LAVENDER: A steady-state core analysis code for design studies of accelerator driven subcritical reactors

Abstract Accelerator driven subcritical reactors (ADSRs) have been proposed and widely investigated for the transmutation of transuranics (TRUs). ADSRs have several special characteristics, such as the subcritical core driven by spallation neutrons, anisotropic neutron flux distribution and complex geometry etc. These bring up requirements for development or extension of analysis codes to perform design studies. A code system named LAVENDER has been developed in this paper. It couples the modules for spallation target simulation and subcritical core analysis. The neutron transport-depletion calculation scheme is used based on the homogenized cross section from assembly calculations. A three-dimensional S N nodal transport code based on triangular-z meshes is employed and a multi-channel thermal-hydraulics analysis model is integrated. In the depletion calculation, the evolution of isotopic composition in the core is evaluated using the transmutation trajectory analysis algorithm (TTA) and fine depletion chains. The new code is verified by several benchmarks and code-to-code comparisons. Numerical results indicate that LAVENDER is reliable and efficient to be applied for the steady-state analysis and reactor core design of ADSRs.

[1]  Takakazu Takizuka,et al.  Code development for the design study of the OMEGA Program accelerator-driven transmutation systems , 2001 .

[2]  A. Ferrari,et al.  FLUKA: A Multi-Particle Transport Code , 2005 .

[3]  Alexander Stanculescu,et al.  Accelerator Driven Systems (ADSs) for nuclear transmutation , 2013 .

[4]  Naoto Aizawa,et al.  Comparison of different neutronics analysis technique for Accelerator-Driven System , 2013 .

[5]  Per Seltborg,et al.  Source efficiency and high-energy neutronics in accelerator-driven systems , 2005 .

[6]  K. F. Raskach,et al.  Effective algorithm for calculation of a subcritical reactor with an external source , 1998 .

[7]  Xiaofeng Jiang,et al.  Transport-burnup code systems and their applications for IAEA ADS benchmark , 2004 .

[8]  Yousry Gohar,et al.  MCNPX, MONK, and ERANOS analyses of the YALINA Booster subcritical assembly , 2011 .

[9]  A. V. Zhukov,et al.  Heat transfer to liquid metals in regular arrays of fuel elements , 1978 .

[10]  Pavel Hejzlar,et al.  MCODE, Version 2.2: An MCNP-ORIGEN DEpletion Program , 2008 .

[11]  Youqi Zheng,et al.  Study on Improvement of Analytic Depletion Calculation Method , 2013 .

[12]  Hongchun Wu,et al.  A nodal SN transport method for three-dimensional triangular-z geometry , 2007 .

[13]  M. Salvatores,et al.  Radioactive waste partitioning and transmutation within advanced fuel cycles: Achievements and Challenges , 2011 .

[14]  Russian Federation,et al.  BN-600 HYBRID CORE BENCHMARK ANALYSES , 2002 .