[go: up one dir, main page]

Clinton et al., 1976 - Google Patents

Recent Experimental Engineering Studies Related to Controlled Thermonuclear Reactors

Clinton et al., 1976

View PDF
Document ID
18032296039268790880
Author
Clinton S
Fisher P
Smith F
Talbot J
Watson J
Publication year
Publication venue
Radiation Effects and Tritium Technology for Fusion Reactors

External Links

Snippet

Recent experimental engineering studies at ORNL on tritium handling systems for controlled thermonuclear reactors (CTRs) include investigations of:(l) metal sorbers for removal of tritium from liquid metals,(2) tritium solubility in lithium-bismuth (Li-Bi),(3) oxidation of …
Continue reading at www.osti.gov (PDF) (other versions)

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/02Devices or arrangements for monitoring coolant or moderator
    • G21C17/04Detecting burst slugs
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01NINVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N1/00Sampling; Preparing specimens for investigation
    • G01N1/28Preparing specimens for investigation including physical details of (bio-)chemical methods covered elsewhere, e.g. G01N33/50, C12Q
    • G01N1/40Concentrating samples

Similar Documents

Publication Publication Date Title
US5208165A (en) Method for testing the soluble contents of nuclear reactor coolant water
Oishi et al. Tritium recovery from molten LiF-BeF2 salt
Cathers Uranium recovery for spent fuel by dissolution in fused salt and fluorination
Clinton et al. Recent Experimental Engineering Studies Related to Controlled Thermonuclear Reactors
Akhtar et al. Separation and analysis of various forms of hydrogen by adsorption and gas chromatography
Trenin et al. Full-scale experimental studies of the various type mass exchange packings by water distillation
Clinton et al. The solubility of tritium in yttrium at temperatures from 250 to 400° C
Hemmerich et al. Gas recovery system for the first JET tritium experiment
Talbot et al. Recovery of tritium from molten lithium using yttrium getters
Talbot et al. Liquid lithium blanket processing studies
Yajima et al. The determination of water by gas chromatography
Bokwa et al. Handling high specific activity tritium
Morimoto et al. Design and operations at the national tritium labelling facility
Kudo et al. Preparation of pure tritium for a liquid D2/T2 target of muon-catalyzed fusion experiments
US3179487A (en) Process for removing radioactive impurities from gases
Maroni Surface phenomena at fluid-structure interfaces and their effects on the migration of tritium in controlled thermonuclear reactors
Schilling et al. The solubility of thorium in liquid bismuth
Venkataramani et al. Poisoning and saturation of St 737 getter alloy in the conversion of isotopic waters to isotopic hydrogen
Chabot et al. Physico-chemical investigations in relation with the tritium circuit in fusion reactors
Kunz Separation techniques for reactor-produced noble gases
Leudet et al. Balance and behavior of gaseous radionuclides released during initial PWR fuel reprocessing operations
Aratono et al. The diffusivities of fission-created or thermally-doped tritium in UO2
Thorogood et al. Adsorption of Oxygen and Nitrogen on Molecular Sieves.
Sakurai et al. Reactions of CH3I and C2H5I with NO2 on Zeolite 13X
Berven et al. Use of a cryogenic sampler to measure radioactive gas concentrations in the main off-gas system at a high-flux isotope reactor