UNIVERSITY OF BUCHAREST
FACULTY OF PHYSICS

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2024-11-24 22:11

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Conference: Bucharest University Faculty of Physics 2010 Meeting


Section: Applied Nuclear Physics


Title:
Comparative results for benchmark test problems in heavy water lattices


Authors:
Aioanei Corina (1)


Affiliation:
(1) Institute for Nuclear Research Pitesti, Romania


E-mail
corina.aioanei@nuclear.ro


Keywords:
HEAVY WATER lattice cell, benchmark problem, WIMS


Abstract:
The paper presents comparative results for the main types of lattice cell calculation performed by using WIMS code, WIMSD5B version. The lattice cell calculations main goal is to obtain the optimal input parameters combination that gives closer results to IAEA measurements. The comparison was made for IAEA benchmark problems applied to heavy water lattices with same sets of configurations. IAEA nuclear data libraries updated in WLUP (WIMS Libraries Updates Project) project were used. The input data have been set from test problems description. The comparisons have been performed for the following heavy water cell configuration (contains D2O both as coolant and moderator): (a) Th5-HW-AECL-ZED2 Analysis of lattice experiments with 19 fuel rod clusters (1/6/12) with ThO2–UO2 fuel. Measurements were made on single pitch 28 cm hexagonal ThO2 fuel containing 1.5 wt% enriched UO2 (93.02 at.% U235), fuel rod diameter 1.153 cm, rod centres radius 0.0/1.468/2.837 cm, fuel material density 9.33 g/cm2, clad material zircaloy 2, sheath material density 6.55 g/cm2, temperature 294.8K (all components); (b) UO2-HW-AECL-ZED2 Analysis of experiments with 37 fuel rod clusters (1/6/12/18). Measurements were made on single pitch 28.58 cm square UO2 fuel, fuel rod diameter 1.21 cm, rod centres radius 0.0/1.4885/2.8755/4.3305 cm, fuel material density 10.50 g/cm2, clad material zircaloy 4, sheath material density 6.55 g/cm2, temperature 294.8K (all components); (c) Th3–HW-BNL-bnl_thd2o1. These benchmarks are eight D2O moderated subcritical lattices of 3% 233UO2–97% ThO2 rods in hexagonal patterns, fuel rod diameter 1.092 cm, fuel material density 8.9618g/cm2, clad material zircaloy 2, sheath material density 6.8365g/cm2, temperature 293 K (all components), lattice pitch 2.170 cm. Lattice calculations were done in order to observe which combination gave the closer results to IAEA measurements for effective multiplication constant keff, average fission and neutron flux spectra corresponding to 69 and 172 energy group libraries.