Program - Brookhaven National Laboratory
Program - Brookhaven National Laboratory
Program - Brookhaven National Laboratory
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Sodium-cooled fast neutron reactor ASTRID is currently under design and development in France. Traditional<br />
ECCO/ERANOS fast reactor code system using for ASTRID core design calculations lies only on<br />
multi-group JEFF-3.1.1 data library. To gauge the use of ENDF/B-VII.0 and JEFF-3.1.1 nuclear data<br />
libraries in the fast reactor applications, in this study two recent OECD/NEA computational benchmarks<br />
specified by Argonne <strong>National</strong> <strong>Laboratory</strong> have been calculated. Using the continuous-energy TRIPOLI-4<br />
Monte Carlo transport code, both ABR-1000 MWth oxyde (MOX) core and metallic (U-Pu) core have<br />
been investigated. Under two different fast neutron spectra and two data libraries, ENDF/B-VII.0 and<br />
JEFF-3.1.1, the reactivity impact studies have been performed. With the JEFF-3.1.1 data library under<br />
the BOEC (Beginning of equilibrium cycle) condition, higher reactivity effects of 750 pcm and 1080 pcm<br />
have been observed for ABR-1000 MOX core and metallic core respectively. To study the causes of these<br />
differences in reactivity, several TRIPOLI-4 runs using mixed data libraries feature allow us to identify the<br />
nuclides and the nuclear data accounting for the major part of the observed reactivity differences. This<br />
work was supported by EDF and AREVA.<br />
[1] T. K. Kim, W. S. Yang, C. Grandy and R. N. Hill, Core Design Studies for a 1000 MWth Advanced<br />
Burner Reactor, Annals of Nuclear Energy 36, p. 331 (2009). [2] Y. K. Lee, TRIPOLI-4 Criticality Calculations<br />
for MOX Fulled SNEAK 7A and 7B Fast Critical Assemblies, Physor 2012, Knoxville, TN. USA,<br />
April 15-20, 2012.<br />
HE 3 4:20 PM<br />
Nuclear Data and the Oklo Natural Nuclear Reactors<br />
C. R. Gould<br />
North Carolina State University and Triangle Universities Nuclear <strong>Laboratory</strong><br />
A. A. Sonzogni<br />
<strong>National</strong> Nuclear Data Center, <strong>Brookhaven</strong> <strong>National</strong> <strong>Laboratory</strong><br />
E. I. Sharapov<br />
Joint Institute for Nuclear Research, Dubna<br />
Recent years have seen a renewed interest in the Oklo phenomenon, particularly in relation to the study<br />
of time variation of the fine structure constant α where Oklo data lead at present to the most precise<br />
terrestrial bounds. Nuclear data are essential to these analyses, but not all are known to the required<br />
precision. We summarize our recent work on Oklo and time variation of fundamental constants, and<br />
highlight 175 Lu neutron capture as one area where improved cross section measurements could lead to<br />
more precise bounds on the operating temperatures of the Oklo reactors. We also comment on γ-ray<br />
fluxes in Oklo, and on 138 La as an independent measure of neutron fluences in the reactors. This work<br />
was supported by the US Department of Energy, Office of Nuclear Physics, under Grant No. DE-FG02-<br />
97ER41041 (NC State University), and under contract No. DE-AC02-98CH10886 with <strong>Brookhaven</strong> Science<br />
Associates (NNDC).<br />
HE 4 4:40 PM<br />
Identification of Energy Regions for Maximising the Fertile-To-Fissile Conversion in<br />
Thorium Fuel Cycles Using Point-Wise Energy Cross Sections in an Actinide Depletion<br />
Code<br />
Anek Kumar, S. Ganesan, Umasankari Kannan and P. D. Krishnani<br />
Reactor Physics Design Division, Bhabha Atomic Research centre, Mumbai, India<br />
127
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