ALEPH2 Monte Carlo burn up code

Gert Van den Eynde; Alexey Stankovskiy; Edouard Malambu Mbala; Tim Vidmar; Peter Baeten

ALEPH2 Monte Carlo burn up code

Gert Van den Eynde, Alexey Stankovskiy, Edouard Malambu Mbala, Tim Vidmar, Peter Baeten

Research output › peer-review

Abstract

ALEPH is a Monte Carlo burn up code under development at SCK-CEN. The first version (ALEPH1) was a coupling between MCNP/X and ORIGEN. Based on neutron spectra calculated by MCNP/X, a one-group cross section library would be generated to be used for the depletion calculations in ORIGEN. In the current version, ALEPH2, the dependence on ORIGEN has been removed and the depletion part is handled by a stiff ODE solver from the RADAU family. Next to this, many other improvements have been made.

Original language	English
Title of host publication	Proceedings of the International Conference on Nuclear Criticality Safety
Place of Publication	Paris, France
State	Published - 19 Sep 2011
Event	International Conference on Nuclear Criticality (ICNC) - Edinburgh Duration: 19 Sep 2011 → 23 Sep 2011

Conference

Conference	International Conference on Nuclear Criticality (ICNC)
Country/Territory	United Kingdom
City	Edinburgh
Period	2011-09-19 → 2011-09-23

Cite this

@inproceedings{b309e66fb5e6435a8b65c66b1c5454ca,

title = "ALEPH2 Monte Carlo burn up code",

abstract = "ALEPH is a Monte Carlo burn up code under development at SCK-CEN. The first version (ALEPH1) was a coupling between MCNP/X and ORIGEN. Based on neutron spectra calculated by MCNP/X, a one-group cross section library would be generated to be used for the depletion calculations in ORIGEN. In the current version, ALEPH2, the dependence on ORIGEN has been removed and the depletion part is handled by a stiff ODE solver from the RADAU family. Next to this, many other improvements have been made.",

keywords = "ALEPH, Monte Carlo, depletion, ORIGEN",

author = "{Van den Eynde}, Gert and Alexey Stankovskiy and {Malambu Mbala}, Edouard and Tim Vidmar and Peter Baeten",

note = "Score = 3; International Conference on Nuclear Criticality (ICNC) ; Conference date: 19-09-2011 Through 23-09-2011",

year = "2011",

month = sep,

day = "19",

language = "English",

booktitle = "Proceedings of the International Conference on Nuclear Criticality Safety",

}

TY - GEN

T1 - ALEPH2 Monte Carlo burn up code

AU - Van den Eynde, Gert

AU - Stankovskiy, Alexey

AU - Malambu Mbala, Edouard

AU - Vidmar, Tim

A2 - Baeten, Peter

N1 - Score = 3

PY - 2011/9/19

Y1 - 2011/9/19

N2 - ALEPH is a Monte Carlo burn up code under development at SCK-CEN. The first version (ALEPH1) was a coupling between MCNP/X and ORIGEN. Based on neutron spectra calculated by MCNP/X, a one-group cross section library would be generated to be used for the depletion calculations in ORIGEN. In the current version, ALEPH2, the dependence on ORIGEN has been removed and the depletion part is handled by a stiff ODE solver from the RADAU family. Next to this, many other improvements have been made.

AB - ALEPH is a Monte Carlo burn up code under development at SCK-CEN. The first version (ALEPH1) was a coupling between MCNP/X and ORIGEN. Based on neutron spectra calculated by MCNP/X, a one-group cross section library would be generated to be used for the depletion calculations in ORIGEN. In the current version, ALEPH2, the dependence on ORIGEN has been removed and the depletion part is handled by a stiff ODE solver from the RADAU family. Next to this, many other improvements have been made.

KW - ALEPH

KW - Monte Carlo

KW - depletion

KW - ORIGEN

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_116832

UR - http://knowledgecentre.sckcen.be/so2/bibref/8426

M3 - In-proceedings paper

BT - Proceedings of the International Conference on Nuclear Criticality Safety

CY - Paris, France

T2 - International Conference on Nuclear Criticality (ICNC)

Y2 - 19 September 2011 through 23 September 2011

ER -