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Tritium permeation through helium-heated steam generators of ceramic breeder blankets for DEMO

Abstract

The specifications of permeation barriers, tritium recovery process maintaining a very low tritium activity in the coolant, and control of the coolant chemistry, required the evaluation of the tritium losses through the steam generators and include the definition of its operating conditions by thermodynamic cycle calculations and its thermal-hydraulic design. For both tasks specific computer tools were developed. The obtained geometry, surface area, and temperature profiles along the heat exchanger tubes were then used to estimate the daily tritium permeation into the steam cycle. Steam oxidized Incoloy 800 austenitic stainless steel was identified as the best suited existing material; in nominal steady-state operation, the tritium escape into the steam cycle could be restricted to less than 10 Ci/d. Tritium permeation during temperature and pressure transients in the steam generator (destruction and possible self-healing of the permeation barrier) is identified to bear a large tritium release potential. Solutions are proposed. (from authors). 4 figs., 1 tab.
Publication Date:
Dec 31, 1994
Product Type:
Conference
Report Number:
CEA-CONF-12039; CONF-940664-
Reference Number:
SCA: 700450; 220600; PA: AIX-27:012496; EDB-96:042870; NTS-96:012626; SN: 96001540459
Resource Relation:
Conference: ISFNT-3: international symposium on fusion nuclear technology, Los Angeles, CA (United States), 27 Jun - 1 Jul 1994; Other Information: PBD: 1994
Subject:
70 PLASMA PHYSICS AND FUSION; 22 NUCLEAR REACTOR TECHNOLOGY; BREEDING BLANKETS; PERMEABILITY; TRITIUM; HELIUM COOLED REACTORS; INCOLOY 800; PRESSURE DEPENDENCE; STEAM GENERATORS; SURFACE CONTAMINATION; TEMPERATURE DEPENDENCE; TRANSIENTS; TRITIUM RECOVERY
OSTI ID:
181025
Research Organizations:
CEA Centre d`Etudes de Saclay, 91 - Gif-sur-Yvette (France). Dept. de Mecanique et de Technologie
Country of Origin:
France
Language:
English
Other Identifying Numbers:
Other: ON: DE96613140; TRN: FR9502064012496
Availability:
INIS; OSTI as DE96613140
Submitting Site:
FRN
Size:
5 p.
Announcement Date:
Feb 20, 1996

Citation Formats

Fuetterer, M A, Raepsaet, X, and Proust, E. Tritium permeation through helium-heated steam generators of ceramic breeder blankets for DEMO. France: N. p., 1994. Web.
Fuetterer, M A, Raepsaet, X, & Proust, E. Tritium permeation through helium-heated steam generators of ceramic breeder blankets for DEMO. France.
Fuetterer, M A, Raepsaet, X, and Proust, E. 1994. "Tritium permeation through helium-heated steam generators of ceramic breeder blankets for DEMO." France.
@misc{etde_181025,
title = {Tritium permeation through helium-heated steam generators of ceramic breeder blankets for DEMO}
author = {Fuetterer, M A, Raepsaet, X, and Proust, E}
abstractNote = {The specifications of permeation barriers, tritium recovery process maintaining a very low tritium activity in the coolant, and control of the coolant chemistry, required the evaluation of the tritium losses through the steam generators and include the definition of its operating conditions by thermodynamic cycle calculations and its thermal-hydraulic design. For both tasks specific computer tools were developed. The obtained geometry, surface area, and temperature profiles along the heat exchanger tubes were then used to estimate the daily tritium permeation into the steam cycle. Steam oxidized Incoloy 800 austenitic stainless steel was identified as the best suited existing material; in nominal steady-state operation, the tritium escape into the steam cycle could be restricted to less than 10 Ci/d. Tritium permeation during temperature and pressure transients in the steam generator (destruction and possible self-healing of the permeation barrier) is identified to bear a large tritium release potential. Solutions are proposed. (from authors). 4 figs., 1 tab.}
place = {France}
year = {1994}
month = {Dec}
}