Published June 2016 | Version v1
Journal article

Reaction rate tally and depletion calculation with on-the-fly temperature treatment

  • 1. Department of Engineering Physics, Tsinghua University, Beijing 100084 (China)
  • 2. Department of Reactor Core Design, Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233 (China)

Description

Highlights: • TMS was developed in RMC based on ray tracking for on-the-fly Doppler-broadening. • On-the-fly interpolation was developed for bound nuclides in thermal energy region. • TMS method was applied to reaction rate tally to consider temperature feedback. • On-the-fly temperature treatment was applied to MC depletion in the first time. • RMC is capable of transport-burnup-thermal-hydraulics coupling for thermal reactors. - Abstract: Monte Carlo method can provide high fidelity neutronic analyses of different types of nuclear reactors, because of its advantages of the flexible geometry modeling and the use of continuous-energy nuclear cross sections. MC codes can also couple with depletion solver and thermal-hydraulics codes simultaneously for the "transport-burnup-thermal-hydraulics" coupled calculations. In this paper, the target motion sampling (TMS) method was developed in RMC code to consider the Doppler broadening effect in resolved resonance energy region, and the on-the-fly interpolation of thermal scattering data was developed to consider the thermal scattering and bound effect in the thermal energy region. Moreover, TMS method was applied to reaction rate tally and depletion calculation for power generation feedback and nuclide density evolutions. This is the first time that a Monte Carlo code is developed for on-the-fly temperature treatment in MC depletion calculations. The results show that TMS method and on-the-fly interpolation of thermal scattering have high efficiency and accuracy in the cases of PWR assembly calculation. With TMS method, the reaction rate can be tallied with temperature feedback. Temperature feedback in each burnup step can also be considered, allowing for the high fidelity "transport-burnup-thermal-hydraulics" coupled calculation.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.anucene.2016.02.006

Additional details

Identifiers

DOI
10.1016/j.anucene.2016.02.006;
PII
S0306-4549(16)30068-8;

Publishing Information

Journal Title
Annals of Nuclear Energy (Oxford)
Journal Volume
92
Journal Page Range
p. 277-283
ISSN
0306-4549
CODEN
ANENDJ

Optional Information

Copyright
Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.