To investigate the possibility of benign prostatic hyperplasia (BPH) in prostatic outer gland by transrectal ultrasound (TRUS) and autopsy examination.Methods Fifty-nine patients were biopsied by TRUS guided in sagitt...To investigate the possibility of benign prostatic hyperplasia (BPH) in prostatic outer gland by transrectal ultrasound (TRUS) and autopsy examination.Methods Fifty-nine patients were biopsied by TRUS guided in sagittal and longitudinal sections,respectively,because hypoechoic nodules were found in the outer glands of the prostates.The specimens were stained by HE methods.The whole prostate specimens obtained from 16 men at autopsy were studied.Sonogram of the specimens was investigated by putting them in water.Them the specimens were sliced down perpendicularly to the urethra,histologically processed and stained by HE methods.Results Pathologically,22 of the 59 specimens were of benign prostate hyperplasia (BPH),29 of prostate cancer (PCa),1 of prostatic intraepithelial neoplasia (PIN) and 7 of tuberculosis (TB).A clear-cut interface between inner gland and outer gland,and multiple calculi and cysts were found on sonogram.Pathological diagnosis of BPH of the outer glands was made in all HE-stained autopsied specimens with varying degrees of hyperplasia of the glands,small muscles and stroma.Conclusion It is suggested that hypoechoic nodules in outer gland of the prostate by TRUS on sonogram may be benign hyperplastic nodules besides PCa,PIN,and TB.10 refs,5 figs.展开更多
A molten salt reactor(MSR)has outstanding features considering the application of thorium fuel,inherent safety,sustainability,and resistance to proliferation.However,fissile material^(233)U is significantly rare at th...A molten salt reactor(MSR)has outstanding features considering the application of thorium fuel,inherent safety,sustainability,and resistance to proliferation.However,fissile material^(233)U is significantly rare at the current stage,thus it is difficult for MSR to achieve a pure thorium-uranium fuel cycle.Therefore,using plutonium or enriched uranium as the initial fuel for MSR is more practical.In this study,we aim to verify the feasibility of a small modular MSR that utilizes plutonium as the starting fuel(SM-MSR-Pu),and highlight its advantages and disadvantages.First,the structural design and fuel management scheme of the SM-MSR-Pu were presented.Second,the neutronic characteristics,such as the graphite-irradiation lifetime,burn-up performance,and coefficient of temperature reactivity were calculated to analyze the physical characteristics of the SM-MSR-Pu.The results indicate that plutonium is a feasible and advantageous starting fuel for a SM-MSR;however,there are certain shortcomings that need to be solved.In a 250 MWth SM-MSR-Pu,approximately 288.64 kg^(233)U of plutonium with a purity of greater than 90% is produced while 978.00 kg is burned every ten years.The temperature reactivity coefficient decreases from -4.0 to -6.5 pcm K^(-1) over the 50-year operating time,which ensures a long-term safe operation.However,the amount of plutonium and accumulation of minor actinides(MAs)would increase as the burn-up time increases,and the annual production and purity of^(233)U will decrease.To achieve an optimal burn-up performance,setting the entire operation time to 30 years is advisable.Regardless,more than 3600 kg of plutonium eventually accumulate in the core.Further research is required to effectively utilize this accumulated plutonium.展开更多
文摘To investigate the possibility of benign prostatic hyperplasia (BPH) in prostatic outer gland by transrectal ultrasound (TRUS) and autopsy examination.Methods Fifty-nine patients were biopsied by TRUS guided in sagittal and longitudinal sections,respectively,because hypoechoic nodules were found in the outer glands of the prostates.The specimens were stained by HE methods.The whole prostate specimens obtained from 16 men at autopsy were studied.Sonogram of the specimens was investigated by putting them in water.Them the specimens were sliced down perpendicularly to the urethra,histologically processed and stained by HE methods.Results Pathologically,22 of the 59 specimens were of benign prostate hyperplasia (BPH),29 of prostate cancer (PCa),1 of prostatic intraepithelial neoplasia (PIN) and 7 of tuberculosis (TB).A clear-cut interface between inner gland and outer gland,and multiple calculi and cysts were found on sonogram.Pathological diagnosis of BPH of the outer glands was made in all HE-stained autopsied specimens with varying degrees of hyperplasia of the glands,small muscles and stroma.Conclusion It is suggested that hypoechoic nodules in outer gland of the prostate by TRUS on sonogram may be benign hyperplastic nodules besides PCa,PIN,and TB.10 refs,5 figs.
基金supported by the Chinese TMSR Strategic Pioneer Science and Technology Project(No.XDA02010000)Chinese Academy of Sciences Talent Introduction Youth Program(No.SINAP-YCJH-202303)Chinese Academy of Sciences Special Research Assistant Funding Project and Shanghai Pilot Program for Basic Research-Chinese Academy of Science,Shanghai Branch(JCYJ-SHFY-2021-003)。
文摘A molten salt reactor(MSR)has outstanding features considering the application of thorium fuel,inherent safety,sustainability,and resistance to proliferation.However,fissile material^(233)U is significantly rare at the current stage,thus it is difficult for MSR to achieve a pure thorium-uranium fuel cycle.Therefore,using plutonium or enriched uranium as the initial fuel for MSR is more practical.In this study,we aim to verify the feasibility of a small modular MSR that utilizes plutonium as the starting fuel(SM-MSR-Pu),and highlight its advantages and disadvantages.First,the structural design and fuel management scheme of the SM-MSR-Pu were presented.Second,the neutronic characteristics,such as the graphite-irradiation lifetime,burn-up performance,and coefficient of temperature reactivity were calculated to analyze the physical characteristics of the SM-MSR-Pu.The results indicate that plutonium is a feasible and advantageous starting fuel for a SM-MSR;however,there are certain shortcomings that need to be solved.In a 250 MWth SM-MSR-Pu,approximately 288.64 kg^(233)U of plutonium with a purity of greater than 90% is produced while 978.00 kg is burned every ten years.The temperature reactivity coefficient decreases from -4.0 to -6.5 pcm K^(-1) over the 50-year operating time,which ensures a long-term safe operation.However,the amount of plutonium and accumulation of minor actinides(MAs)would increase as the burn-up time increases,and the annual production and purity of^(233)U will decrease.To achieve an optimal burn-up performance,setting the entire operation time to 30 years is advisable.Regardless,more than 3600 kg of plutonium eventually accumulate in the core.Further research is required to effectively utilize this accumulated plutonium.
