### Abstract

This manuscript focuses on the UNIC code, which is being developed to provide high fidelity solutions of the neutron transport equation in the fast reactor program of the Global Nuclear Energy Partnership. At present, we have developed three solvers for the neutron transport code: PN2ND, SN2ND, and MOCFE. PN2ND is based upon the second-order even-parity transport equation where spherical harmonics are utilized for the angular approximation. SN2ND is also based upon the second-order even-parity transport equation where a discrete ordinates approximation is utilized for the angular approximation. This manuscript discusses the motivations behind creating the PN2ND and SN2ND solvers along with their targeted applications. We also discuss the current performance of the two solvers and present some benchmark results. MOCFE is the first-order method of characteristics solver, which is focused on providing the capability of treating the explicit geometrical problems - a long term goal of this project. We give a summary of the status of this solver and have included a companion paper to provide more details.

Original language | English |
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Title of host publication | American Nuclear Society - International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009 |

Pages | 80-97 |

Number of pages | 18 |

Volume | 1 |

Publication status | Published - 2009 |

Externally published | Yes |

Event | International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009 - Saratoga Springs, NY, United States Duration: 3 May 2009 → 7 May 2009 |

### Other

Other | International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009 |
---|---|

Country | United States |

City | Saratoga Springs, NY |

Period | 3/5/09 → 7/5/09 |

### Fingerprint

### Keywords

- Discrete ordinates
- MOC
- Neutron transport

### ASJC Scopus subject areas

- Nuclear Energy and Engineering
- Computational Mathematics
- Nuclear and High Energy Physics

### Cite this

*American Nuclear Society - International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009*(Vol. 1, pp. 80-97)

**Recent research progress on UNIC at Argonne national laboratory.** / Smith, Micheal A.; Kaushik, Dinesh; Wollaber, Allan; Yang, Won Sik; Smith, Barry; Rabiti, Cristian; Palmiotti, Giuseppe.

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution

*American Nuclear Society - International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009.*vol. 1, pp. 80-97, International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009, Saratoga Springs, NY, United States, 3/5/09.

}

TY - GEN

T1 - Recent research progress on UNIC at Argonne national laboratory

AU - Smith, Micheal A.

AU - Kaushik, Dinesh

AU - Wollaber, Allan

AU - Yang, Won Sik

AU - Smith, Barry

AU - Rabiti, Cristian

AU - Palmiotti, Giuseppe

PY - 2009

Y1 - 2009

N2 - This manuscript focuses on the UNIC code, which is being developed to provide high fidelity solutions of the neutron transport equation in the fast reactor program of the Global Nuclear Energy Partnership. At present, we have developed three solvers for the neutron transport code: PN2ND, SN2ND, and MOCFE. PN2ND is based upon the second-order even-parity transport equation where spherical harmonics are utilized for the angular approximation. SN2ND is also based upon the second-order even-parity transport equation where a discrete ordinates approximation is utilized for the angular approximation. This manuscript discusses the motivations behind creating the PN2ND and SN2ND solvers along with their targeted applications. We also discuss the current performance of the two solvers and present some benchmark results. MOCFE is the first-order method of characteristics solver, which is focused on providing the capability of treating the explicit geometrical problems - a long term goal of this project. We give a summary of the status of this solver and have included a companion paper to provide more details.

AB - This manuscript focuses on the UNIC code, which is being developed to provide high fidelity solutions of the neutron transport equation in the fast reactor program of the Global Nuclear Energy Partnership. At present, we have developed three solvers for the neutron transport code: PN2ND, SN2ND, and MOCFE. PN2ND is based upon the second-order even-parity transport equation where spherical harmonics are utilized for the angular approximation. SN2ND is also based upon the second-order even-parity transport equation where a discrete ordinates approximation is utilized for the angular approximation. This manuscript discusses the motivations behind creating the PN2ND and SN2ND solvers along with their targeted applications. We also discuss the current performance of the two solvers and present some benchmark results. MOCFE is the first-order method of characteristics solver, which is focused on providing the capability of treating the explicit geometrical problems - a long term goal of this project. We give a summary of the status of this solver and have included a companion paper to provide more details.

KW - Discrete ordinates

KW - MOC

KW - Neutron transport

UR - http://www.scopus.com/inward/record.url?scp=74549182658&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=74549182658&partnerID=8YFLogxK

M3 - Conference contribution

AN - SCOPUS:74549182658

SN - 9781615673490

VL - 1

SP - 80

EP - 97

BT - American Nuclear Society - International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009

ER -