Calculation of damage, He and H production using SPECTER
This document explains the procedure to compute gas production in fuel and structural materials using SPECTER from neutronics calculations provided by J. Latkowski using MCNP. The gas production cross sections (four channels are considered: (n, {sub 1}{sup 1,2,3}H) and (n,{sub 2}{sup 4}He)) for each isotope are taken from the cross-section library ENDF/B-V (we refer the reader to the SPECTER manual for more details). Therein, one can see flux data from, approximately, 0 (BOL) to 50 (EOL) years (cut after 7 columns for clarity). In order to compute damage and gas production with SPECTER, one needs to provide the flux group data expressed in a maximum of 100 energy groups (a SPECTER requirement). The flux data structure provided by J. Latkowski using MCNP consists of 616 groups spanning the 10{sup -9} < E < 20 MeV energy range. The first thing that needs to be done is to collapse these data into a format consisting of 100 groups suitable for SPECTER. As we can see, our (arbitrarily chosen) group structure covers the same energy range as the flux data from MCNP. A simple code (multgrp.c) has been written using the C programming language to do the collapse. This code only requires the desired output group structure as input (just shown above), and the flux data from MCNP. Note that the input flux group structure (from MCNP) can be any, as the code is not limited to the specific one of 616 groups used by Latkowski et al.
- Research Organization:
- Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 965461
- Report Number(s):
- LLNL-TR-416495; TRN: US200922%%451
- Country of Publication:
- United States
- Language:
- English
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