A TIME-DEPENDENT SOLVER FOR COUPLED NEUTRON-TRANSPORT THERMAL-MECHANICS CALCULATIONS AND SIMULATION OF A GODIVA PROMPT-CRITICAL BURST

被引:0
作者
Fiorina, Carlo [1 ]
Aufiero, Manuele [2 ]
Pelloni, Sandro [1 ]
Mikityuk, Konstantin [1 ]
机构
[1] Paul Scherrer Inst, Villigen, Switzerland
[2] Politecn Milan, I-20133 Milan, Italy
来源
PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 4 | 2014年
关键词
CODE SYSTEM;
D O I
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中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
The present paper describes a first step taken at the Paul Scherrer Institut in the development of a new multi-physics platform for reactor analysis. Such platform is based on the finite-volume software OpenFOAM and aims at a tightly coupled description of neutron transport, thermal mechanics and fluid dynamics. For this purpose, a steady-state 3-D discrete ordinates/thermal-mechanics solver was first developed in collaboration with the Politecnico di Milano. The present work briefly discusses such solver and its preliminary validation, which will be described in detail in parallel publications. It then focuses on its extension to time-dependent simulations. The solver is first tested by simulating different step-wise reactivity insertions in a critical configuration constituted by an infinite slab of highly enriched uranium. Subsequently, a super-prompt-critical power burst in the Godiva reactor has been simulated. Godiva was a spherical assembly of highly enriched uranium built and operated at the Los Alamos National Laboratory (US) during the Fifties. A prompt-critical transient in such system configures as a quick power excursion (up to similar to 10 GW), which causes a temperature rise, and a subsequent reactivity reduction via expansion of the sphere. The overall transient lasts for few fractions of a millisecond. Results obtained with the newly developed model have been compared to experimental results, showing a relatively good agreement.
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共 15 条
  • [1] Aufiero M., 2014, THESIS
  • [2] Aufiero M., 2014, 2 FRONT COMP PHYS C
  • [3] Analysis of selected Phenix EOL tests with the FAST code system - Part II: Unprotected phase of the Natural Convection Test
    Chenu, A.
    Mikityuk, K.
    Chawla, R.
    [J]. ANNALS OF NUCLEAR ENERGY, 2012, 49 : 191 - 199
  • [4] Eaton JohnW., 2008, GNU Octave Manual Version 3
  • [5] Hetnarski R.B., 2009, Thermal Stresses-Advanced Theory and Applications
  • [6] HETRICK D. L., 1993, DYNAMICS NUCL REACTO
  • [7] Jarrell J.J., 2011, INT C MATH COMP METH
  • [8] Leppanen J., 2007, THESIS
  • [9] Calculation of effective point kinetics parameters in the Serpent 2 Monte Carlo code
    Leppanen, Jaakko
    Aufiero, Manuele
    Fridman, Emil
    Rachamin, Reuven
    van der Marck, Steven
    [J]. ANNALS OF NUCLEAR ENERGY, 2014, 65 : 272 - 279
  • [10] FAST: An advanced code system for fast reactor transient analysis
    Mikityuk, K
    Pelloni, S
    Coddington, P
    Bubelis, E
    Chawla, R
    [J]. ANNALS OF NUCLEAR ENERGY, 2005, 32 (15) : 1613 - 1631