Tritium control in fusion reactor materials: A model for Tritium Extracting System
Creators
- 1. DENERG, Politecnico di Torino (Italy)
- 2. ENEA UTIS – C.R. Brasimone, Bacino del Brasimone, Camugnano, BO (Italy)
- 3. University of California Los Angeles (UCLA), Los Angeles, CA (United States)
- 4. Karlsruhe Institute of Technology, Karlsruhe (Germany)
Description
Highlights: • A modeling work has been performed to address these issues in view of its utilization for the TES (Tritium Extraction System), in the case of the HCPB TBM and for a Molecular sieve as adsorbent material. • A computational model has been setup and tested in this paper. • The results of experimental measurement of fundamental parameters such as mass transfer coefficients have been implemented in the model. • It turns out the capability to model the extraction process of gaseous tritium compounds and to estimate the breakthrough curves of the two main tritium gaseous species (H2 and HT). - Abstract: In fusion reactors, tritium is bred by lithium isotopes inside the blanket and then extracted. However, tritium can contaminate the reactor structures, and can be eventually released into the environment. Tritium in reactor components should therefore be kept under close control throughout the fusion reactor lifetime, bearing in mind the risk of accidents, the need for maintenance and the detritiation of dismantled reactor components before their re-use or disposal. A modeling work has been performed to address these issues in view of its utilization for the TES (Tritium Extraction System), in the case of the HCPB TBM and for a molecular sieve as adsorbent material. A computational model has been setup and tested. The results of experimental measurement of fundamental parameters such as mass transfer coefficients have been implemented in the model. It turns out the capability of the model to describe the extraction process of gaseous tritium compounds and to estimate the breakthrough curves of the two main tritium gaseous species (H2 and HT).
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2015.06.052Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2015.06.052;
- PII
- S0920-3796(15)30082-X;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 98-99
- Journal Page Range
- p. 1885-1888
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 28. symposium on fusion technology
- Acronym
- SOFT-28
- Dates
- 29 Sep - 3 Oct 2014
- Place
- San Sebastian (Spain)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48006731
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDING BLANKETS; EXTRACTION; ITER TOKAMAK; LITHIUM ISOTOPES; MAINTENANCE; MASS TRANSFER; MOLECULAR SIEVES; RISK ASSESSMENT; SERVICE LIFE; SIMULATION; THERMONUCLEAR REACTOR MATERIALS; TRITIUM; TRITIUM COMPOUNDS
- Descriptors DEC
- ADSORBENTS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLOSED PLASMA DEVICES; HYDROGEN COMPOUNDS; HYDROGEN ISOTOPES; ISOTOPES; LIFETIME; LIGHT NUCLEI; MATERIALS; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; REACTOR COMPONENTS; SEPARATION PROCESSES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.