![](/images/graphics-bg.png)
Advanced Method for Calculations of Core Burn-Up, Activation of Structural Materials, and Spallation Products Accumulation in Accelerator-Driven Systems
Joint Authors
Van den Eynde, Gert
Stankovskiy, A.
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2012, Issue 2012 (31 Dec. 2012), pp.1-12, 12 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2012-04-09
Country of Publication
Egypt
No. of Pages
12
Main Subjects
Engineering Sciences and Information Technology
Abstract EN
The ALEPH2 Monte Carlo depletion code has two principal features that make it a flexible and powerful tool for reactor analysis.
First of all, it uses a nuclear data library covering neutron- and proton-induced reactions, neutron and proton fission product yields, spontaneous fission product yields, radioactive decay data, and total recoverable energies per fission.
Secondly, it uses a state-of-the-art numerical solver for the first-order ordinary differential equations describing the isotope balances, namely, a Radau IIA implicit Runge-Kutta method.
The versatility of the code allows using it for time behavior simulation of various systems ranging from single pin model to full-scale reactor model, including such specific facilities as accelerator-driven systems.
The core burn-up, activation of the structural materials, irradiation of samples, and, in addition, accumulation of spallation products in accelerator-driven systems can be calculated in a single ALEPH2 run.
The code is extensively used for the neutronics design of the MYRRHA research facility which will operate in both critical and subcritical modes.
American Psychological Association (APA)
Stankovskiy, A.& Van den Eynde, Gert. 2012. Advanced Method for Calculations of Core Burn-Up, Activation of Structural Materials, and Spallation Products Accumulation in Accelerator-Driven Systems. Science and Technology of Nuclear Installations،Vol. 2012, no. 2012, pp.1-12.
https://search.emarefa.net/detail/BIM-480262
Modern Language Association (MLA)
Stankovskiy, A.& Van den Eynde, Gert. Advanced Method for Calculations of Core Burn-Up, Activation of Structural Materials, and Spallation Products Accumulation in Accelerator-Driven Systems. Science and Technology of Nuclear Installations No. 2012 (2012), pp.1-12.
https://search.emarefa.net/detail/BIM-480262
American Medical Association (AMA)
Stankovskiy, A.& Van den Eynde, Gert. Advanced Method for Calculations of Core Burn-Up, Activation of Structural Materials, and Spallation Products Accumulation in Accelerator-Driven Systems. Science and Technology of Nuclear Installations. 2012. Vol. 2012, no. 2012, pp.1-12.
https://search.emarefa.net/detail/BIM-480262
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-480262