Leakage-corrected fast reactor assembly calculation with Monte-Carlo code and its validation methodology

Cai Li

doi:10.11884/HPLPB201830.170254

Volume 30 Issue 2

Feb. 2018

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Cai Li. Leakage-corrected fast reactor assembly calculation with Monte-Carlo code and its validation methodology[J]. High Power Laser and Particle Beams, 2018, 30: 026005. doi: 10.11884/HPLPB201830.170254

Citation:

Cai Li. Leakage-corrected fast reactor assembly calculation with Monte-Carlo code and its validation methodology[J]. High Power Laser and Particle Beams, 2018, 30: 026005. doi: 10.11884/HPLPB201830.170254

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Leakage-corrected fast reactor assembly calculation with Monte-Carlo code and its validation methodology

doi: 10.11884/HPLPB201830.170254

Cai Li

China Nuclear Power Technology Research Institute Co Ltd, Shenzhen 518031, China

Received Date: 2017-06-21
Rev Recd Date: 2017-10-17
Publish Date: 2018-02-15

Abstract

Abstract

A leakage model based on B1 homogeneous equations has been implemented in continuous-energy Monte Carlo code TRIPOLI4. This leakage model algorithm iterates between the point-wise Monte Carlo simulation and a B1 homogeneous equation solver till reaching a final critical state in Monte Carlo simulation. The two advantages of our leakage model compared with the others are: we use critical flux spectrum to generate the multi-group constants for solving the B1 homogeneous equation; the leakage coefficients calculated are considered in point-wise Monte Carlo simulation. This leakage model is validated by a pre-designed numerical experiment simulated with continuous-energy TRIPOLI4 and the results obtained by this leakage model are proved to be more accurate by comparison with those from SERPENT leakage model and deterministic leakage model in ECCO code.
- leakage model,
- critical buckling,
- cross section

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References(7)

References

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