Study On Pebble-Bed HTR Reactor Calculation With Several Options Of Fuel Matrix Designs

STUDY ON PEBBLE-BED HTR REACTOR CALCULATION WITH SEVERAL OPTIONS OF FUEL MATRIX DESIGNS

Zuhair dan Suwoto
Pusat Teknologi Reaktor dan Keselamatan Nuklir – BATAN

ABSTRACT
STUDY ON PEBBLE-BED HTR REACTOR CALCULATION WITH SEVERAL OPTIONS OF FUEL MATRIX DESIGNS. Pebble-bed HTR core is able to acomodate various types of fuel without significant core modification. This paper presents study of calculation of pebble-bed HTR core with three options of fuel matrix designs: UO2 (8.2% U235 enrichment), PuO2 (53.85% Pu239 enrichment) and ThO2/UO2 (7.47% U233 enrichment). Core calculation includes cell calculation using infinite array model of pebble-bed fuel with reflective boundary and full core calculation uses cylindrical model (2-D R-Z) with 300 cm in diameter and 943 cm in height. All computations are carried out using Monte Carlo transport code MCNP5 at temperature of 293.6 K and 1000 K. In general, MCNP5 calculations indicate consistency with k_inf and k_eff values of UO2 core which always almost higher than those of PuO2 and ThO2/UO2 cores. Compared to the other Monte Carlo simulation show that MCNP5 produces the value of k_inf which is closer to that obtained by MCNP-4B than that obtained by MONK9 with the computation bias less than 1.3%. The MCNP5's k_eff calculation reflect a close tendency to that achieved by MCNP-4B, KENO-V.a, and MONK9, however, its computation bias is relatively high compared to the TRIPOLI4, especially for reactor core with PuO2. It can be concluded that MCNP5 estimations exist in the range of all Monte Carlo calculation codes and are expected to be the most precision if the experimental data found later.

Keywords: HTR pebble-bed, fuel, MCNP5, ENDF/B-VI
Published : Prosiding Seminar Nasional Ke-15 "TEKNOLOGI DAN KESELAMATAN PLTN SERTA FASILITAS NUKLIR", Surakarta, 17 Oktober 2009

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BORON DILUTION IN THE PRIMARY COOLANT INFLUENCE TO THE FUEL CHARACTERISTIC OF PIUS REACTOR

BORON DILUTION IN THE PRIMARY COOLANT INFLUENCE TO THE FUEL CHARACTERISTIC OF PIUS REACTOR
Ign. Djoko Irianto
Center for Nuclear Technology Assessment - BATAN
Email: igndjoko@batan.go.id
ABSTRACT
BORON DILUTION IN THE PRIMARY COOLANT INFLUENCE TO THE FUEL CHARACTERISTIC OF PIUS REACTOR. The influence of boron dilution in the primary coolant to the fuel characteristic of Pressurized Water Reactor (PWR) have been studied as a preliminary study of fuel characteristic of Process Inherent Ultimate Safety (PIUS) reactor. The focus of study are fuel bundle with several enrichment of U-235 from 2.4% until 3.4% using boron dilution concentration in the primary coolant are 150 ppm and 200 ppm. The calculation result of the fuel bundle which is set as a matrix of 17x17 element and the dimension is 30.294 cm x 30.294 cm using WIMS-D4 personal computer (PC) version, shows that the value of infinite multiplication factor of the fuel bundle which 2.4% enrichment in the primary coolant with 200 ppm boron concentration is 1.01672. In general, it is concluded that the fuel bundle which enrichment of 2.4% and the concentration of boron dilution of 200 ppm, the PIUS reactor could be achieve the critical or could be able to start up.

Keywords : Boron Dilution, Primary Coolant, Fuel Characteristic, WIMS-D4, Start Up Reactor.
Published : Journal "Pengkajian Sains dan Teknologi Nuklir", Vol.3, No.1, 1998, Pusat Pengkajian Teknologi Nuklir, BATAN, ISSN No. : 0852-8047

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