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CATEGORIES:CamTalk
SUMMARY:Benchmark Comparisons of Deterministic\, Monte Car
lo and Finite Element Methods for 3D Reactor Physi
cs Modeling of Reduced-Moderation Water Reactor -
Syed Bahauddin Alam (University of Cambridge)
DTSTART;TZID=Europe/London:20130820T110000
DTEND;TZID=Europe/London:20130820T120000
UID:TALK105958AThttp://talks.cam.ac.uk
URL:http://talks.cam.ac.uk/talk/index/105958
DESCRIPTION:The Reduced-Moderation Water Reactor (RMWR) is an
innovative water-cooled reactor with some of the c
haracteristics of a fast neutron reactor\, which c
an achieve a high conversion ratio of more than 1.
0 and a negative void reactivity coefficient. The
conception of RMWR is built on established Boiling
Water Reactor (BWR) technology and is being resea
rched by the Japan Atomic Energy Agency (JAEA) and
Hitachi. \n\nThe current methods of 2D modeling a
re not sufficient and 3D Monte Carlo codes are slo
w due to the need to generate data for a full core
axially heterogeneous RMWR model. These drawbacks
severely limit the modeling capability of the RMW
R. The objective is to observe the differences wit
hin the 3D deterministic route to see whether it c
an be used more efficiently as an alternative to t
he 3D Monte Carlo in order to achieve reasonable a
ccuracy. The 2D few-group cross-section generation
methodology will be insufficient for the full cor
e modeling of such reactors. Although 2D modeling
is quick\, it is not suitable for the axially hete
rogeneous RMWR core configuration. Cross-sections
generated with 2D lattice calculations will also b
e insufficient for the full core modeling of such
reactors. That is because neutron net current at t
he boundary of each zone is assumed to be zero in
the 2D modeling while in fact\, neutrons of differ
ent energies will leak from adjacent zones. That i
s why 3D modeling of an RMWR is necessary. \n\nThe
refore\, the aim of the project is to study the 3D
reactor physics modeling of an RMWR fuel assembly
and compare the results using three computational
codes: WIMS\, MONK and EVENT. It is worth address
ing that Deterministic code WIMS and Monte Carlo c
ode MONK are the reactor physics software package
developed by the ANSWERS Software Service. In addi
tion\, EVENT (Even-parity Neutral particle Transpo
rt) is developed by the Applied Mechanics and Comp
utation Group in Imperial College London and it ca
n solve the multi-group\, steady-state and time-de
pendent self-adjoint second-order transport equati
on using the finite element-spherical harmonics ap
proximation.\n\nTwo sets of fuels: Pu-UO2 and Th-U
O2 have been studied for this project. The compari
son among the three codes have been carried out wi
th 1D axial slab\, 3D lattice and 3D pincell model
s of an RMWR fuel assembly model. Three sets of cr
oss-section are used in comparison: (i) P0 scatter
with total cross section\, (ii) P0 scatter with t
ransport cross section and a corrected self-scatte
r cross section and (iii) P1 scatter with total cr
oss section. The solution of the multiplication fa
ctor\, neutron flux and yield in energy are compar
ed using 172-group cross-sections using 2D equival
ence theory in WIMS and with cross-sections that h
ave been condensed to 12-group by the use of 2D tr
ansport calculations. Therefore\, two sets of cros
s-sections with P0 scattering for WIMS and both P1
and P0 scattering for MONK were used for the comp
arison of results for the slab\, pincell and latti
ce models with both 172-group and 12-group.\n\nThi
s talk will present the research findings of this
project.
LOCATION: Cambridge University Engineering Department LR6
CONTACT:Syed Bahauddin Alam
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