SANTA: A safety analysis code for neutron absorbers in spent nuclear fuel pools

Kim, Geon; Jung, Yunsong; Lee, Myeongkyu; Yoon, Eisung; Ahn, Sangjoon

doi:10.1016/j.cpc.2022.108513

Cited by 3 publications

(1 citation statement)

References 11 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Additionally, several different coupon thickness reduction assumptions were considered, as a reduced thickness can result in a considerable change in the cumulative 10 B(n, α) 7 Li reactions in coupon peripheries. The simulations were conducted by SANTA [27], a dedicated code for the evaluation of radiation damage and ion distribution in Al-B 4 C MMCs, which was developed by coupling several existing codes, Transport Rigor Implemented with Time-dependent Operation for Neutronic depletion (TRITON), Criticality Safety Analysis Sequence with KENO-VI (CSAS6), and Static and Dynamic Trim for Sequential and Parallel computer (SDTrimSP) [28,29], with proper modifications to reflect the ion emission and geometric characteristics of B 4 C particles.…”

Section: Introductionmentioning

confidence: 99%

Simulation of Radiation Damage and He Accumulation Induced by ¹⁰B(n, α)⁷Li Reactions in Al‐B₄C Neutron Absorbers Used in Spent Fuel Pools

Kim,

Lee,

Jung

et al. 2024

International Journal of Energy Research

Self Cite

View full text Add to dashboard Cite

Faster than expected surface corrosion and a considerable decrease in the 10B areal density of a non-clad Al-B4C neutron absorber were recently reported from surveillance coupons used in a spent fuel pool for about 8 years, which is only approximately one-fifth of the guaranteed service life of the absorber. Such premature degradation was largely attributed to irradiation-assisted corrosion since numerous gas bubbles filled with He and H were discovered in the Al alloy matrix near B4C particles, and naturally 10B(n, α)7Li reactions were designated as the underlying mechanism for the porosification that may have expedited the absorber corrosion. In this study, the levels of radiation damage and He concentration in the micrographs published in recent experimental studies were estimated to design ion beam irradiation experiments having appropriate parameters to emulate the status of neutron-irradiated non-clad Al-B4C absorbers. TRITON, CSAS6, and SDTrimSP were coupled with modifications for the calculation of dpa and He concentration in irradiated neutron absorbers. The simulations yielded 3.74–6.71 dpa and 0.71–1.64 at% of He after 99 months of use and 3.82–8.39 dpa and 0.73–2.08 at% of He after 40 years of use. The simulations also demonstrated that the radiation damage and He concentration have a weak correlation with the particle diameter. In terms of radiation damage, these results are in good agreement with the reported experimental data, indicating that they can be referred to in the experimental design. The calculated He concentrations, however, may warrant modification to include leakage of implanted He atoms through irradiation-induced microcracks in the B4C particles. Because of the high diffusivity of He, full leakage of He from B4C particles to their boundaries with the Al alloy matrix was assumed for further estimations, which revealed that He concentration could be significantly elevated in the Al matrix near B4C particles.

show abstract

Section: Introductionmentioning

confidence: 99%

Simulation of Radiation Damage and He Accumulation Induced by ¹⁰B(n, α)⁷Li Reactions in Al‐B₄C Neutron Absorbers Used in Spent Fuel Pools

Kim,

Lee,

Jung

et al. 2024

International Journal of Energy Research

Self Cite

View full text Add to dashboard Cite

show abstract

Experimental investigation of non-condensable gas effects in a natural circulation system

Jeong,

Hwang,

Kim

et al. 2023

J Mech Sci Technol

View full text Add to dashboard Cite

Experimental emulation of 10B(n, α)7Li reaction-induced microstructural evolution of Al-B4C neutron absorber used in the dry storage of spent nuclear fuel

Ha,

Kim,

Jung

et al. 2024

Journal of Nuclear Materials

View full text Add to dashboard Cite

SANTA: A safety analysis code for neutron absorbers in spent nuclear fuel pools

Cited by 3 publications

References 11 publications

Simulation of Radiation Damage and He Accumulation Induced by ¹⁰B(n, α)⁷Li Reactions in Al‐B₄C Neutron Absorbers Used in Spent Fuel Pools

Simulation of Radiation Damage and He Accumulation Induced by ¹⁰B(n, α)⁷Li Reactions in Al‐B₄C Neutron Absorbers Used in Spent Fuel Pools

Experimental investigation of non-condensable gas effects in a natural circulation system

Experimental emulation of 10B(n, α)7Li reaction-induced microstructural evolution of Al-B4C neutron absorber used in the dry storage of spent nuclear fuel

Contact Info

Product

Resources

About

SANTA: A safety analysis code for neutron absorbers in spent nuclear fuel pools

Cited by 3 publications

References 11 publications

Simulation of Radiation Damage and He Accumulation Induced by 10B(n, α)7Li Reactions in Al‐B4C Neutron Absorbers Used in Spent Fuel Pools

Simulation of Radiation Damage and He Accumulation Induced by 10B(n, α)7Li Reactions in Al‐B4C Neutron Absorbers Used in Spent Fuel Pools

Experimental investigation of non-condensable gas effects in a natural circulation system

Experimental emulation of 10B(n, α)7Li reaction-induced microstructural evolution of Al-B4C neutron absorber used in the dry storage of spent nuclear fuel

Contact Info

Product

Resources

About

Simulation of Radiation Damage and He Accumulation Induced by ¹⁰B(n, α)⁷Li Reactions in Al‐B₄C Neutron Absorbers Used in Spent Fuel Pools

Simulation of Radiation Damage and He Accumulation Induced by ¹⁰B(n, α)⁷Li Reactions in Al‐B₄C Neutron Absorbers Used in Spent Fuel Pools