Multi-group cross section for new group structure using weightiung spectrum for sodium cooled fast reactor

Muhammad Sohail; Myung Hyun Kim

doi:10.1109/PGSRET.2015.7312196

Multi-group cross section for new group structure using weightiung spectrum for sodium cooled fast reactor

Muhammad Sohail
, Myung Hyun Kim

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

Abstract

The cross section data is the primary requirement to carry-out multi-group calculations for nuclear reactor design and analysis. The multi-group cross section data library is generated for a Multipurpose Experimental Sodium Cooled Fast Reactor (MESOF). A specific flux weighting spectra is used for point averaging the cross section obtained from Evaluated Nuclear Data Files (ENDF/B-VII.0). A new group structure is formed and well-known established procedure for nuclear data processing is adopted. The multi-group calculations are performed using diffusion and transport theory based codes for sodium cooled fast reactor with new and existing multi-group data libraries. The calculations have shown improved results for multiplication factor.

Original language	English
Title of host publication	2015 Power Generation Systems and Renewable Energy Technologies, PGSRET 2015
Publisher	Institute of Electrical and Electronics Engineers Inc.
ISBN (Electronic)	9781467368124
DOIs	https://doi.org/10.1109/PGSRET.2015.7312196
Publication status	Published - 28 Oct 2015
Event	2nd International Conference on Power Generation Systems and Renewable Energy Technologies, PGSRET 2015 - Islamabad, Pakistan Duration: 10 Jun 2015 → 11 Jun 2015

Publication series

Name	2015 Power Generation Systems and Renewable Energy Technologies, PGSRET 2015

Conference

Conference	2nd International Conference on Power Generation Systems and Renewable Energy Technologies, PGSRET 2015
Country/Territory	Pakistan
City	Islamabad
Period	10/06/15 → 11/06/15

Bibliographical note

Publisher Copyright:
© 2015 IEEE.

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

SDG 7 Affordable and Clean Energy

Keywords

Neutron Flux Spectra
Nuclear Cross section Data
Sodium Cooled Fast Reactor

Access to Document

10.1109/PGSRET.2015.7312196

Cite this

Sohail, M., & Kim, M. H. (2015). Multi-group cross section for new group structure using weightiung spectrum for sodium cooled fast reactor. In 2015 Power Generation Systems and Renewable Energy Technologies, PGSRET 2015 Article 7312196 (2015 Power Generation Systems and Renewable Energy Technologies, PGSRET 2015). Institute of Electrical and Electronics Engineers Inc.. https://doi.org/10.1109/PGSRET.2015.7312196

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title = "Multi-group cross section for new group structure using weightiung spectrum for sodium cooled fast reactor",

abstract = "The cross section data is the primary requirement to carry-out multi-group calculations for nuclear reactor design and analysis. The multi-group cross section data library is generated for a Multipurpose Experimental Sodium Cooled Fast Reactor (MESOF). A specific flux weighting spectra is used for point averaging the cross section obtained from Evaluated Nuclear Data Files (ENDF/B-VII.0). A new group structure is formed and well-known established procedure for nuclear data processing is adopted. The multi-group calculations are performed using diffusion and transport theory based codes for sodium cooled fast reactor with new and existing multi-group data libraries. The calculations have shown improved results for multiplication factor.",

keywords = "Neutron Flux Spectra, Nuclear Cross section Data, Sodium Cooled Fast Reactor",

author = "Muhammad Sohail and Kim, \{Myung Hyun\}",

note = "Publisher Copyright: {\textcopyright} 2015 IEEE.; 2nd International Conference on Power Generation Systems and Renewable Energy Technologies, PGSRET 2015 ; Conference date: 10-06-2015 Through 11-06-2015",

year = "2015",

month = oct,

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doi = "10.1109/PGSRET.2015.7312196",

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Sohail, M & Kim, MH 2015, Multi-group cross section for new group structure using weightiung spectrum for sodium cooled fast reactor. in 2015 Power Generation Systems and Renewable Energy Technologies, PGSRET 2015., 7312196, 2015 Power Generation Systems and Renewable Energy Technologies, PGSRET 2015, Institute of Electrical and Electronics Engineers Inc., 2nd International Conference on Power Generation Systems and Renewable Energy Technologies, PGSRET 2015, Islamabad, Pakistan, 10/06/15. https://doi.org/10.1109/PGSRET.2015.7312196

Multi-group cross section for new group structure using weightiung spectrum for sodium cooled fast reactor. / Sohail, Muhammad; Kim, Myung Hyun.
2015 Power Generation Systems and Renewable Energy Technologies, PGSRET 2015. Institute of Electrical and Electronics Engineers Inc., 2015. 7312196 (2015 Power Generation Systems and Renewable Energy Technologies, PGSRET 2015).

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

TY - GEN

T1 - Multi-group cross section for new group structure using weightiung spectrum for sodium cooled fast reactor

AU - Sohail, Muhammad

AU - Kim, Myung Hyun

PY - 2015/10/28

Y1 - 2015/10/28

N2 - The cross section data is the primary requirement to carry-out multi-group calculations for nuclear reactor design and analysis. The multi-group cross section data library is generated for a Multipurpose Experimental Sodium Cooled Fast Reactor (MESOF). A specific flux weighting spectra is used for point averaging the cross section obtained from Evaluated Nuclear Data Files (ENDF/B-VII.0). A new group structure is formed and well-known established procedure for nuclear data processing is adopted. The multi-group calculations are performed using diffusion and transport theory based codes for sodium cooled fast reactor with new and existing multi-group data libraries. The calculations have shown improved results for multiplication factor.

AB - The cross section data is the primary requirement to carry-out multi-group calculations for nuclear reactor design and analysis. The multi-group cross section data library is generated for a Multipurpose Experimental Sodium Cooled Fast Reactor (MESOF). A specific flux weighting spectra is used for point averaging the cross section obtained from Evaluated Nuclear Data Files (ENDF/B-VII.0). A new group structure is formed and well-known established procedure for nuclear data processing is adopted. The multi-group calculations are performed using diffusion and transport theory based codes for sodium cooled fast reactor with new and existing multi-group data libraries. The calculations have shown improved results for multiplication factor.

KW - Neutron Flux Spectra

KW - Nuclear Cross section Data

KW - Sodium Cooled Fast Reactor

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U2 - 10.1109/PGSRET.2015.7312196

DO - 10.1109/PGSRET.2015.7312196

M3 - Conference contribution

AN - SCOPUS:84962374982

T3 - 2015 Power Generation Systems and Renewable Energy Technologies, PGSRET 2015

BT - 2015 Power Generation Systems and Renewable Energy Technologies, PGSRET 2015

PB - Institute of Electrical and Electronics Engineers Inc.

T2 - 2nd International Conference on Power Generation Systems and Renewable Energy Technologies, PGSRET 2015

Y2 - 10 June 2015 through 11 June 2015

ER -

Sohail M, Kim MH. Multi-group cross section for new group structure using weightiung spectrum for sodium cooled fast reactor. In 2015 Power Generation Systems and Renewable Energy Technologies, PGSRET 2015. Institute of Electrical and Electronics Engineers Inc. 2015. 7312196. (2015 Power Generation Systems and Renewable Energy Technologies, PGSRET 2015). doi: 10.1109/PGSRET.2015.7312196

Multi-group cross section for new group structure using weightiung spectrum for sodium cooled fast reactor

Abstract

Publication series

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Bibliographical note

UN SDGs

Keywords

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