ANALYSES OF FUEL BURNUP CALCULATIONS OF KARTINI REACTOR BASED ON THE NEW CALCULATION SCHEME

Tegas Sutondo

DOI: http://dx.doi.org/10.17146/gnd.2014.17.2.2801

Sari


ABSTRACT

ANALYSES OF FUEL BURNUP CALCULATIONS OF KARTINI REACTOR BASED ON THE NEW CALCULATION SCHEME. It has been described a new scheme of fuel burnup calculation, intended to improve the present practice used at Kartini reactor. The improvement includes the use of power distributions, which will be used as the base for estimating the burnup of each individual fuel element, and the inclusion of epithermal neutron which will affect to the burnup rates and the total fuel consumed. A small computation program was then made to perform calculations based on the two calculation schemes, and to see the differences. The results indicate that the proposed scheme results in higher estimated value against that of the present scheme, and the differences tends to increase linearly with the cumulative burnups. For each cumulative burnup of 30 MWD the difference could reach about 9.87 % which is around 3.7 gram for the whole core. It can be concluded that the proposed approach could improve the present’s practice of burnup estimation, especially for each individual fuel element which is important to the in-core fuel management program.

Kata Kunci


Analyses, Nuclear fuel, Burn up, Calculations, Kartini Reactor, Scheme.

Teks Lengkap:

PDF

Referensi


REFERENCES

HDBK-1019/1-93, DOE FUNDAMENTALS HANDBOOK NUCLEAR PHYSICS AND REACTOR THEORY, Volume 1, U.S. Department of Energy. FSC-6910, JANUARY 1993. http://www.steamtablesonline.com/pdf/Nuclear-Volume1.pdf

TRIGA REACTOR CHARACTERISTICS, IAEA Education and Training, Nuclear Installation Safety Division of the IAEA, updated on 18 May 2005,

http://ansn.iaea.org/Common/documents/Training/

S.F. MUGHABGHAB, Atlas of Neutron Resonances, National Nuclear Data Center, Brookhaven National Laboratory, Published by Elsevier Science, April 17, 2006, http://www.nndc.bnl.gov/atlas/atlasvalues.html

THE ACCOUNTANCY OF NUCLEAR MATERIALS FOR MBA RI-B, Center for Accelerator and material Process Technology, National Nuclear Energy Agency of Indonesia, Report period June 07, 2011 – May 09, 2014

PUTRANTO ILHAM YAZID, “TRIGA-MCNP”, version 9, January 2006.

SAFETY ANALYSES REPORT OF KARTINI REACTOR, revision 7, Document No: C7/05/B2/LAK/2012, Center for Accelerator and Material Process Technology, National Nuclear Energy of Indonesia (BATAN)

Denise B. Pelowitz, MCNPXTM USER’S MANUAL, Version 2.6.0, LA-CP-07-1473, April 2008


Refbacks

  • Saat ini tidak ada refbacks.


##submission.copyrightStatement##

##submission.license.cc.by-nc-sa4.footer##