skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Midterm Summary of Japan-US Fusion Cooperation Program TITAN

Abstract

Japan-US cooperation program TITAN (Tritium, Irradiation and Thermofluid for America and Nippon) started in April 2007 as 6-year project. This is the summary report at the midterm of the project. Historical overview of the Japan-US cooperation programs and direction of the TITAN project in its second half are presented in addition to the technical highlights. Blankets are component systems whose principal functions are extraction of heat and tritium. Thus it is crucial to clarify the potentiality for controlling heat and tritium flow throughout the first wall, blanket and out-of-vessel recovery systems. The TITAN project continues the JUPITER-II activity but extends its scope including the first wall and the recovery systems with the title of 'Tritium and thermofluid control for magnetic and inertial confinement systems'. The objective of the program is to clarify the mechanisms of tritium and heat transfer throughout the first-wall, the blanket and the heat/tritium recovery systems under specific conditions to fusion such as irradiation, high heat flux, circulation and high magnetic fields. Based on integrated models, the breeding, transfer, inventory of tritium and heat extraction properties will be evaluated for some representative liquid breeder blankets and the necessary database will be obtained for focused research in themore » future.« less

Authors:
 [1];  [2];  [3];  [3];  [3]
  1. National Institute for Fusion Science, Toki, Japan
  2. University of California, San Diego
  3. ORNL
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); High Flux Isotope Reactor
Sponsoring Org.:
USDOE Office of Science (SC)
OSTI Identifier:
1023874
DOE Contract Number:
DE-AC05-00OR22725
Resource Type:
Journal Article
Resource Relation:
Journal Name: Fusion Science and Technology; Journal Volume: 60; Journal Issue: 1
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; BREEDING; FIRST WALL; HEAT EXTRACTION; HEAT FLUX; HEAT TRANSFER; INERTIAL CONFINEMENT; IRRADIATION; MAGNETIC FIELDS; TRITIUM

Citation Formats

Muroga, Takeo, Sze, Dai-Kai, Sokolov, Mikhail, Katoh, Yutai, and Stoller, Roger E. Midterm Summary of Japan-US Fusion Cooperation Program TITAN. United States: N. p., 2011. Web.
Muroga, Takeo, Sze, Dai-Kai, Sokolov, Mikhail, Katoh, Yutai, & Stoller, Roger E. Midterm Summary of Japan-US Fusion Cooperation Program TITAN. United States.
Muroga, Takeo, Sze, Dai-Kai, Sokolov, Mikhail, Katoh, Yutai, and Stoller, Roger E. Sat . "Midterm Summary of Japan-US Fusion Cooperation Program TITAN". United States. doi:.
@article{osti_1023874,
title = {Midterm Summary of Japan-US Fusion Cooperation Program TITAN},
author = {Muroga, Takeo and Sze, Dai-Kai and Sokolov, Mikhail and Katoh, Yutai and Stoller, Roger E},
abstractNote = {Japan-US cooperation program TITAN (Tritium, Irradiation and Thermofluid for America and Nippon) started in April 2007 as 6-year project. This is the summary report at the midterm of the project. Historical overview of the Japan-US cooperation programs and direction of the TITAN project in its second half are presented in addition to the technical highlights. Blankets are component systems whose principal functions are extraction of heat and tritium. Thus it is crucial to clarify the potentiality for controlling heat and tritium flow throughout the first wall, blanket and out-of-vessel recovery systems. The TITAN project continues the JUPITER-II activity but extends its scope including the first wall and the recovery systems with the title of 'Tritium and thermofluid control for magnetic and inertial confinement systems'. The objective of the program is to clarify the mechanisms of tritium and heat transfer throughout the first-wall, the blanket and the heat/tritium recovery systems under specific conditions to fusion such as irradiation, high heat flux, circulation and high magnetic fields. Based on integrated models, the breeding, transfer, inventory of tritium and heat extraction properties will be evaluated for some representative liquid breeder blankets and the necessary database will be obtained for focused research in the future.},
doi = {},
journal = {Fusion Science and Technology},
number = 1,
volume = 60,
place = {United States},
year = {Sat Jan 01 00:00:00 EST 2011},
month = {Sat Jan 01 00:00:00 EST 2011}
}