BROWSE

Related Researcher

Author's Photo

Ahn, Sangjoon
UNIST RAdioactive NUclear Materials (URANUM) Laboratory
Research Interests
  • Nuclear Fuel Performance Experiments & Modeling
  • Radiation Interactions with Matter
  • Thermophysical Investigation of Nuclear Materials
  • Nuclear Non-Proliferation Technology

ITEM VIEW & DOWNLOAD

DEVELOPMENT OF LEAD SLOWING DOWN SPECTROMETER FOR ISOTOPIC FISSILE ASSAY

Cited 0 times inthomson ciCited 0 times inthomson ci
Title
DEVELOPMENT OF LEAD SLOWING DOWN SPECTROMETER FOR ISOTOPIC FISSILE ASSAY
Author
Lee, YongdeokPark, ChangjeAhn, SangjoonKim, Hodong
Issue Date
2014-12
Publisher
KOREAN NUCLEAR SOC
Citation
NUCLEAR ENGINEERING AND TECHNOLOGY, v.46, no.6, pp.837 - 846
Abstract
A lead slowing down spectrometer (LSDS) is under development for analysis of isotopic fissile material contents in pyro-processed material, or spent fuel. Many current commercial fissile assay technologies have a limitation in accurate and direct assay of fissile content. However, LSDS is very sensitive in distinguishing fissile fission signals from each isotope. A neutron spectrum analysis was conducted in the spectrometer and the energy resolution was investigated from 0.1eV to 100keV. The spectrum was well shaped in the slowing down energy. The resolution was enough to obtain each fissile from 0.2eV to lkeV. The detector existence in the lead will disturb the source neutron spectrum. It causes a change in resolution and peak amplitude. The intense source neutron production was designed for similar to E12 n's/sec to overcome spent fuel background. The detection sensitivity of U238 and Th232 fission chamber was investigated. The first and second layer detectors increase detection efficiency. Thorium also has a threshold property to detect the fast fission neutrons from fissile fission. However, the detection of Th232 is about 76% of that of U238. A linear detection model was set up over the slowing down neutron energy to obtain each fissile material content. The isotopic fissile assay using LSDS is applicable for the optimum design of spent fuel storage to maximize burnup credit and quality assurance of the recycled nuclear material for safety and economics. LSDS technology will contribute to the transparency and credibility of pyro-process using spent fuel, as internationally demanded.
URI
https://scholarworks.unist.ac.kr/handle/201301/13433
URL
http://www.sciencedirect.com/science/article/pii/S1738573315301510
DOI
10.5516/NET.06.2014.069
ISSN
1738-5733
Appears in Collections:
NUE_Journal Papers
Files in This Item:
There are no files associated with this item.

find_unist can give you direct access to the published full text of this article. (UNISTARs only)

Show full item record

qrcode

  • mendeley

    citeulike

Items in DSpace are protected by copyright, with all rights reserved, unless otherwise indicated.

MENU