TY - JOUR
T1 - Advanced Method for Calculations of Core Burn-Up, Activation of Structural Materials, and Spallation Products Accumulation in Accelerator-Driven Systems
AU - Stankovskiy, Alexey
AU - Van den Eynde, Gert
A2 - Baeten, Peter
N1 - Score = 10
PY - 2012/4/10
Y1 - 2012/4/10
N2 - 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-Kuttamethod. 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.
AB - 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-Kuttamethod. 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.
KW - Particle transport
KW - depletion
KW - cross sections
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_120700
UR - http://knowledgecentre.sckcen.be/so2/bibref/9843
U2 - 10.1155/2012/545103
DO - 10.1155/2012/545103
M3 - Article
SN - 1687-6075
VL - 2012
SP - 1
EP - 12
JO - Science and Technology of Nuclear Installations
JF - Science and Technology of Nuclear Installations
IS - 1
ER -