Crazymechanic said:
Hi could you please explain me what happens with the atomic structure and overall material structure of neutron absorber rods used in fission reactors?
As I imagine when they are used they absorb the neutrons that keep the chain reaction going so to stop the chain reaction hence shut the reactor down, but the absorber rod material then while absorbing these neutrons changes it's atomic structure I guess as every other element being bombarded with fast or thermal neutron would , so how long a absorber rod material would last and how does it changes it's structure over time , I guess the explanation should be about the overall tendencies as each reactor type uses a little different material or mix of materials like boron , boric acid , cadmium, hafnium etc.
Thanks.
One has to distinguish between BWR and PWRs, and in PWRs, those designs that use control rods for shutdown only vs those that use grey rods for power shaping and quick power control (grey rods) or reactivity control.
In BWRs, groups of control rods are used intermittently of reactivity control, in addition to using the void distribution. Groups of control rods are swapped periodically to balance the reactivity in the core. After a certain service period, the active control rods are swapped into shudown banks, and those control rods in the shutdown banks are removed from service when they reach their design exposure. BWR control rods use B
4C and some Hf in peak flux locations. Boron may be enriched in B-10, and B-10 undergoes an n,α reaction that depletes the B-10. Hf absorbs neutrons, but does not disintegrate like B-10.
http://web.mit.edu/nrl/Training/Absorber/absorber.htm
One has to be careful with Hf, because within the stainless steel structure, it may absorb hydrogen and swell. The structural material is usually high purity (low S, P and other impurities) 304L or 316L.
PWRs usually do not use control rods during operation for reactivity control, but rather the control rods are withdrawn above the core and only used to shutdown the reactor. Some designs use 'grey rods' which contain a reduced absorber content or a Ni-based absorber. These are used for radial and axial power shaping, as well as fine reactivity control for load following. Some new reactor designs do use more advanced grey rods, and at least one new PWR-type design is planning to use control rods for reactivity control to eliminate the need for boric acid (chemical shim). PWRs traditionally use boric acid buffered with LiOH to ensure the pH is within certain limits during the cycle.
PWR control rods use B
4C, AIC (Silver (Ag)-Indium (In)-Cadmium (Cd), Hf, or Dy (in form of Dysprosium titanate). Use of B
4C and AIC has to take into account the swelling that occurs with exposure. Use of Hf means one has to be concerned with hydrogen absorption. In some cases, B
4C may be used with AIC tips.
Both BWR and PWR fuel use gadolinia mixed with the UO2 fuel for control of power peaking in the fuel, and in some PWR fuel, some fuel pellets are coated with ZrB
2 instead of using gadolinia. The isotopes Gd-155 and -157 are strong thermal neutron absorbers as compared to Gd-156 and Gd-158.
PWR control rods use 304L or 316L for structural material. Swelling and intergranular stress corrosion cracking are two concerns with respect to performance and lifetime. Austenitic steels are susceptible to swelling.
Neutron irradiation does cause changes to atomic microstructure in metals - mainly dislocations of atoms in the crystal structure. This has the effect of hardening and embrittling the metals. Irradation may sensitize certain alloys, i.e., make them more susceptible to cracking.
Lifetime of PWR control rods is about 15 years.