A Reduced-Boron OPR1000 Core Based on the BigT Burnable Absorber

Hwanyeal Yu, Mohd Syukri Yahya, Yonghee Kim

Research output: Contribution to journalArticle

10 Citations (Scopus)

Abstract

Reducing critical boron concentration in a commercial pressurized water reactor core offers many advantages in view of safety and economics. This paper presents a preliminary investigation of a reduced-boron pressurized water reactor core to achieve a clearly negative moderator temperature coefficient at hot zero power using the newly-proposed "Burnable absorber-Integrated Guide Thimble" (BigT) absorbers. The reference core is based on a commercial OPR1000 equilibrium configuration. The reduced-boron ORP1000 configuration was determined by simply replacing commercial gadolinia-based burnable absorbers with the optimized BigT-loaded design. The equilibrium cores in this study were directly searched via repetitive Monte Carlo depletion calculations until convergence. The results demonstrate that, with the same fuel management scheme as in the reference core, application of the BigT absorbers can effectively reduce the critical boron concentration at the beginning of cycle by about 65 ppm. More crucially, the analyses indicate promising potential of the reduced-boron OPR1000 core with the BigT absorbers, as its moderator temperature coefficient at the beginning of cycle is clearly more negative and all other vital neutronic parameters are within practical safety limits. All simulations were completed using the Monte Carlo Serpent code with the ENDF/B-VII.0 library.

Original languageEnglish
Pages (from-to)318-329
Number of pages12
JournalNuclear Engineering and Technology
Volume48
Issue number2
DOIs
Publication statusPublished - 01 Apr 2016

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Boron
Moderators
Reactor cores
Pressurized water reactors
Gadolinium
Temperature
Economics

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

Cite this

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A Reduced-Boron OPR1000 Core Based on the BigT Burnable Absorber. / Yu, Hwanyeal; Yahya, Mohd Syukri; Kim, Yonghee.

In: Nuclear Engineering and Technology, Vol. 48, No. 2, 01.04.2016, p. 318-329.

Research output: Contribution to journalArticle

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