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Magnesium phosphate-based neutron shielding cementing material with high boron carbide content
The invention discloses a magnesium phosphate-based neutron shielding cementing material with high boron carbide content, which is prepared from the following components in parts by mass: 16.1 to 42 parts of dead burnt magnesium oxide, 20 to 49 parts of monopotassium phosphate, 0.9 to 2.6 parts of retarder and 20 to 55 parts of boron carbide. The mass ratio of magnesium oxide to phosphate is uniquely controlled to be about 4: 7, so that the material still keeps high compressive strength when the content of boron carbide reaches 20%-55%, meanwhile, the material has more excellent neutron absorption capacity, and the cementing material has high strength (the compressive strength is close to 60 MPa in 28d) and long setting time (the initial setting time is 15-60 min), and can be applied to the field of thermal insulation materials. The absorption rate of a material with the thickness of 20 mm to thermal neutrons of 1-100 ev is larger than 99.5%, and the absorption rate of a material with the thickness of 100 mm to medium energy neutrons of 1-10 kev is larger than 98.7%. The radiation shield can be used for radiation shielding of nuclear reactors or various neutron sources.
本发明公开了一种高碳化硼含量磷酸镁基中子屏蔽胶凝材料，以质量份数计，该胶凝材料包括：重烧氧化镁为16.1~42份，磷酸二氢钾为20~49份，缓凝剂为0.9~2.6份，碳化硼为20~55份。本发明独特地控制氧化镁与磷酸盐的质量比在4：7左右，使得碳化硼含量达到20%~55%时材料依然保持高的抗压强度，同时具有更加优异的中子吸收能力，该胶凝材料具有高强度（28d抗压强度接近60MPa），较长的凝结时间（初凝时间介于15~60min之间），高的中子屏蔽性能（20mm厚材料对1~100ev热中子的吸收率大于99.5%，100mm厚材料对1~10kev中能中子的吸收率大于98.7%）等特点。可用作核反应堆或各类中子源的辐射屏蔽。
Magnesium phosphate-based neutron shielding cementing material with high boron carbide content
The invention discloses a magnesium phosphate-based neutron shielding cementing material with high boron carbide content, which is prepared from the following components in parts by mass: 16.1 to 42 parts of dead burnt magnesium oxide, 20 to 49 parts of monopotassium phosphate, 0.9 to 2.6 parts of retarder and 20 to 55 parts of boron carbide. The mass ratio of magnesium oxide to phosphate is uniquely controlled to be about 4: 7, so that the material still keeps high compressive strength when the content of boron carbide reaches 20%-55%, meanwhile, the material has more excellent neutron absorption capacity, and the cementing material has high strength (the compressive strength is close to 60 MPa in 28d) and long setting time (the initial setting time is 15-60 min), and can be applied to the field of thermal insulation materials. The absorption rate of a material with the thickness of 20 mm to thermal neutrons of 1-100 ev is larger than 99.5%, and the absorption rate of a material with the thickness of 100 mm to medium energy neutrons of 1-10 kev is larger than 98.7%. The radiation shield can be used for radiation shielding of nuclear reactors or various neutron sources.
本发明公开了一种高碳化硼含量磷酸镁基中子屏蔽胶凝材料，以质量份数计，该胶凝材料包括：重烧氧化镁为16.1~42份，磷酸二氢钾为20~49份，缓凝剂为0.9~2.6份，碳化硼为20~55份。本发明独特地控制氧化镁与磷酸盐的质量比在4：7左右，使得碳化硼含量达到20%~55%时材料依然保持高的抗压强度，同时具有更加优异的中子吸收能力，该胶凝材料具有高强度（28d抗压强度接近60MPa），较长的凝结时间（初凝时间介于15~60min之间），高的中子屏蔽性能（20mm厚材料对1~100ev热中子的吸收率大于99.5%，100mm厚材料对1~10kev中能中子的吸收率大于98.7%）等特点。可用作核反应堆或各类中子源的辐射屏蔽。
Magnesium phosphate-based neutron shielding cementing material with high boron carbide content
一种高碳化硼含量磷酸镁基中子屏蔽胶凝材料
WANG TAO (author) / ZHA WEI (author) / ZHANG XINXIN (author) / WANG QI (author)
2022-05-06
Patent
Electronic Resource
Chinese
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