Published January 1984 | Version v1
Report Open

Assessment of problems associated with tritium containment

Description

Preventing tritium leakage across a large heat transfer area at high temperature is one of the most difficult problems associated with a D-T fusion reactor design. One of the most efficient methods to reduce the mobility of tritium is to convert it to tritiated water. Most solid breeder systems use a purge gas and assume tritium will be oxidized into the water form. For 17 Li-83Pb system, a double-walled steam generator is used. Tritium is assumed to be oxidized across the gap in between the two walls. However, if tritium cannot be oxidized efficiently, the tritium containment problem can become critical

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE84006441.

Files

15071172.pdf

Files (58.8 kB)

Name Size Download all
md5:4cd17ea082d75b286360442f16dad9ea
58.8 kB Preview Download

Additional details

Publishing Information

Imprint Pagination
4 p.
Report number
CONF-840614--26

Conference

Title
Annual meeting of the American Nuclear Society.
Dates
3-8 Jun 1984.
Place
New Orleans, LA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
15071172
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAINMENT; DIFFUSION; LEAD ALLOYS; LITHIUM ALLOYS; OXIDATION; PERMEABILITY; STEAM GENERATORS; TRITIUM
Descriptors DEC
ALLOYS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; BOILERS; CHEMICAL REACTIONS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; VAPOR GENERATORS; YEARS LIVING RADIOISOTOPES