0

Full Content is available to subscribers

Subscribe/Learn More  >

Development and Verification of Multi-Group Cross Section Process Code TXMAT for Fast Reactor RBEC-M Analysis

[+] Author Affiliations
Ruomeng Qiu, Xubo Ma, Qian Xu, Jiayi Liu, Yixue Chen

North China Electric Power University, Beijing, China

Paper No. ICONE25-66550, pp. V003T02A015; 7 pages
doi:10.1115/ICONE25-66550
From:
  • 2017 25th International Conference on Nuclear Engineering
  • Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application
  • Shanghai, China, July 2–6, 2017
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5781-6
  • Copyright © 2017 by ASME

abstract

In order to generate cross sections for fast reactor calculation, a code named TXMAT based on object–oriented programming and allocate memory technology has been developed. It has the capability to generate macroscopic cross sections for transport or diffusion calculation and microscopic cross sections for burnup calculation, and can also deal with the ultrafine group cross sections (more than 2000 groups and P5 Legendre order) which TRANSX 2.15 can’t do. It works together with a generalized cross section data library called MATXS to give the transport code users easier access to appropriate nuclear data and capabilities which are difficult or impossible to get with any other systems. The TXMAT can handle the shielding effects of many isotopes through background cross section iteration. Several critical benchmarks are calculated. It is shown that the total cross section, absorption cross section, fission neutron spectrum and zero Legendre scattering matrix have been verified using TRANSX 2.15, and the maximum relative difference for the main groups is less than 0.2%. After the critical benchmark calculation, the RBEC-M benchmark is used for the whole core calculation. It is shown that the effective multiplication factor of the calculation is consistent with that of other codes, and the power distribution is also in good agreement with that of other codes except for the blankets. The maximum relative difference of the power distribution among core-1, core-2 and core-3 regions is less than 2.3%. But in the blankets the relative error is about 33%, which may be caused by the difference of the weight function between IWT = 8 and real model. Further analysis will be performed in the future.

Copyright © 2017 by ASME

Figures

Tables

Interactive Graphics

Video

Country-Specific Mortality and Growth Failure in Infancy and Yound Children and Association With Material Stature

Use interactive graphics and maps to view and sort country-specific infant and early dhildhood mortality and growth failure data and their association with maternal

NOTE:
Citing articles are presented as examples only. In non-demo SCM6 implementation, integration with CrossRef’s "Cited By" API will populate this tab (http://www.crossref.org/citedby.html).

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In