Research Article
BibTex RIS Cite

INVESTIGATION OF NEUTRONIC AND THERMAL-HYDRAULIC PERFORMANCE FOR HTR-10 UNDER NORMAL OPERATING CONDITIONS

Year 2003, Volume: 29 Issue: 1-2, 1 - 18, 01.06.2003

Abstract


The VSOP’94 code, obtained from OECD/NEA Data Bank, has been used for the neutronic and thermal-hydraulic prediction calculations for the initial core ioading of the HTR-10 reactor. In the neutronic aspect of this study, double heterogeneity for the fuel element, buckling feedback in the spectrum calculation, and mixture of graphite and fuel balls are taken into account. The results, compared to a relevant study based on the first criticality experiment of HTR-10, indicate that relative errors for the multiplication factor are less than 1.34%, being in a reasonable range.

In the thermal-hydraulic analysis, the power distribution obtained from the neutronic calculations is used where temperature and flow distributions are calculated for the reactor core. During the calculations, conservative hydraulics and physics parameters, such as minimum mass flow rates in the core, no radiation heat transfer in the axial direction, are used. The calculated maximum fuel centerline temperature is 927.4°C for normal operating conditions and observed not to exceed the safety limit.





 





References

  • Teuchert E., Haas K.A., et al., 1994, VSOP-Computer code system for Reactor Physics and Fuel cycle Simulation. JÜLİCH.
  • Wolf L, Scherer W., et al., 1990, High temperature reactor core physics and reactor dynamics. Nucl. Eng. Des. 121,227-240.
  • IAEA-CRP, 2000, Evaluation of High Temperature Gas Cooled reactor performance- Physics benchmark results.
  • Xingqing J„ Xiaolin X., et al., 2002, Prediction calculations and experiments for the first criticality of the 10 MW High Temperature Gas Cooled Reactor-Test Module. Nucl. Eng. Des. 218, 43-49. Turkish Journal of Nuclear Sciences
  • KT.A Standards, 3102.1 (1978), 3102.2 (1933), 3102.3 (1981), 3102.4 (1984), 3102.5 (1986)
  • Zuying Gao, Lei Shi, 2002, Thermal hydraulic calculation of the HTR-10 for the initial and equilibrium core. Nucl. Eng. Des. 218, 51-64.

NORMAL ÇALIŞMA KOŞULLARINDA HTR-10 İÇİN NEUTRONIC VE TERMAL-HİDROLİK PERFORMANSIN İNCELENMESİ

Year 2003, Volume: 29 Issue: 1-2, 1 - 18, 01.06.2003

Abstract



OECD Veri Bankasından temin edilen VSOP’94 bilgisayar
programı kullanılarak HTR-10 reaktörünün ilk kor yüklemesine ait nötronik ve
ısıl- akışkan hesaplamaları gerçekleştirilmiştir. Çalışmanın nötronik kısmında,
yakıt elemanları için çift heterojenlik, şpektrum hesaplamalarında akı-büküm
geri beslemesi, grafit ve yakıt toplarının homojen karışımı göz önüne
alınmıştır. Nötronik hesaplamalar, HTR-10’nun ilk kritiklik hesaplama
sonuçlarını içeren başka bir çalışma ile karşılaştırılmıştır. Analizin
sonucunda, çoğalma faktöründeki göreli hataların, makul sınırlarda (maksimum
%1.34’den düşük) olduğu gözlenmiştir.



Isı-akışkan hesaplamalarda, nötronik hesaplamalarda elde
edilen güç dağılım profilleri kullanılmıştır. Bu analizde basınç kabı
içerisindeki sıcaklık ve akışkan dağılımları hesaplanmıştır. Hesaplamalarda,
kordan minimum akış oranının geçirilmesi, eksensel yönde radyasyonel ısı
aktarımının olmaması vb. gibi tutucu kabuller yapılmıştır. Normal işletme
koşulları için, maksimum yakıt merkez sıcaklığı 927.4°C olarak hesaplanmıştır.
Bu değerin normal işletme ve kaza koşulları için belirlenen sınır olan 1230
°C’nin altında kaldığı görülmüştür.




