Rossi, F. 
; Rodriguez, D. ; Takahashi, Tone; Seya, Michio; Koizumi, Mitsuo
This paper (presentation) reports on the design study for seeking compactness of moderator (and reflector) structure for the Delayed Gamma-ray Spectroscopy Non Destructive Assay system to be applied for verification of fissile isotopic (Pu-239, Pu-241 and U-235) composition ratio in High Radioactive Nuclear Material sample such as dissolved solution of reprocessing facility. We first investigated advantages and disadvantages of using different compact neutron sources as DT and DD neutron generators. This led us to the conclusion of using DD sources to achieve a compact (and practical) NDA system. Based on MCNP simulations, with the use of a DD neutron generator, a preliminary optimization study was performed and will be shown here.
Language |
: | English |
|---|---|---|
Journal |
: | Nihon Kaku Busshitsu Kanri Gakkai Dai-39-Kai Nenji Taikai Rombunshu (CD-ROM) |
Volume |
: | |
Number |
: | |
Pages |
: | 3 Pages |
Publication Year/Month |
: | 2018/11 |
Meeting title |
: | |
Held date |
: | 2018/11 |
Location (city) |
: | 東京 |
Location (country) |
: | 日本 |
Paper URL |
: |
|
Keywords |
: | Delayed gamma spectroscopy; DD neutron generator; Safeguards; Monte Carlo Simulations; Moderator optimization |
Cooperating Institute |
: |
Accesses |
: |
- Accesses |
|---|---|---|
Altmetrics |
: |
[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.
Times Cited Count：