We examine the effect of neutron irradiation on the release of deuterium from tungsten at 573 K to understand the efficiency of tritium removal by baking out at moderate temperatures. Tungsten samples, undamaged and neutron-irradiated to a damage level of approximately 0.016 displacements per atom, are exposed to low-energy (108 eV), high-flux (3.0 10²¹ to 9.4 10²¹ m⁻² s⁻¹) deuterium plasma at temperatures ranging from 573 to 773 K to an ion fluence of 1.1 10²⁵ m⁻². At each exposure temperature, two undamaged and two neutron-irradiated tungsten samples are exposed to plasma. The deuterium content in the tungsten samples is measured by thermal desorption spectrometry soon after the plasma exposure and after post-plasma annealing at 573 K for 30 h. It is found that: (i) the deuterium retention in the neutron-irradiated tungsten samples is significantly higher than that in the undamaged tungsten samples; (ii) annealing at 573 K of undamaged tungsten samples pre-exposed to deuterium plasma at 573–773 K leads to an almost complete (60%–99%) release of deuterium from the samples; (iii) annealing at 573 K of neutron-irradiated tungsten samples pre-exposed to deuterium plasma at 573–773 K leads to a significant (8%–20%) release of deuterium from the samples.

我们研究了在573 K下中子辐照对从钨中释放氘的影响，以了解通过在中等温度下烘烤去除removal的效率。钨样品（未损坏且被中子辐照至每个原子约0.016位移的损伤水平）暴露于低能（108 eV）高通量（3.0 10 ²¹至9.4 10 ²¹ m ^-2 s ^-1）氘等离子体在573至773 K的温度范围内达到1.1 10 ²⁵ m ^-2的离子通量。在每个暴露温度下，将两个未损坏和两个中子辐照的钨样品暴露于等离子体。等离子体暴露后不久以及在573 K下进行了30 h等离子后退火后，通过热脱附光谱法测量了钨样品中的氘含量。发现：（i）中子辐照的钨样品中的氘保留显着高于未损坏的钨样品中的氘保留；（ii）在573-773 K暴露于氘等离子体的未损坏钨样品在573 K退火导致几乎完全（60％-99％）氘从样品中释放出来；（iii）在573–773 K下预先暴露于氘等离子体中的中子辐照钨样品在573 K下退火会导致样品中氘的大量释放（8％–20％）。