Preliminary tritium safety analysis and problems with obtaining public consent to deuterium plasma experiments in the LHD

Fusion Science and Technology

Volumn 41, Issue 3 II, 2002, Pages 652-657

  Uda, T ^a   Tanahashi, S ^a   Nishimura, K ^a   Shinotsuka, K ^a   Motojima, O ^a  

^a NATIONAL INSTITUTE FOR FUSION SCIENCE   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; DEUTERIUM; ELECTRIC COILS; FUSION REACTIONS; GASES; NEUTRONS; PLASMA APPLICATIONS; WINDING;

TRITIUM SAFETY ANALYSIS;

TRITIUM;

EID: 0036565464     PISSN: 15361055     EISSN: None     Source Type: Journal    
DOI: 10.13182/fst02-a22668     Document Type: Conference Paper

References (10)

1. Progress summary of LHD engineering design and construction
2. Energy confinement and thermal transport characteristics of net current plasmas in the Large Helical Device
3. Development of a tritium cleanup system for a large helical device using nonvolatile getter materials
4. Development of tritium cleanup system for LHD
5. Age-dependent dose to members of the public from intake of radionuclides: Part 5 complication of ingestion inhalation dose coefficient report of ICRP
6. Overview of tritium: Characteristics, sources, and problems
7. Sources and effects of ionizing radiation
8. Hydrogen permeation characteristics of some austenitic and nickel-base alloys
9. Hydrogen permeation in stainless steel