Development and validation of ALEPH2 Monte Carlo burn-up code

Conference · Mon Jul 01 04:00:00 EDT 2013

OSTI ID:22212898

Van Den Eynde, G.; Stankovskiy, A.; Fiorito, L.; Broustaut, M. ^[1]

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1. SCK-CEN, Boeretang 200, B-2400 Mol (Belgium)

The ALEPH2 Monte Carlo depletion code has two principal features that make it a flexible and powerful tool for reactor analysis. First of all, its comprehensive nuclear data library ensures the consistency between steady-state Monte Carlo and deterministic depletion modules. It covers 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, ALEPH2 uses an advanced 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. The code is extensively used for the neutronics design of the MYRRHA research fast spectrum facility which will operate in both critical and sub-critical modes. The code has been validated on the decay heat data from JOYO experimental fast reactor. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22212898
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
97 MATHEMATICS AND COMPUTING
A CODES
AFTER-HEAT
BURNUP
COMPUTERIZED SIMULATION
DESIGN
DIFFERENTIAL EQUATIONS
FISSION PRODUCTS
JOYO REACTOR
MONTE CARLO METHOD
NUCLEAR DATA COLLECTIONS
RUNGE-KUTTA METHOD
SPECTRA
SPONTANEOUS FISSION
VALIDATION