Ceramic helium-cooled blanket test module

The design of RF DEMO-relevant ceramic helium cooled blanket test module (C HC BTM) for testing in international thermonuclear experimental reactor (IT ER) is under consideration. The RF concept of DEMO BTM is based upon the br eeder inside tube (BIT)-concept. This concept suggests the use of solid bre eding ceramic material, helium as coolant and tritium purge-gas, ferrite-ma rtensite steel as structural material, and beryllium as neutron multiplier. The parameters of the primary circuit coolant are the following, pressure -8 MPa, inlet/outlet temperature - 300/550 degreesC, respectively. Helium ( 0.1 MPa pressure) is used for tritium removal from ceramic breeder. The ITE R water coolant is the secondary circuit coolant of DEMO BTM cooling system . Lithium orthosilicate (Li4SiO4) is used as tritium breeding material (peb bles-bed of empty set 0.5-1 mm spheres). It is planned to use the beryllium as neutron multiplier (spheres empty set 1 mm pebbles-bed or the porous be ryllium). The 3-D neutronic calculations on Monte Carlo method, in accordan ce with FENDL-1 library of the nuclear data, have been performed for CHC BT M. To validate the CHC BTM concept, the thermal hydraulic analysis has been performed for the design elements and cooling system equipment. The prelim inary stress analysis for BTM design elements has been carried out on the A SME-code and RF strength regulations. The four types of LOFA and LOCA accid ents have been investigated. The parameters of cooling, coolant purificatio n and tritium extraction systems have been determined. (C) 2000 Elsevier Sc ience B.V. All rights reserved.