THE EFFECTS OF VARIATIONS IN LITHIUM (7Li) AND URANIUM (235U) ISOTOPE LEVELS ON A SMALL FLUORIDE SALT-COOLED, HIGH-TEMPERATURE REACTOR WITH UO2 FUEL PINS

  • Hassan Mohamed, Dr. Centre for Nuclear Energy, College of Engineering, Universiti Tenaga Nasional, 43000 Kajang, Selangor, Malaysia.
  • Geoffrey T. Parks, Dr. University of Cambridge, United Kingdom
Keywords: FLiBe, 7Li2BeF4, fluoride salt, lithium enrichment, high-temperature reactor, FHR

Abstract

Abstract

Lithium beryllium fluoride, FLiBe (66.7 mole % LiF and 33.3 mole % BeF2) has become the baseline coolant for fluoride salt-cooled high-temperature reactors (FHRs). Natural lithium contains 92.5% 7Li and 7.5% 6Li. The presence of 6Li can present challenges as it is an unfavourably strong neutron absorber. Hence, the objective of this study is to perform sensitivity analysis on 7Li enrichment in order to better understand the effects on neutronic performance, multiplication factor and coolant temperature coefficient of reactivity (TCR), for a pin-type fuel assembly in a small FHR. The calculations carried out for this study use the WIMS infinite lattice code and a UO2 pin-type fuel assembly design. The first case is performed at 19.75 wt.% 235U enrichment while the 7Li enrichment is varied over seven different values, namely 100%, 99.999%, 99.995%, 99.99%, 99.9%, 99.1% and 99.0%. Second test is performed at 7 wt.% 235U and the 7Li enrichment is only varied over six values, namely 100%, 99.999%, 99.995%, 99.99%, 99.9% and 99.1%. Additional variation of the 7Li enrichment is unnecessary because the system becomes subcritical when the 7Li enrichment is at 99.1% or lower. Results show that the neutronic performance is not only affected by the 7Li enrichment, but also sensitive to the UO2 fuel enrichment, especially at lower fuel enrichments. For 19.75 wt.% UO2, the reactivity is incremented by 11 pcm while the coolant TCR is improved by 0.013 pcm for every 0.001% increase in 7Li enrichment. On the other hand, for 7 wt.% UO2, the reactivity is incremented by 35 pcm and the coolant TCR is improved by 0.014 pcm for every 0.001% increase in 7Li enrichment.

 

Abstrak

Litium berilium fluorida, FLiBe (66.7 mole% LiF dan 33.3 mole% BeF2) telah menjadi penyejuk asas bagi reaktor suhu tinggi yang disejukkan dengan garam fluorida (FHRs). Litium semulajadi mengandungi 92.5% 7Li dan 7.5% 6Li. Kehadiran 6Li dapat menimbulkan cabaran kerana penyerap neutron yang tidak baik. Oleh yang demikian, objektif kajian ini adalah untuk melakukan analisis kepekaan terhadap pengayaan 7Li untuk lebih memahami kesan ke atas prestasi neutron, faktor pendaraban dan koefisien kefaktor reaktiviti suhu (TCR) untuk pemasangan bahan pin-pin dalam FHR yang kecil. Pengiraan yang dilakukan untuk kajian ini menggunakan kod kekisi WIMS tak terhingga dan reka bentuk perhimpunan bahan api pin-UO2. Kes pertama dilakukan pada pengayaan 19.75 wt.% 235U manakala pengayaan 7Li bervariasi dalam tujuh nilai yang berbeza iaitu 100%, 99.999%, 99.995%, 99.99%, 99.9%, 99.1% dan 99.0%. Ujian kedua dilakukan pada 7 wt.% 235U dan pengayaan 7Li hanya bervariasi daripada enam nilai iaitu 100%, 99.999%, 99.995%, 99.99%, 99.9% dan 99.1%. Perubahan tambahan pengayaan 7Li tidak perlu kerana sistem menjadi subkritis apabila pengayaan 7Li berada pada 99.1% atau lebih rendah. Keputusan menunjukkan bahawa prestasi neutron tidak hanya dipengaruhi oleh pengayaan 7Li, tetapi juga sensitif terhadap pengayaan bahan bakar UO2, terutama pada pengayaan bahan bakar yang lebih rendah. Untuk 19.75 wt.% UO2, kereaktifan meningkat sebanyak 11 pcm manakala TCR penyejuk diperbaiki dengan 0.013 pcm untuk setiap peningkatan 0.001% dalam pengayaan 7Li. Sebaliknya, untuk 7% berat UO2, kereaktifan meningkat sebanyak 35 pcm dan penyejuk TCR meningkat sebanyak 0.014 pcm untuk setiap peningkatan 0.001% dalam pengayaan 7Li.

Author Biographies

Hassan Mohamed, Dr., Centre for Nuclear Energy, College of Engineering, Universiti Tenaga Nasional, 43000 Kajang, Selangor, Malaysia.

Senior Lecturer

Geoffrey T. Parks, Dr., University of Cambridge, United Kingdom

Principal Lecturer

Published
2017-06-30
How to Cite
Mohamed, H., & Parks, G. T. (2017). THE EFFECTS OF VARIATIONS IN LITHIUM (7Li) AND URANIUM (235U) ISOTOPE LEVELS ON A SMALL FLUORIDE SALT-COOLED, HIGH-TEMPERATURE REACTOR WITH UO2 FUEL PINS. JOURNAL of NUCLEAR and Related TECHNOLOGIES, 14(1), 27-36. Retrieved from https://jnrtmns.net/index.php/jnrt/article/view/6
Section
Articles