A study of the potential influence of frame coolant distribution on the radiation-induced damage of HCLL-TBM structural material
- 1. Dipartimento di Ingegneria Nucleare, Universita di Palermo, Viale delle Scienze, 90128 Palermo (Italy)
Description
Within the European Fusion Technology Programme, the Helium-Cooled Lithium Lead (HCLL) breeding blanket concept is one of the two EU lines to be developed for a Long Term fusion reactor, in particular with the aim of manufacturing a Test Blanket Module (TBM) to be implemented in ITER. The HCLL-TBM is foreseen to be located in an ITER equatorial port, being housed inside a steel-supporting frame, actively cooled by pressurized water. That supporting frame has been designed to house two different TBMs, providing two cavities separated by a dividing Plate 20 cm thick. As the nuclear response of HCLL-TBM might vary accordingly to the supporting frame configuration and composition, at the Department of Nuclear Engineering of the University of Palermo, a parametric study has been launched to investigate such an influence. Previous works dealt with the dependence of the nuclear response of HCLL-TBM on the configuration of a homogeneous frame, the present one has been focused on the investigation of the potential influence of coolant distribution within the frame on the radiation-induced damage of the HCLL-TBM structural material. To this purpose, a detailed parametric study of the HCLL-TBM nuclear response has been performed by means of 3D-Monte Carlo neutronic analyses to asses both the rates of displacements per atom and helium and hydrogen production within the structural material. A semi-heterogeneous model of the supporting frame, assuming a realistic coolant distribution, and a 3D heterogeneous model of the HCLL-TBM, taking into account EUROFER as structural material, has been set-up. Therefore, the models of the TBM and of its frame have been inserted into the existing 3D ITER one, simulating realistically the reactor lay-out up to the cryostat and providing for a proper D-T neutron source. The analyses have been performed by means of the MCNP-4C code, and the results obtained are reported and critically discussed
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2008.08.022Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2008.08.022;
- PII
- S0920-3796(08)00246-9;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 83
- Journal Issue
- 7-9
- Journal Page Range
- p. 1273-1276
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 8. international symposium of fusion nuclear technology
- Acronym
- ISFNT-8 SI
- Dates
- 30 Sep - 5 Oct 2007
- Place
- Heidelberg (Germany)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 40087289
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATOMIC DISPLACEMENTS; BREEDING BLANKETS; CONFIGURATION; COOLANTS; CRYOSTATS; DAMAGE; HELIUM; HYDROGEN PRODUCTION; ITER TOKAMAK; LEAD; LITHIUM; MONTE CARLO METHOD; NEUTRON SOURCES; NUCLEAR ENGINEERING; PARAMETRIC ANALYSIS; STEELS; WATER
- Descriptors DEC
- ALKALI METALS; ALLOYS; CALCULATION METHODS; CARBON ADDITIONS; CLOSED PLASMA DEVICES; CONTROL EQUIPMENT; ELEMENTS; ENGINEERING; EQUIPMENT; FLUIDS; GASES; HYDROGEN COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; METALS; NONMETALS; OXYGEN COMPOUNDS; PARTICLE SOURCES; PHYSICAL RADIATION EFFECTS; RADIATION EFFECTS; RADIATION SOURCES; RARE GASES; REACTOR COMPONENTS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; THERMOSTATS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENT ALLOYS
Optional Information
- Copyright
- Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.