Proposal for Combined Electrolysis and Catalytic Exchange System (CECE) development within the Pilot Plant
- 1. National R&D Institute for Cryogenics and Isotopic Technologies – ICSI, Uzinei 4, Rm. Valcea (Romania)
Description
Nuclear reactors generate low concentration tritium and deuterium waste water. Romania, where two CANDU type reactors are in operation, has been committed to promoting concrete and fast measures for the radioactive waste management, and solving problems related to the processing of tritiated water waste is of particular relevance. The recovery of tritium/deuterium can be accomplished by combined isotopic transfer processes, but poorly concentrated water require the use of technologies that ensure a pre-concentration, providing efficient waste management by reducing inventory and increasing the tritium and deuterium recovery. The CECE process is suitable for the concentration of tritium and deuterium in such waste as well as for the transfer of tritium from water to gas at higher concentration levels. We chose this option to develop a technological system that complete the Pilot Plant from ICSI Rm.Valcea (based on Liquid Phase Catalytic Exchange followed by Cryogenic Distillation), extending the concentration range for water detritiation. This paper presents a research direction in two stages: the realization of an experimental installation based on the CECE process in order to acquire knowledge and obtaining the necessary information for design and the second stage the developing of a demonstrative installation in addition to the existing Pilot Plant. The demonstrative installation will be designed to be operated independently of the existing Pilot Plant and providing only an increasing concentration of tritium and deuterium in water, or coupled to the Pilot Plant for tritium and deuterium recovery.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2018.03.046Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2018.03.046;
- PII
- S0920379618302655;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 136
- Journal Issue
- Part A
- Journal Page Range
- p. 645-649
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51011938
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- CANDU TYPE REACTORS; CRYOGENICS; DEUTERIUM; DISTILLATION; ELECTROLYSIS; MATERIALS RECOVERY; PILOT PLANTS; RADIOACTIVE WASTE MANAGEMENT; TRITIUM; TRITIUM OXIDES; TRITIUM RECOVERY; WASTE WATER
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CHALCOGENIDES; FUNCTIONAL MODELS; HEAVY WATER MODERATED REACTORS; HYDROGEN COMPOUNDS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; LIQUID WASTES; LYSIS; MANAGEMENT; NUCLEI; ODD-EVEN NUCLEI; ODD-ODD NUCLEI; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; PRESSURE TUBE REACTORS; PROCESSING; RADIOISOTOPES; REACTORS; SEPARATION PROCESSES; STABLE ISOTOPES; THERMAL REACTORS; TRITIUM COMPOUNDS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; WATER; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- © 2018 Elsevier B.V. All rights reserved.