Standardized verification of the CYCLUS fuel cycle simulator

Jin Whan Bae; Joshua L. Peterson-Droogh; Kathryn D. Huff

doi:10.1016/j.anucene.2019.01.014

Standardized verification of the CYCLUS fuel cycle simulator

Jin Whan Bae, Joshua L. Peterson-Droogh, Kathryn D. Huff

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5 Scopus citations

Abstract

Many nuclear fuel cycle simulators can analyze transitions from once-through to advanced nuclear fuel cycles. Verification studies compare various fuel cycle analysis tools to test agreement and identify sources of difference. A recent verification study, Feng et al. (2016) established transition scenario test case specifications and accordingly evaluated national laboratory nuclear fuel cycle simulators, DYMOND, VISION, ORION, and MARKAL. This work verifies the performance of CYCLUS, the agent-based, open-source fuel cycle simulator, using the test case specifications in Feng et. al. In this work, CYCLUS demonstrates agreement with the results from the previous verification study. Minor differences reflect intentional, detailed material tracking in the CYCAMORE reactor module. These results extend the example results in Feng et al. to further enable future verification of additional nuclear fuel cycle simulation tools.

Original language	English
Pages (from-to)	288-291
Number of pages	4
Journal	Annals of Nuclear Energy
Volume	128
DOIs	https://doi.org/10.1016/j.anucene.2019.01.014
State	Published - Jun 2019
Externally published	Yes

Funding

This work was supported by the Nuclear Engineering Science Laboratory Synthesis (NESLS) program as well as the DOE Office of Nuclear Energy's Nuclear Energy University Program (Project 16–10512) ’Demand-Driven Cycamore Archetypes’. We thank Eva Davidson from Oak Ridge National Laboratory (ORNL) and Bo Feng from Argonne National Laboratory (ANL) for their aid in providing benchmark solutions and insight for this work. Additionally, the authors are thankful for the thoughtful reviews from our colleagues in the Advanced Reactors and Fuel Cycles research group.Prof. Huff is supported by the Nuclear Regulatory Commission Faculty Development Program, the Blue Waters sustained-petascale computing project supported by the National Science Foundation (awards OCI-0725070 and ACI-1238993) and the state of Illinois, the NNSA Office of Defense Nuclear Nonproliferation R&D through the Consortium for Verification Technologies and the Consortium for Nonproliferation Enabling Capabilities (awards DE-NA0002576 and DE-NA0002534), and the International Institute for Carbon Neutral Energy Research (WPI-I2CNER), sponsored by the Japanese Ministry of Education, Culture, Sports, Science and Technology. Prof. Huff is supported by the Nuclear Regulatory Commission Faculty Development Program, the Blue Waters sustained-petascale computing project supported by the National Science Foundation (awards OCI-0725070 and ACI-1238993) and the state of Illinois, the NNSA Office of Defense Nuclear Nonproliferation R&D through the Consortium for Verification Technologies and the Consortium for Nonproliferation Enabling Capabilities (awards DE-NA0002576 and DE-NA0002534), and the International Institute for Carbon Neutral Energy Research (WPI-I2CNER), sponsored by the Japanese Ministry of Education, Culture, Sports, Science and Technology. This work was supported by the Nuclear Engineering Science Laboratory Synthesis (NESLS) program as well as the DOE Office of Nuclear Energy’s Nuclear Energy University Program (Project 16–10512) ’Demand-Driven Cycamore Archetypes’. We thank Eva Davidson from Oak Ridge National Laboratory (ORNL) and Bo Feng from Argonne National Laboratory (ANL) for their aid in providing benchmark solutions and insight for this work. Additionally, the authors are thankful for the thoughtful reviews from our colleagues in the Advanced Reactors and Fuel Cycles research group.

Funders	Funder number
National Science Foundation	OCI-0725070, ACI-1238993
U.S. Nuclear Regulatory Commission
Office of Nuclear Energy
Office of Defense Nuclear Nonproliferation	DE-NA0002576, DE-NA0002534
Nuclear Energy University Program	16–10512
Ministry of Education, Culture, Sports, Science and Technology
International Institute for Carbon-Neutral Energy Research, Kyushu University	WPI-I2CNER
National Science Foundation

Keywords

CYCLUS
Nuclear fuel cycle
Simulation
Verification

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10.1016/j.anucene.2019.01.014

Cite this

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title = "Standardized verification of the CYCLUS fuel cycle simulator",

abstract = "Many nuclear fuel cycle simulators can analyze transitions from once-through to advanced nuclear fuel cycles. Verification studies compare various fuel cycle analysis tools to test agreement and identify sources of difference. A recent verification study, Feng et al. (2016) established transition scenario test case specifications and accordingly evaluated national laboratory nuclear fuel cycle simulators, DYMOND, VISION, ORION, and MARKAL. This work verifies the performance of CYCLUS, the agent-based, open-source fuel cycle simulator, using the test case specifications in Feng et. al. In this work, CYCLUS demonstrates agreement with the results from the previous verification study. Minor differences reflect intentional, detailed material tracking in the CYCAMORE reactor module. These results extend the example results in Feng et al. to further enable future verification of additional nuclear fuel cycle simulation tools.",

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doi = "10.1016/j.anucene.2019.01.014",

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AU - Peterson-Droogh, Joshua L.

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AB - Many nuclear fuel cycle simulators can analyze transitions from once-through to advanced nuclear fuel cycles. Verification studies compare various fuel cycle analysis tools to test agreement and identify sources of difference. A recent verification study, Feng et al. (2016) established transition scenario test case specifications and accordingly evaluated national laboratory nuclear fuel cycle simulators, DYMOND, VISION, ORION, and MARKAL. This work verifies the performance of CYCLUS, the agent-based, open-source fuel cycle simulator, using the test case specifications in Feng et. al. In this work, CYCLUS demonstrates agreement with the results from the previous verification study. Minor differences reflect intentional, detailed material tracking in the CYCAMORE reactor module. These results extend the example results in Feng et al. to further enable future verification of additional nuclear fuel cycle simulation tools.

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JO - Annals of Nuclear Energy

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ER -

Standardized verification of the CYCLUS fuel cycle simulator

Abstract

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Keywords

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