Published October 16, 2018 | Version v1
Report

Tritium Handling and Recovery System for Accelerator Based 14-MeV Neutron Generator

  • 1. ITER-India, Institute for Plasma Research (IPR), Bhat, Gandhinagar (India)
  • 2. Institute for Plasma Research (IPR), Bhat, Gandhinagar (India)

Description

Full text: An accelerator based 14 MeV neutron source is under development to study the fusion neutronics for Indian fusion programmes. The neutrons are generated by impinging 10 mA deuterium beam accelerated up to 340 keV energy over a 140 Ci tritium target. Being a system handling tritium radioactive material, a recovery system is to be designed to minimize airborne tritium effluent releases to well below the permitted limit. In addition, the system should minimize tritium exposure to staff by maintaining low levels of tritium in the rotating tritium target holder (RTTH). The paper presents the first estimated value of tritium escaping into the exhaust of the accelerator system. A mathematical model is developed to estimate the amount of tritium sputtered from the target. The calculated result is then successfully simulated using SRIM software, and validated using the experimental results available. According to M. Martone, J. Nucl. Mater., 212–215, 1661–1664 (1994), tritium release from the target at maximum power has been evaluated to be 37 GBq/h experimentally. As per our calculation method and the simulated results, the tritium release is calculated to be 40 GBq/h which is in very close conformance with the claimed value. Based on this primary calculated data a conceptual design of the tritium handling and recovery system (THRS) is also presented. There are a number of technologies available for THR like, metal membrane reactors, cryogenic adsorption on molecular sieve beds, getter beds, cryogenic freezing, high temperature electrolysis, and catalytic oxidation. Today globally, getter bed technology for the tritium separation is in frequent practice. This paper also elaborates the specific selection criteria for development of recovery system. Followed by determining the significance of the selection criteria using pairwise comparison (Pugh matrix) approach for weighting the criteria accordingly, and selecting the appropriate technology. (author)

Part of:
27th IAEA Fusion Energy Conference. Programme and Book of Abstracts

Additional details

Publishing Information

Imprint Title
27th IAEA Fusion Energy Conference. Programme and Book of Abstracts
Imprint Pagination
844 p.
Journal Page Range
p. 671
Report number
IAEA-CN--258

Conference

Title
27. IAEA Fusion Energy Conference
Acronym
FEC 2018
Dates
22-27 Oct 2018
Place
Ahmedabad (India)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
50057756
Subject category
S07: ISOTOPES AND RADIATION SOURCES;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CRYOGENICS; DEUTERIUM; MEV RANGE 10-100; MOLECULAR SIEVES; NEUTRON GENERATORS; RADIOACTIVE MATERIALS; SPUTTERING; TRITIUM; TRITIUM TARGET
Descriptors DEC
ADSORBENTS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; ENERGY RANGE; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; MATERIALS; MEV RANGE; NEUTRON SOURCES; NUCLEI; ODD-EVEN NUCLEI; ODD-ODD NUCLEI; PARTICLE SOURCES; RADIATION SOURCES; RADIOISOTOPES; STABLE ISOTOPES; TARGETS; YEARS LIVING RADIOISOTOPES

Optional Information

Notes
1 ref.
Secondary number(s)
IAEA-CN--258-607