UTIAS tritium exposure facility for fusion materials studies.
Read Online

UTIAS tritium exposure facility for fusion materials studies.

  • 950 Want to read
  • ·
  • 14 Currently reading

Published by Ontario Hydro in Mississauga, Ontario .
Written in English


  • Canadian Fusion Fuels Technology Project.,
  • University of Toronto. -- Institute for Aerospace Studies. -- Low-Level Tritium Research Facility,
  • Thermonuclear fuels -- Research -- Ontario -- Toronto.,
  • Tritium -- Research -- Ontario -- Toronto.

Book details:

Edition Notes

SeriesReport / Canadian Fusion Fuels Technology Project, Report (Canadian Fusion Fuels Technology Project) -- no. CFFTP-G-8906.
ContributionsHaasz, A. A. 1943-, Youle, I. S.
LC ClassificationsQC789.2.C22 U564 1989
The Physical Object
Paginationiv, 12, [6] leaves :
Number of Pages12
ID Numbers
Open LibraryOL14935491M

Download UTIAS tritium exposure facility for fusion materials studies.


applicability of the materials for their fusion reactor roles. The tasks carried out in the frameworks of this project are as follows: Develop and apply methods for tritium total amount, spatial distribution and chemical forms measurements in tritium containing materials;. The International Fusion Materials Irradiation Facility, also known as IFMIF, is a projected material testing facility in which candidate materials for the use in an energy producing fusion reactor can be fully will be an accelerator-driven neutron source producing a high intensity fast neutron flux with a spectrum similar to that expected at the first wall of a fusion reactor.   Tritium Aging Studies of Metal Hydrides for NNSA Applications Development of Predictive Models of Tritium & 3He in Metals and Hydrides Tritium Aging Studies of Storage and Separation Materials Metal Hydride Investigations •Pd • Pd (thick film) on supports (kieselguhr, alumina) • La-Ni(5-x)-Al(x) alloys – various comps. 0>x> • La-Ni. SUITABILITY AND FEASIBILITY OF THE INTERNATIONAL FUSION MATERIALS IRRADIATION FACILITY (IFMIF) FOR FUSION MATERIALS STUDIES A. MÖSLANG, K. EHRLICH EURATOM-FZK Association Forschungszentrum Karlsruhe, IMF-I, P.O. Box , D Karlsruhe, Germany T. E. SHANNON*, M. J. RENNICH The Oak Ridge National Laboratory, Oak Ridge, TN, USA.

The Safety and Tritium Applied Research (STAR) facility has been established to provide a laboratory infrastructure for the fusion community to study tritium science associated with the. 1. Introduction. This paper presents a preliminary evaluation of the materials challenges presented by the conceptual design for a Fusion Nuclear Science Facility (FNSF) to bridge the development gap between ITER and a demonstration power plant (DEMO). Here the FNSF specifically denotes the concept that has been studied in the recent Fusion Energy System Studies (FESS) supported by the US Cited by: 9. The facility’s key aim is to provide intense high energy neutrons with a sufficient irradiation volume to enable the realistic testing (in terms of intensity and duration) of candidate materials and components for use in a demonstration reactor plant and in future fusion plants. Tritium rods sent to Savannah River Site. The U.S. Department of Energy (DOE) has confirmed that the Savannah River Site (SRS) in South Carolina has received it first shipment of nuclear rods containing tritium, a radioactive gas that is a key ingredient in nuclear weapons.

• Restricted to a facility total tritium inventory of less than gram (15, Ci), to remain below DOE Hazard Category 3 threshold! less than Hazard Category 3 Nuclear Facility – Current tritium inventory is ~ gram (~ Ci) • Specializes in: – Tritium (fusion fuel)File Size: 3MB. International Fusion Materials Irradiation Facility (IFMIF) Design Activity IFMIF is a design project for an intense neutron source for fusion materials studies at high radiation damage levels. The neutrons will be generated by a Li(d,xn) stripping reaction, bombarding liquid lithium with deuterium ions at . Journal of Fusion Energy, Vol. 19, No. 1, March (q ) Review of the Fusion Materials Research Program Samuel D. Harkness,1 Charles C. Baker,2 Mohamed A. Abdou,3 John W. Davis, 4 William Hogan, 5 Gerald L. Kulcinski,6 Michael Mauel,7 Carl McHargue,8 Robert Odette,9 David A. Petti,10 Paul Shewmon,11 and Stewart J. Zweben12 This report presents the results and recommendations of the Author: Samuel D. Harkness, Charles C. Baker, Mohamed A. Abdou, John W. Davis, William Hogan, Gerald L. Kulc. – Tritium permeation barrier materials can reduce the release to the environment, however, the performance of tritium permeation barrier materials (e.g. ceramics) is unknown under fusion nuclear environments due to strong radiation field and displacement damage.