10B(n, α)7Li reaction-induced gas bubble formation in Al–B4C neutron absorber irradiated in spent nuclear fuel pool
Source abstract
Abstract
Al–B 4 C metal matrix composites have been utilized as a neutron absorber for the past two decades to manage the neutron flux and the criticality of spent nuclear fuel pools. Recently, premature surface corrosion has been found from an eight-year-old surveillance coupon although 40 years of service life was guaranteed based on separated corrosion tests and gamma irradiation tests. Suspecting the premature corrosion was assisted by radiation damage effects from energetic particles emitted from 10B(n, α) 7 Li reaction, nanoscale characterization and neutron attenuation tests were carried out on the surveillance coupons used in a spent nuclear fuel pool for 33, 52, and 99 months to investigate the degradation mechanisms and 10 B depletion. Highly radiation-damaged structures, such as numerous gas bubbles filled with helium and hydrogen in the aluminum matrix and microcracks in boron carbide particles, were observed from all absorber coupons with slightly reduced densities (<1%) matching with the porous structures. The neutron attenuation tests on 52 and 99 month-installed coupons showed ∼3.1% reduction of 10 B areal density, which also indicates the needs for further investigation on the long-term safety and performance of the absorber material.
Source: expertdata · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Aluminum Alloys Composites Properties
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (33)
Show source-provided references
1. Nuclear Energy Institute · 2016
2. Holtec International · 2015
3. Electric Power Research Institute · 2009
4. Electric Power Research Institute · 2016
5. Electric Power Research Institute · 2016
6. Electric Power Research Institute · 2009
7. Accelerated corrosion tests to evaluate the long-term performance of BORAL® in spent fuel pools
8. B-10 evaluation of BORAL neutron absorber
9. Electric Power Research Institute · 2001
10. Performance evaluation of METAMIC neutron absorber in spent fuel storage rack
11. Defect structure of neutron irradiated boron carbide10.1016/0022-3115(73)90003-2 ↗
12. Helium bubble evolution in ion irradiated Al/B4C metal metrix composite10.1016/j.scriptamat.2015.07.011 ↗
13. Gamma and fast neutron radiation monitoring inside spent reactor fuel assemblies10.1016/j.nima.2007.05.192 ↗
14. Nanostructures formation in Al-B4C neutron absorbing materials after accelerated irradiation and corrosion tests, microsc
15. The effect of cutting process on surface microstructure and hardness of pure and Al 6061 aluminium alloy10.1016/j.jestch.2014.07.004 ↗
16. SRIM - the stopping and range of ions in matter10.1016/j.nimb.2010.02.091 ↗
17. On the use of SRIM for computing radiation damage exposure10.1016/j.nimb.2013.05.008 ↗
18. ASTM Standard E2971-16 · 2016
19. Swelling and microcracking of boron carbide subjected to fast neutron irradiations10.1063/1.346370 ↗
20. Crack propagation in irradiated B4C induced by swelling and thermal gradients10.1111/j.1151-2916.1982.tb10398.x ↗
21. Irradiation response and tritium release behavior of boron carbide10.1016/0022-3115(85)90245-4 ↗
22. Irradiation effects of boron carbide used as control rod elements in fast breeder reactors10.1016/0022-3115(78)90539-1 ↗
23. Irradiation behavior of boron carbide10.13182/NT72-A31189 ↗
24. International Atomic Energy Agency · 1982
25. Bubble nucleation and growth in an Fe-12 at% Cr ferritic alloy under He+ implantation and Fe+ irradiation10.1016/0022-3115(86)90080-2 ↗
26. Helium accumulation in metals during irradiation - where do we stand?10.1016/j.jnucmat.2003.09.001 ↗
27. Possible mechanisms limiting the pressure in inert gas bubbles in metals
28. Divergent impact study of the compressive failure threshold in SiC and B4C10.1016/j.ijimpeng.2010.10.027 ↗
29. Strengthening mechanisms in particulate Al/B4C composites produced by repeated roll bonding process10.1016/j.jallcom.2010.11.004 ↗
30. Aging behavior of Al 6061 alloy processed by high-pressure torsion and subsequent aging10.1007/s11661-015-2840-5 ↗
31. Nano-scale microstructure damage by neutron irradiations in a novel Boron-11 enriched TiB2 ultra-high temperature ceramic10.1016/j.actamat.2018.11.030 ↗
32. Compound formation in the systems lithium-carbon and lithium-boron10.1111/j.1151-2916.1967.tb14985.x ↗
33. Effect of fast neutron irradiation on the structure of boron carbide10.1111/j.1151-2916.1977.tb14097.x ↗