References

  • Teuchert E., Haas K.A., et al., 1994, VSOP-Computer code system for Reactor Physics and Fuel cycle Simulation. JÜLİCH.
  • Wolf L, Scherer W., et al., 1990, High temperature reactor core physics and reactor dynamics. Nucl. Eng. Des. 121,227-240.
  • IAEA-CRP, 2000, Evaluation of High Temperature Gas Cooled reactor performance- Physics benchmark results.
  • Xingqing J„ Xiaolin X., et al., 2002, Prediction calculations and experiments for the first criticality of the 10 MW High Temperature Gas Cooled Reactor-Test Module. Nucl. Eng. Des. 218, 43-49. Turkish Journal of Nuclear Sciences
  • KT.A Standards, 3102.1 (1978), 3102.2 (1933), 3102.3 (1981), 3102.4 (1984), 3102.5 (1986)
  • Zuying Gao, Lei Shi, 2002, Thermal hydraulic calculation of the HTR-10 for the initial and equilibrium core. Nucl. Eng. Des. 218, 51-64.
There are 6 citations in total.

Details

Primary Language English
Subjects Metrology, Applied and Industrial Physics
Journal Section Articles
Authors

Serhat Köse This is me

İhsan Kılıç This is me

Publication Date June 1, 2003
Published in Issue Year 2003 Volume: 29 Issue: 1-2

Cite

APA Köse, S., & Kılıç, İ. (2003). INVESTIGATION OF NEUTRONIC AND THERMAL-HYDRAULIC PERFORMANCE FOR HTR-10 UNDER NORMAL OPERATING CONDITIONS. Turkish Journal of Nuclear Sciences, 29(1-2), 1-18.
AMA Köse S, Kılıç İ. INVESTIGATION OF NEUTRONIC AND THERMAL-HYDRAULIC PERFORMANCE FOR HTR-10 UNDER NORMAL OPERATING CONDITIONS. Turkish Journal of Nuclear Sciences. December 2003;29(1-2):1-18.
Chicago Köse, Serhat, and İhsan Kılıç. “INVESTIGATION OF NEUTRONIC AND THERMAL-HYDRAULIC PERFORMANCE FOR HTR-10 UNDER NORMAL OPERATING CONDITIONS”. Turkish Journal of Nuclear Sciences 29, no. 1-2 (December 2003): 1-18.
EndNote Köse S, Kılıç İ (December 1, 2003) INVESTIGATION OF NEUTRONIC AND THERMAL-HYDRAULIC PERFORMANCE FOR HTR-10 UNDER NORMAL OPERATING CONDITIONS. Turkish Journal of Nuclear Sciences 29 1-2 1–18.
IEEE S. Köse and İ. Kılıç, “INVESTIGATION OF NEUTRONIC AND THERMAL-HYDRAULIC PERFORMANCE FOR HTR-10 UNDER NORMAL OPERATING CONDITIONS”, Turkish Journal of Nuclear Sciences, vol. 29, no. 1-2, pp. 1–18, 2003.
ISNAD Köse, Serhat - Kılıç, İhsan. “INVESTIGATION OF NEUTRONIC AND THERMAL-HYDRAULIC PERFORMANCE FOR HTR-10 UNDER NORMAL OPERATING CONDITIONS”. Turkish Journal of Nuclear Sciences 29/1-2 (December 2003), 1-18.
JAMA Köse S, Kılıç İ. INVESTIGATION OF NEUTRONIC AND THERMAL-HYDRAULIC PERFORMANCE FOR HTR-10 UNDER NORMAL OPERATING CONDITIONS. Turkish Journal of Nuclear Sciences. 2003;29:1–18.
MLA Köse, Serhat and İhsan Kılıç. “INVESTIGATION OF NEUTRONIC AND THERMAL-HYDRAULIC PERFORMANCE FOR HTR-10 UNDER NORMAL OPERATING CONDITIONS”. Turkish Journal of Nuclear Sciences, vol. 29, no. 1-2, 2003, pp. 1-18.
Vancouver Köse S, Kılıç İ. INVESTIGATION OF NEUTRONIC AND THERMAL-HYDRAULIC PERFORMANCE FOR HTR-10 UNDER NORMAL OPERATING CONDITIONS. Turkish Journal of Nuclear Sciences. 2003;29(1-2):1-18.