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Examination and Improvement of SHEM multigroup energy structure

Examination and Improvement of SHEM multigroup energy structure. Tholakele P. Ngeleka Radiation and Reactor Theory, Necsa , RSA Ivanov Kostadin , Levine Samuel Department of Nuclear Engineering, PSU, USA. Post-Graduates conference, iThemba Labs, Cape Town, August 11 – 14, 2013. layout.

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Examination and Improvement of SHEM multigroup energy structure

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  1. Examination and Improvement of SHEM multigroupenergy structure TholakeleP. Ngeleka Radiation and Reactor Theory, Necsa, RSA IvanovKostadin, Levine Samuel Department of Nuclear Engineering, PSU, USA Post-Graduates conference, iThemba Labs, Cape Town, August 11 – 14, 2013

  2. layout • Introduction • Unit cells • Computational Tools • Method • Conclusions • References

  3. Introduction • Fine energy group structures allow accurate calculation of neutron cross sections for reactor analysis • SHEM energy group structures were developed for LWRs • Addressed the materials in fuel component and structural material found in LWRs • Important nuclides were addressed in such that their resonances are covered • However, it was uncertain that they are applicable to HTRs, which are graphite moderated and achieve high burnup, without any further modifications.

  4. Introduction Figure 1: Hydrogen and carbon cross sections (t2.lanl.gov)

  5. Introduction Figure 2: Unresolved resonances for U-235 and U-238 (t2.lanl.gov)

  6. Unit cells • Two types of fuel: • Prismatic hexagonal blocks are used for GFR and VHTR • Pebble sphere fuel element (FE) used in PBR • Both Prismatic block and pebble FE consist of TRISO coated particles, embedded in a graphite matrix

  7. Unit cells Pebble 15000 CP in each pebble sphere It has 5 cm diameter fuel zone and 6 cm outer diameter Figure 3: Pebble FE model

  8. Unit cells Prismatic 3000 CP in each cylinder Fuel channel diameter :1.27 cm Coolant channel diameter: 1.588 cm Figure 4: Prismatic block model

  9. Computational Tools • Dragon - deterministic code • Capabilities of calculating angular flux and adjoint flux • Adjoint flux allow the computation of importance function for each energy group which is used to improve the energy group structure

  10. Method • Contributonand Point-Wise Cross Section Driven method developed at PennState • It is an iterative method that selects effective fine and broad energy group structures for the problem of interest (1)

  11. Method • The procedure for the group structure improvement is as follows: • An initial multi-group energy structure was selected (SHEM-281 or 361) • Cross sections were generated for the initial multi-group energy structure • The angular and adjoint flux calculations were performed to determine the importance function • After identifying the energy groups with higher importance, this energy group structure was improved by dividing the energy group into two or more energy groups

  12. Method • When the improvement process was complete for all energy groups, the new energy group structure was used for cross section generation • The new cross section library was used to calculate the reaction rates and k-effective • The reaction rates and k-effective are calculated using the new library are compared with the results obtained from the previous library analysis • If the results are within a specified tolerance, the procedure ends; otherwise, previous steps are repeated until the specified tolerance is achieved (1% deviation of reaction rate and 10pcm relative deviation of dk/k)

  13. Results Fig. 5: Importance function for fast energy region Fig. 6: Importance function for epithermal energy region

  14. Results Fig. 7: Importance function for thermal energy region Table 1: Reaction rates (281 and 407 energy group structures)

  15. Results • SHEM-281 SHEM_TPN-407 • SHEM-361 SHEM_TPN-531 • SHEM energy group structures can be used for HTR analysis Table 2: Reaction rates (361 and 531 energy group structures)

  16. References • Ngeleka, T.P., 2012. Examination and improvements of energy group structures for HTR and HTR design analysis, PhD Thesis, The Pennsylvania State University, USA. • Alpan, F. A., and Haghighat, A., 2005. Development of the CPXSD methodology for generation of fine-group libraries for shielding applications, Nuclear Science and Engineering, 149. 51-64. • Kriangchairporn, N., 2006. Transport Model based on 3D cross section generation for TRIGA core analysis, PhD Thesis, The Pennsylvania State University, USA.

  17. Thank you

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