Development of ceramic breeding zone models and mock-up of a demo blanket for in-pile irradiation testing

Citation
V. Kapychev et al., Development of ceramic breeding zone models and mock-up of a demo blanket for in-pile irradiation testing, PLASMA D OP, 8(3), 2000, pp. 187-199
Citations number
2
Language
INGLESE
art.tipo
Article
Categorie Soggetti
Nuclear Emgineering
Journal title
PLASMA DEVICES AND OPERATIONS
ISSN journal
1051-9998 → ACNP
Volume
8
Issue
3
Year of publication
2000
Pages
187 - 199
Database
ISI
SICI code
1051-9998(2000)8:3<187:DOCBZM>2.0.ZU;2-W
Abstract
A goal of demonstration fusion reactor (DEMO) with ceramic helium cooled (C HC) blanket test module (BTM) is to demonstrate the breeding capability tha t would lead to tritium self-sufficiency in the ITER reactor and to extract a high-grade heat suitable for electricity generation. The experimental va lidation of all the adopted design solutions is one of main concerns at des ign and calculation works carried out with the aim to create the CHC BTM. T he in-pile test is one of the most important components of the bleeding zon e feasibility validation. For validation of the CHC BTM breeding zone feasibility we have developed a nd fabricated two models and breeding blanket mock-up for testing in the IV V-2M reactor. The first model and mock-up contain pellets from lithium orth osilicate and porous beryllium, the second model contains pebbles from thes e materials. The tritium produced in the breeder material is purged by flow of neon at 0.1 - 0.2 MPa. The models structural material is ferrite marten site steel. A special processing installation has been designed, constructed and assemb led at the IVV-2M reactor for study of the kinetics of tritium extraction f rom ceramics under the reactor irradiation. Designs of the models and experimental channel and results of neutronic and thermohydraulic calculations are presented in the paper.