Abstract
In this study, an approach to simulate a novel variable-yield heterogeneous 241Am-9Be was proposed with a hybrid use of SOURCES4C and MCNPX codes, and its energy spectrum and neutron emission yield were simulated. In these simulations, the energy spectra of the alpha particles emitted from the americium source and the neutrons produced within the beryllium and oxygen contents as a result of 9Be(α,n) and 17,18O(α,n) reactions were calculated with SOURCES4C whilst the neutron transport from neutron production points to the space outside the source assembly were performed with the MCNPX code. The neutron energy spectrum and neutron emission yield for two different configurations of single-rod and multi-rod sources (i.e., americium or americium oxide rods in beryllium medium) were compared to a source of homogeneous americium (or its oxides) and beryllium mixture. The proposed heterogeneous geometry was aimed to provide a neutron source with a variable neutron yield, easy-to-shut down and easy-to-waste process features. The results confirmed that the homogeneous source represented the largest neutron yield compared to single- and multi-rod geometries. However, the neutron yield in heterogenous geometry could be altered by varying the number of americium (or americium oxide) rods to reach the desired neutron yield.
| Original language | English |
|---|---|
| Article number | 108811 |
| Journal | Applied Radiation and Isotopes |
| Volume | 153 |
| DOIs | |
| Publication status | Published - 1 Nov 2019 |
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Keywords
- Am-Be
- Energy spectrum
- MCNPX
- Neutron source assembly
- Neutron yield
- SOURCES4C
ASJC Scopus subject areas
- Radiation
Cite this
Conceptual design for a new heterogeneous 241Am-9Be neutron source assembly using SOURCES4C-MCNPX hybrid simulations. / Ghal-Eh, N.; Rahmani, F.; Bedenko, S. V.
In: Applied Radiation and Isotopes, Vol. 153, 108811, 01.11.2019.Research output: Contribution to journal › Article
}
TY - JOUR
T1 - Conceptual design for a new heterogeneous 241Am-9Be neutron source assembly using SOURCES4C-MCNPX hybrid simulations
AU - Ghal-Eh, N.
AU - Rahmani, F.
AU - Bedenko, S. V.
PY - 2019/11/1
Y1 - 2019/11/1
N2 - In this study, an approach to simulate a novel variable-yield heterogeneous 241Am-9Be was proposed with a hybrid use of SOURCES4C and MCNPX codes, and its energy spectrum and neutron emission yield were simulated. In these simulations, the energy spectra of the alpha particles emitted from the americium source and the neutrons produced within the beryllium and oxygen contents as a result of 9Be(α,n) and 17,18O(α,n) reactions were calculated with SOURCES4C whilst the neutron transport from neutron production points to the space outside the source assembly were performed with the MCNPX code. The neutron energy spectrum and neutron emission yield for two different configurations of single-rod and multi-rod sources (i.e., americium or americium oxide rods in beryllium medium) were compared to a source of homogeneous americium (or its oxides) and beryllium mixture. The proposed heterogeneous geometry was aimed to provide a neutron source with a variable neutron yield, easy-to-shut down and easy-to-waste process features. The results confirmed that the homogeneous source represented the largest neutron yield compared to single- and multi-rod geometries. However, the neutron yield in heterogenous geometry could be altered by varying the number of americium (or americium oxide) rods to reach the desired neutron yield.
AB - In this study, an approach to simulate a novel variable-yield heterogeneous 241Am-9Be was proposed with a hybrid use of SOURCES4C and MCNPX codes, and its energy spectrum and neutron emission yield were simulated. In these simulations, the energy spectra of the alpha particles emitted from the americium source and the neutrons produced within the beryllium and oxygen contents as a result of 9Be(α,n) and 17,18O(α,n) reactions were calculated with SOURCES4C whilst the neutron transport from neutron production points to the space outside the source assembly were performed with the MCNPX code. The neutron energy spectrum and neutron emission yield for two different configurations of single-rod and multi-rod sources (i.e., americium or americium oxide rods in beryllium medium) were compared to a source of homogeneous americium (or its oxides) and beryllium mixture. The proposed heterogeneous geometry was aimed to provide a neutron source with a variable neutron yield, easy-to-shut down and easy-to-waste process features. The results confirmed that the homogeneous source represented the largest neutron yield compared to single- and multi-rod geometries. However, the neutron yield in heterogenous geometry could be altered by varying the number of americium (or americium oxide) rods to reach the desired neutron yield.
KW - Am-Be
KW - Energy spectrum
KW - MCNPX
KW - Neutron source assembly
KW - Neutron yield
KW - SOURCES4C
UR - http://www.scopus.com/inward/record.url?scp=85069633951&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=85069633951&partnerID=8YFLogxK
U2 - 10.1016/j.apradiso.2019.108811
DO - 10.1016/j.apradiso.2019.108811
M3 - Article
AN - SCOPUS:85069633951
VL - 153
JO - Applied Radiation and Isotopes
JF - Applied Radiation and Isotopes
SN - 0969-8043
M1 - 108811
ER -