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SUMMARY:Benchmark Comparisons of Deterministic\, Monte Carlo and Finite El
 ement Methods for 3D Reactor Physics Modeling of Reduced-Moderation Water 
 Reactor  - Syed Bahauddin Alam (University of Cambridge)
DTSTART:20130820T100000Z
DTEND:20130820T110000Z
UID:TALK105958@talks.cam.ac.uk
CONTACT:Syed Bahauddin Alam
DESCRIPTION:The Reduced-Moderation Water Reactor (RMWR) is an innovative w
 ater-cooled reactor with some of the characteristics of a fast neutron rea
 ctor\, which can achieve a high conversion ratio of more than 1.0 and a ne
 gative void reactivity coefficient. The conception of RMWR is built on est
 ablished Boiling Water Reactor (BWR) technology and is being researched by
  the Japan Atomic Energy Agency (JAEA) and Hitachi. \n\nThe current method
 s of 2D modeling are not sufficient and 3D Monte Carlo codes are slow due 
 to the need to generate data for a full core axially heterogeneous RMWR mo
 del. These drawbacks severely limit the modeling capability of the RMWR. T
 he objective is to observe the differences within the 3D deterministic rou
 te to see whether it can be used more efficiently as an alternative to the
  3D Monte Carlo in order to achieve reasonable accuracy. 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 sui
 table for the axially heterogeneous RMWR core configuration. Cross-section
 s generated with 2D lattice calculations will also be insufficient for the
  full core modeling of such reactors. That is because neutron net current 
 at the boundary of each zone is assumed to be zero in the 2D modeling whil
 e in fact\, neutrons of different energies will leak from adjacent zones. 
 That is why 3D modeling of an RMWR is necessary. \n\nTherefore\, the aim o
 f the project is to study the 3D reactor physics modeling of an RMWR fuel 
 assembly and compare the results using three computational codes: WIMS\, M
 ONK and EVENT. It is worth addressing that Deterministic code WIMS and Mon
 te Carlo code MONK are the reactor physics software package developed by t
 he ANSWERS Software Service. In addition\, EVENT (Even-parity Neutral part
 icle Transport) is developed by the Applied Mechanics and Computation Grou
 p in Imperial College London and it can solve the multi-group\, steady-sta
 te and time-dependent self-adjoint second-order transport equation using t
 he finite element-spherical harmonics approximation.\n\nTwo sets of fuels:
  Pu-UO2 and Th-UO2 have been studied for this project. The comparison amon
 g the three codes have been carried out with 1D axial slab\, 3D lattice an
 d 3D pincell models of an RMWR fuel assembly model. Three sets of cross-se
 ction are used in comparison: (i) P0 scatter with total cross section\, (i
 i) P0 scatter with transport cross section and a corrected self-scatter cr
 oss section and (iii) P1 scatter with total cross section. The solution of
  the multiplication factor\, neutron flux and yield in energy are compared
  using 172-group cross-sections using 2D equivalence theory in WIMS and wi
 th cross-sections that have been condensed to 12-group by the use of 2D tr
 ansport calculations. Therefore\, two sets of cross-sections with P0 scatt
 ering for WIMS and both P1 and P0 scattering for MONK were used for the co
 mparison of results for the slab\, pincell and lattice models with both 17
 2-group and 12-group.\n\nThis talk will present the research findings of t
 his project.
LOCATION: Cambridge University Engineering Department LR6
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