Development of continuous-energy sensitivity analysis capability in OpenMC
© 2017 Elsevier Ltd The iterated fission probability (IFP) method and the Contributon-Linked eigenvalue sensitivity/Uncertainty estimation via Track length importance CHaracterization (CLUTCH) method have been implemented in several Monte Carlo codes to perform sensitivity calculations. In this work...
| Main Authors: | , , , , |
|---|---|
| Other Authors: | |
| Format: | Article |
| Language: | English |
| Published: |
Elsevier BV
2022
|
| Online Access: | https://hdl.handle.net/1721.1/135719.2 |
| _version_ | 1811083559227621376 |
|---|---|
| author | Peng, Xingjie Liang, Jingang Alhajri, Abdulla Abdulaziz Forget, Benoit Robert Yves Smith, Kord S. |
| author2 | Massachusetts Institute of Technology. Department of Nuclear Science and Engineering |
| author_facet | Massachusetts Institute of Technology. Department of Nuclear Science and Engineering Peng, Xingjie Liang, Jingang Alhajri, Abdulla Abdulaziz Forget, Benoit Robert Yves Smith, Kord S. |
| author_sort | Peng, Xingjie |
| collection | MIT |
| description | © 2017 Elsevier Ltd The iterated fission probability (IFP) method and the Contributon-Linked eigenvalue sensitivity/Uncertainty estimation via Track length importance CHaracterization (CLUTCH) method have been implemented in several Monte Carlo codes to perform sensitivity calculations. In this work the unified adjoint and generalized adjoint calculation framework combining the IFP method and the CLUTCH method is proposed, and corresponding capabilities for calculating nuclear data sensitivity to the effective multipilication factor and reaction rate ratios are implemented in OpenMC. Results are presented on Godiva, Jezebel and a PWR fuel pin system which demonstrate that OpenMC results agree well with reference direct perturbation sensitivity coefficients. In addition, two main problems of the IFP method related to the number of latent generations, namely convergence and statistical fluctuations are investigated theoretically and numerically. This paper further demonstrates that the fission matrix approach is better suited to generate the adjoint and generalized adjoint source distribution in the CLUTCH method to overcome the drawbacks of the IFP method. |
| first_indexed | 2024-09-23T12:34:59Z |
| format | Article |
| id | mit-1721.1/135719.2 |
| institution | Massachusetts Institute of Technology |
| language | English |
| last_indexed | 2024-09-23T12:34:59Z |
| publishDate | 2022 |
| publisher | Elsevier BV |
| record_format | dspace |
| spelling | mit-1721.1/135719.22022-07-12T18:33:02Z Development of continuous-energy sensitivity analysis capability in OpenMC Peng, Xingjie Liang, Jingang Alhajri, Abdulla Abdulaziz Forget, Benoit Robert Yves Smith, Kord S. Massachusetts Institute of Technology. Department of Nuclear Science and Engineering © 2017 Elsevier Ltd The iterated fission probability (IFP) method and the Contributon-Linked eigenvalue sensitivity/Uncertainty estimation via Track length importance CHaracterization (CLUTCH) method have been implemented in several Monte Carlo codes to perform sensitivity calculations. In this work the unified adjoint and generalized adjoint calculation framework combining the IFP method and the CLUTCH method is proposed, and corresponding capabilities for calculating nuclear data sensitivity to the effective multipilication factor and reaction rate ratios are implemented in OpenMC. Results are presented on Godiva, Jezebel and a PWR fuel pin system which demonstrate that OpenMC results agree well with reference direct perturbation sensitivity coefficients. In addition, two main problems of the IFP method related to the number of latent generations, namely convergence and statistical fluctuations are investigated theoretically and numerically. This paper further demonstrates that the fission matrix approach is better suited to generate the adjoint and generalized adjoint source distribution in the CLUTCH method to overcome the drawbacks of the IFP method. 2022-07-12T18:33:01Z 2021-10-27T20:28:59Z 2022-07-12T18:33:01Z 2017 2019-09-24T16:01:16Z Article http://purl.org/eprint/type/JournalArticle https://hdl.handle.net/1721.1/135719.2 en 10.1016/J.ANUCENE.2017.06.061 Annals of Nuclear Energy Creative Commons Attribution-NonCommercial-NoDerivs License http://creativecommons.org/licenses/by-nc-nd/4.0/ application/octet-stream Elsevier BV Prof. Forget via Chris Sherratt |
| spellingShingle | Peng, Xingjie Liang, Jingang Alhajri, Abdulla Abdulaziz Forget, Benoit Robert Yves Smith, Kord S. Development of continuous-energy sensitivity analysis capability in OpenMC |
| title | Development of continuous-energy sensitivity analysis capability in OpenMC |
| title_full | Development of continuous-energy sensitivity analysis capability in OpenMC |
| title_fullStr | Development of continuous-energy sensitivity analysis capability in OpenMC |
| title_full_unstemmed | Development of continuous-energy sensitivity analysis capability in OpenMC |
| title_short | Development of continuous-energy sensitivity analysis capability in OpenMC |
| title_sort | development of continuous energy sensitivity analysis capability in openmc |
| url | https://hdl.handle.net/1721.1/135719.2 |
| work_keys_str_mv | AT pengxingjie developmentofcontinuousenergysensitivityanalysiscapabilityinopenmc AT liangjingang developmentofcontinuousenergysensitivityanalysiscapabilityinopenmc AT alhajriabdullaabdulaziz developmentofcontinuousenergysensitivityanalysiscapabilityinopenmc AT forgetbenoitrobertyves developmentofcontinuousenergysensitivityanalysiscapabilityinopenmc AT smithkords developmentofcontinuousenergysensitivityanalysiscapabilityinopenmc |