Abstract
Data and functions of the cell burnup calculation of the SRAC system were revised to improve mainly the accuracy of the burnup calculation of high conversion light water reactors (HCLWRs). New burnup chain models were developed in order to treat fission products (FPs) and actinide nuclides in detail. Group cross section library, SRACLIB-JENDL2, was generated based on JENDL-2 nuclear data file. In generating this library, emphasis was placed on FPs and actinides. Also revised were the data such as the average energy release per fission for various actinides. These improved data were verified by performing the burnup analysis of PWR spent fuels. Some new functions were added to the SRAC system for the convenience to yield macroscopic cross sections used in the core burnup process. (author).
Akie, Hiroshi;
Okumura, Keisuke;
Takano, Hideki;
Ishiguro, Yukio;
[1]
Kaneko, Kunio
- Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Citation Formats
Akie, Hiroshi, Okumura, Keisuke, Takano, Hideki, Ishiguro, Yukio, and Kaneko, Kunio.
Improvements on burnup chain model and group cross section library in the SRAC system.
Japan: N. p.,
1992.
Web.
Akie, Hiroshi, Okumura, Keisuke, Takano, Hideki, Ishiguro, Yukio, & Kaneko, Kunio.
Improvements on burnup chain model and group cross section library in the SRAC system.
Japan.
Akie, Hiroshi, Okumura, Keisuke, Takano, Hideki, Ishiguro, Yukio, and Kaneko, Kunio.
1992.
"Improvements on burnup chain model and group cross section library in the SRAC system."
Japan.
@misc{etde_10150910,
title = {Improvements on burnup chain model and group cross section library in the SRAC system}
author = {Akie, Hiroshi, Okumura, Keisuke, Takano, Hideki, Ishiguro, Yukio, and Kaneko, Kunio}
abstractNote = {Data and functions of the cell burnup calculation of the SRAC system were revised to improve mainly the accuracy of the burnup calculation of high conversion light water reactors (HCLWRs). New burnup chain models were developed in order to treat fission products (FPs) and actinide nuclides in detail. Group cross section library, SRACLIB-JENDL2, was generated based on JENDL-2 nuclear data file. In generating this library, emphasis was placed on FPs and actinides. Also revised were the data such as the average energy release per fission for various actinides. These improved data were verified by performing the burnup analysis of PWR spent fuels. Some new functions were added to the SRAC system for the convenience to yield macroscopic cross sections used in the core burnup process. (author).}
place = {Japan}
year = {1992}
month = {Jan}
}
title = {Improvements on burnup chain model and group cross section library in the SRAC system}
author = {Akie, Hiroshi, Okumura, Keisuke, Takano, Hideki, Ishiguro, Yukio, and Kaneko, Kunio}
abstractNote = {Data and functions of the cell burnup calculation of the SRAC system were revised to improve mainly the accuracy of the burnup calculation of high conversion light water reactors (HCLWRs). New burnup chain models were developed in order to treat fission products (FPs) and actinide nuclides in detail. Group cross section library, SRACLIB-JENDL2, was generated based on JENDL-2 nuclear data file. In generating this library, emphasis was placed on FPs and actinides. Also revised were the data such as the average energy release per fission for various actinides. These improved data were verified by performing the burnup analysis of PWR spent fuels. Some new functions were added to the SRAC system for the convenience to yield macroscopic cross sections used in the core burnup process. (author).}
place = {Japan}
year = {1992}
month = {Jan}
}