INDC(IND)-35G - IAEA Nuclear Data Services

Analysis of ZPR-9 Assembly 31. the Advanced Fuels Program
Carbide Benchmark Critical Assembly
(s.Ganesan, M.M.Ramanadhan and V.Gopalakrishnan)
The analysis of the 10001itre (core) sized carbide
benchmark fast reactor assembly using the RRC non adjusted
multigroup set and the adjusted French 1969 set shows nc
surprising results as compared to ovr predictional capability
for oxide cores* The results for central worths, compare
very veil with those reported by U.S. teas using ENDF/B-XV
Set and also show that non adjusted set maynot be satisfactory
in the prediction of central worths of materials. On
the other hand Kftff is best predicted by the non adjusted
EHDF/B-IV based RRC set and the ratio of fission reaction
rates are predicted to the same extent by the two sets
available at RRC.
Based on our pro.; ?tt analysis the following conclusions
and recommendations are drawn:-
1. Our attempts of writing our own nuclear data processing
code system RAMBHA and the generation of non adjusted
ENDF/B-IV based RRC multigroup datausing RAMBHA and its
validation have been quite successful.
The Keff for the carbide benchmark critical
assembly is well predicted by the non adjusted ENDF/B-IV
based RRC multigroup set.
2. The over predictions of central worths by non adjusted
RRC and US sets are more, compared to the over prediction
by the adjusted French set, for most of the element*.
Special attention should be given to
reducing the over prediction of central worths of various
elements in future with stress on improving the status
for structural elements.
3. The non adjusted ENDF/B-IV based RRC set is superior, as