Preliminary computational and experimental design studies of the ISHTAR thermostatic rig for the high-temperature reactors materials irradiation

Abstract

The Irradiation System for High-Temperature Reactors (ISHTAR) thermostatic rig will be used to irradiate advanced core material samples in conditions corresponding to those prevailing in the high-temperature reactors (HTRs): these conditions include a stable temperature extending up to 1000°C in the helium atmosphere. Computational and experimental studies concerning the design have been conducted, proving the possibility of these conditions’ fulfillment inside the rig while maintaining the safety limits for MARIA research reactor. The outcome is the thermostatic rig design that will be implemented in the MARIA reactor. Appropriate irradiation temperature will be achieved by a combination of electric heating with the control system, gamma heating, and a helium insulation gap with precisely designed thickness. The ISHTAR rig will be placed inside the vertical irradiation channel, which is located in the reactor pool. The device is being developed from scratch at the Nuclear Facilities Operation Department of the National Centre for Nuclear Research as a part of the GOSPOSTRATEG programme.

MARIA Reactor Irradiation Technology Capabilities towards Advanced Applications

“…The ISHTAR device was tested with the use of special hydraulic stand, and the first batch of measurements confirmed that we can achieve 1000 • C [34] inside the capsule. Since August 2021 it has been installed in the core and successfully operated for three consecutive reactor operational cycles [35].…”

Modelling Irradiation Effects in Metallic Materials Using the Crystal Plasticity Theory—A Review

“…Although presently built generation III/III+ NPPs are much improved as compared to previous projects, generation IV (Gen-IV) initiative calls for new nuclear energy systems that will significantly improve the safety and reliability, sustainability, useful reactor life, proliferation-resistance, and profitability [5]. Generation-IV International Forum (GIF) members identified six systems [6]: very high temperature gas-cooled reactors (VHTR) [7,8], gas-cooled fast reactors (GFR) [9], sodium-cooled fast reactors (SFR) [10,11], lead-cooled fast reactors (LFR) [12], molten salt reactors (MSR) [13], and super-critical water-cooled reactors (SCWR) [14]. However, the Gen-IV projects typically pose new material challenges.…”