2005
DOI: 10.1093/rpd/nci260
|View full text |Cite
|
Sign up to set email alerts
|

SOURCES: a code for calculating (α,n), spontaneous fission, and delayed neutron sources and spectra

Abstract: SOURCES is a computer code that determines neutron production rates and spectra from (alpha,n) reactions, spontaneous fission and delayed neutron emission owing to the decay of radionuclides in homogeneous media, interface problems and three-region interface problems. The code is also capable of calculating the neutron production rates due to (alpha,n) reactions induced by a monoenergetic beam of alpha particles incident on a slab of target material. The (alpha,n) spectra are calculated using an assumed isotro… Show more

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...
1
1
1
1

Citation Types

1
83
0

Year Published

2008
2008
2024
2024

Publication Types

Select...
8
1
1

Relationship

0
10

Authors

Journals

citations
Cited by 78 publications
(99 citation statements)
references
References 14 publications
1
83
0
Order By: Relevance
“…capture on 63 Cu and 65 Cu in the copper components, and on 136 Xe in the LXe). A simulation using a simplified experimental geometry and employing the FLUKA [22,23] and SOURCES [24] software packages is used to generate neutrons, track and thermalize them. The resulting neutron capture rates are used as input to the Geant4-based [20] EXO-200 simulation package [9], with the respective ncapture γ-spectra produced based upon ENSDF information [25] for the given nuclides.…”
Section: Investigation and Determination Of Systematic Errorsmentioning
confidence: 99%
“…capture on 63 Cu and 65 Cu in the copper components, and on 136 Xe in the LXe). A simulation using a simplified experimental geometry and employing the FLUKA [22,23] and SOURCES [24] software packages is used to generate neutrons, track and thermalize them. The resulting neutron capture rates are used as input to the Geant4-based [20] EXO-200 simulation package [9], with the respective ncapture γ-spectra produced based upon ENSDF information [25] for the given nuclides.…”
Section: Investigation and Determination Of Systematic Errorsmentioning
confidence: 99%
“…For alumina, such as is used for the construction of the insulator in this model of resistor, the total neutron yield (due to the high cross-section (α,n) reaction involving 27 Al) for the 238 U chain in equilibrium is calculated using the SOURCES4A software [30]. The soft- Table 6: Calculated contaminations for a sample of resistors screened using both Chaloner and Lunehead.…”
Section: Significant Disequilibrium At 210 Pbmentioning
confidence: 99%
“…Neutrons originating from the Th and U decay chains were simulated for each material in the setup (lead, polyethylene, copper). The primary energy spectra of the neutrons was generated using the SOURCES4C package [74][75][76], which computes the neutron spectra due to spontaneous fission and (α, n) reactions of alphas from the full decay chains within the matrix material. The neutrons were propagated through all materials, eventually creating NRs in the Ge and Si detectors.…”
Section: Radiogenic Background Estimatementioning
confidence: 99%