Author: Charles H. SkinnerPublisher:
ISBN:
Category : Tokamaks
Languages : en
Pages : 4
Book Description
Tritium Removal by CO(sub 2) Laser Heating
Author: Charles H. SkinnerPublisher:
ISBN:
Category : Tokamaks
Languages : en
Pages : 4
Book Description
Tritium Removal by Laser Heating and Its Application to Tokamaks
Author: Charles H. SkinnerPublisher:
ISBN:
Category : Lasers
Languages : en
Pages : 5
Book Description
Tritium Removal by Laser Heating and Its Application to Tokamaks
Author: Charles H. SkinnerPublisher:
ISBN:
Category : Lasers
Languages : en
Pages : 5
Book Description
Tritium Removal from Codeposits on Carbon Tiles by a Scanning Laser
Author: Charles H. SkinnerPublisher:
ISBN:
Category : Tokamaks
Languages : en
Pages : 10
Book Description
Tritium Removal from Contaminated Water Via Infrared Laser Multiple-photon Dissociation
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Isotope separation by means of infrared-laser multiple-photon dissociation offers an efficient way to recover tritium from contaminated light or heavy water found in fission and fusion reactors. For tritium recovery from heavy water, chemical exchange of tritium into deuterated chloroform is followed by selective laser dissociation of tritiated chloroform and removal of the tritiated photoproduct, TCl. The single-step separation factor is at least 2700 and is probably greater than 5000. Here we present a description of the tritium recovery process, along with recent accomplishments in photochemical studies and engineering analysis of a recovery system.
Tritium Removal from JET and TFTR Tiles by a Scanning Laser
Author: Charles H. SkinnerPublisher:
ISBN:
Category : Lasers
Languages : en
Pages : 5
Book Description
Energy Research Abstracts
Author: Hot Cell Studies of Tritium Removal from and Dissolution of an Irradiated Thoria Fuel
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Tritium removal and dissolution studies on an irradiated thoria-based fuel were conducted in the High Level Caves at the Savannah River Laboratory (SRL). The objectives of these studies were to define the effects of key process-related parameters on tritium evolution and subsequent dissolution. The test program at SRL determined the effects on tritium removal of particle size, heating temperature, oxidation, and agitation. ThO2/UO2 (95%/5%) fuel from the Elk River Reactor, irradiated to about 12,000 MWD/MTHM and cooled for about 12 years, was used in the tests. The thoria/urania fuel pellets were separated from the stainless steel cladding and were divided into size fractions to determine the particle-size distribution resulting from the decladding process. In the tritium removal tests, the effect of heating several different particle-size fractions was studied at temperatures ranging from 600 to 1000°C in the presence of air for 10 to 30 hours. Each of the roasted samples (about 100 grams) was subsequently dissolved in refluxing Thorex reagent (13M HNO3, 0.05M HF, and 0.1M Al(NO3)3) to determine the residual tritium. The amount of insoluble residue remaining after the dissolution was determined and characterized.
Author: 
Author: