Future technological tests on large-scale mock-ups of ITER blanket modules at IVV-2M reactor
- Research and Development Inst. of Power Engineering, Sverdlovsk (Russian Federation); and others
A multisection core of water-cooled water-moderated reactor IVV-2M facilities testing of large scale mock-ups of ITER breeder blanket modules, the reactor arrangement in a building provides a maximum close position of tritium {open_quotes}in-pile{close_quotes} measurement station {open_quotes}RITM{close_quotes} to the core (in-pile testing of tritium producing mock-ups). Mock-ups of ceramic and liquid metal blankets are planned to be tested complying the following requirements: mock-up dimensions maximum close to those of ITER, distributions of nuclear power density, temperature fields, tritium release modes at continuous helium purging, provision of cyclic neutron and thermal loading variations. Variants of location of large ({approximately}150x200 mm) mock-up of ceramic blanket and a submerged loop facility containing liquid lithium and a vanadium alloy as a structure material are described. A technological scheme of {open_quotes}RITM{close_quotes} measurement station to study tritium system operation modes are presented.
- OSTI ID:
- 197094
- Report Number(s):
- CONF-940664-; TRN: 95:005767-0272
- 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; Related Information: Is Part Of Third international symposium on fusion nuclear technology; PB: 362 p.
- Country of Publication:
- United States
- Language:
- English
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