22 Westinghouse Electric Corp. Process for coating the internal surface of zirconium tubes with neutron absorbers
US5241571A (en) * 1992-06-30 1993-08-31 Combustion Engineering, Inc. Corrosion resistant zirconium alloy absorber material
GB2318902B (en) * 1996-11-02 1998-09-23 British Nuclear Fuels Plc Neutron absorbing coating
US10546661B2 (en) * 2014-06-23 2020-01-28 Free Form Fibers, Llc Additive manufacturing technique for placing nuclear reactor fuel within fibers
CN105693524A (zh) * 2014-11-28 2016-06-22 浙江省化工研究院有限公司 一种硝基化合物的制备方法

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2843539A (en) * 1955-05-16 1958-07-15 North American Aviation Inc Samarium compensator method for nuclear reactor fuel
GB796989A (en) * 1956-02-06 1958-06-25 Gen Electric Improvements relating to neutronic reactor fuels
US2873242A (en) * 1956-06-29 1959-02-10 Treshow Michael Neutronic reactor system

Also Published As

Publication number Publication date
GB913655A (en) 1962-12-19
BE585200A (fr) 1960-04-01
FR1242102A (fr) 1960-09-23
CH359491A (fr) 1962-01-15
DE1176766B (de) 1964-08-27
GB931286A (en) 1963-07-17
US3103476A (en) 1963-09-10

Similar Documents

Publication Publication Date Title
Lane et al. Fluid fuel reactors: Molten salt reactors, aqueous homogeneous reactors, fluoride reactors, chloride reactors, liquid metal reactors and why liquid fission
US3745069A (en) Fuel assemblies containing uo2 and puo2-uo2 for water cooled nuclear reactors
US3235463A (en) Nuclear reactor
NL245961A (fr)
US3197376A (en) Epithermal thorium power-breeder nuclear reactor
Al-Zahrani et al. Neutronic performance of fully ceramic microencapsulated of uranium oxycarbide and uranium nitride composite fuel in SMR
Cahalan et al. Performance of metal and oxide fuels during accidents in a large liquid metal cooled reactor
Peng et al. Core neutronic characterization of a large molten‐salt cooled thorium‐based solid fuel fast reactor
US3687804A (en) Compact and safe nuclear reactor
US3253997A (en) Nuclear reactor and cooling and moderating arrangement therefor
Koch et al. Fast reactors
US3466225A (en) Pulsing nuclear reactor
Weinberg Power Reactors
Slater An Overview of the Potential of the CANDU Reactor as a Thermal Breeder
Zee et al. Development of core design and analyses technology for integral reactor
JPH05323072A (ja) 加圧水型原子炉用燃料集合体
Drbal Nuclear Power
Goldsmith IRRADIATION TESTING NEEDS AND FACILITIES FOR FAST REACTOR FUEL AND MATERIAL DEVELOPMENT.
Bobone Space-time distribution of fission-induced monoclinic to cubic transformation in zirconia during in-pile corrosion
Yoshimi et al. JOYO modification program for demonstration tests of FBR innovative technology development
Helmersson et al. Method of exchanging fuel in a nuclear reactor
Heaberlin et al. Design basis neutronics calculations for NRU-LOCA experiments
Kouts The development of breeder reactors in the United States
Simnad Highlights of 50 years of nuclear fuel development
Karsten Between science and technology: results and reflections on the status of fuel element development for fast reactors