CRITICALITY ANALYSIS OF URANIUM STORAGE FACILITY WITH FORMATION RACKS

Authors

  • Sri Kuntjoro Center for Technology and Nuclear Reactor Safety - BATAN

DOI:

https://doi.org/10.17146/tdm.2017.19.1.3251

Keywords:

criticality, uranium storage facility, k-eff

Abstract

Uranium materials are needed for the uranium fuel production of research reactors and radioisotope. Before the uranium material is used, it is stored in the storage facility. One of the prerequisites for uranium material storage facilities is that it must be in the sub-critical condition. The purpose of this study is to analyze the criticality condition of uranium material storage facility located in PT. Inuki (Persero) and to ensure that the criticality condition is always in sub-critical state. Criticality analysis was performed using MCNP-5 program to determine the level of criticality of the three uranium material storage facilities at initial conditions and conditions after adding the storage racks. For analysing storage facilities 1 and 2, three scenarios of container on the storage rack formations were considered. Meanwhile, for analysing the storage facility 3, one scenario was considered. The results confirm that all strorages at initial condition and after adding storage racks formation were still in sub-critical condition (k-eff<1). These results are then used as the basis for the uranium materials management. It is also used as a basis for issuing an operational license by the nuclear energy regulatory body (BAPETEN).

References

X-5 Monte Carlo Team MCNP - A General Monte Carlo N-Particle Transport Code, Version 5. Los Alamos Nuclear Laboratory. Los Alamos - USA: 2005.

Kastanya D. Critical mass calculations using MCNP: An academic exercise. Ann. Nucl. Energy. 2015. 75:228-231.

https://doi.org/10.1016/j.anucene.2014.08.041

Alloni D., Borio Di Tigliole A., Cammi A., Chiesa D., Clemenza M., Magrotti G., et al. Final characterization of the first critical configuration for the TRIGA Mark II reactor of the University of Pavia using the Monte Carlo code MCNP. Prog. Nucl. Energy. 2014. 74:129-135.

https://doi.org/10.1016/j.pnucene.2014.02.022

Robinson M.L., DeBey T.M., Higginbotham J.F. Benchmarking criticality analysis of TRIGA fuel storage racks. Appl. Radiat. Isot. 2017. 119:16-22.

https://doi.org/10.1016/j.apradiso.2016.08.019

Wang M.-J., Sheu R.-J., Peir J.-J., Liang J.-H. Criticality calculations of the HTR-10 pebble-bed reactor with SCALE6/CSAS6 and MCNP5. Ann. Nucl. Energy. 2014. 64:1-7.

https://doi.org/10.1016/j.anucene.2013.09.031

Wang M.-J., Peir J.-J., Sheu R.-J., Liang J.-H. Effects of geometry homogenization on the HTR-10 criticality calculations. Nucl. Eng. Des. 2014. 271:356-360.

https://doi.org/10.1016/j.nucengdes.2013.11.062

Setiawati E., Oktajianto H., Richardina V., Endro S J. Analysis loading height of HTR (High Temperature Reactor) core to obtain criticality of reactor. Int. J. Sci. Eng. 2015. 9:113-116.

Oktajianto H., Setiawati E., Richardina V. Modelling of HTR (High Temperature Reactor) Pebble-Bed 10 MW to determine criticality as a variations of enrichment and radius of the Fuel (Kernel) with the Monte Carlo code MCNP4C. Int. J. Sci. Eng. 2015. 8:42-46.

Ho H.Q., Honda Y., Goto M., Takada S. Numerical investigation of the Random Arrangement Effect of coated fuel particles on the Criticality of HTTR fuel compact using MCNP6. Ann. Nucl. Energy. 2017. 103:114-121.

https://doi.org/10.1016/j.anucene.2017.01.026

Zuhair, Suwoto, Irianto I.D. Pemodelan teras untuk analisis perhitungan konstanta multiplikasi reaktor HTR-PROTEUS. Tri Dasa Mega. 2010. 12(2):91-102.

Sudarmono, Suwoto, Hery A. Sensitivitas pengayaan dan fraksi packing partikel triso dalam bahan bakar Pebble terhadap k-inf sebagai dasar disain konseptual RGTT200K. J. Ilmu Daur Bahan Bakar Nuklir URANIA. 2013. 19:25-38.

Odoi H.C., Akaho E.H.K., Jonah S.A., Abrefah R.G., Ibrahim V.Y., Al E.T. Study of criticality safety and neutronic Performance for a 348-Fuel-Pin Ghana Research Reactor 1 LEU core using MCNP code. World J. Nucl. Sci. Technol. 2014. 4:46-52.

https://doi.org/10.4236/wjnst.2014.41008

Mosteller R. Comparison of ENDF / B-VII . 1 and ENDF / B-VII . 0 results for the expanded criticality validation suite for MCNP and for selected additional criticality benchmarks. Nucl. Data Sheets. 2014. 118:442-445.

https://doi.org/10.1016/j.nds.2014.04.101

Zerovnik G., Podvratnik M., Snoj L. On normalization of fluxes and reaction rate in MCNP criticality calculation. Ann. Nucl. Energy. 2014. 63:126-128.

https://doi.org/10.1016/j.anucene.2013.07.045

Hughes C.R., Pelaez O., Schubring D., Jordan K.A. Multi-physics analysis of a supercritical water reactor with improved MCNP modeling. Nucl. Eng. Des. 2014. 270:412-420.

https://doi.org/10.1016/j.nucengdes.2014.01.018

NUKEM GMBH, Basic and Detail Engineering Process - element fabrication plan for Badan Tenaga Atom Nasional - NUKEM VT-No 2.008, HANAU, Germany, 1983

Downloads

Published

2017-02-11

How to Cite

Kuntjoro, S. (2017). CRITICALITY ANALYSIS OF URANIUM STORAGE FACILITY WITH FORMATION RACKS. Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega, 19(1), 41–54. https://doi.org/10.17146/tdm.2017.19.1.3251