Activation and Environmental Aspects of In-Vacuum Vessel Components of CFETR

来源 :Plasma Science and Technology | 被引量 : 0次 | 上传用户:lzjsja
下载到本地 , 更方便阅读
声明 : 本文档内容版权归属内容提供方 , 如果您对本文有版权争议 , 可与客服联系进行内容授权或下架
论文部分内容阅读
The water-cooled ceramic breeder(WCCB) blanket is one of the three candidates of China’s Fusion Engineering Test Reactor(CFETR). The evaluation of the radioactivity and decay heat produced by neutrons for the in-vacuum vessel components is essential for the assessment of radioactive wastes and the safety of CFETR. The activation calculation of CFETR in-vacuum vessel components was carried out by using the Monte Carlo N-Particle Transport Code MCNP, IAEA Fusion Evaluated Nuclear Data Library FENDL2.1, and the nuclear inventory code FISPACT-2007 and corresponding EAF-2007 libraries. In these analyses, the three-dimensional(3-D) neutronics model was employed and the WCCB blanket, the divertor, and the shield were modeled in detail to provide the detailed spatial distribution of the neutron flux and energy spectra. Then the neutron flux, energy spectra and the materials specification were transferred to FISPACT for the activation calculation with an assumed irradiation scenario of CFETR. This paper presents the main results of the activation analysis to evaluate the radioactivity, the decay heat, the contact dose, and the waste classification of the radioactive materials. At the time of shutdown, the activity of the WCCB blanket is 1.88×10~(19)Bq and the specific activity, the decay heat and the contact dose rate are 1.7×10~(13)Bq/kg, 3.05 MW, and 2.0×10~3Sv/h respectively. After cooling for 100 years, 79%(4166.4 tons) radioactive wastes produced from the blanket, divertor,high temperature shield(HTS) and low temperature shield(LTS) need near surface disposal, while21%(1112.3 tons) need geological disposal. According to results of the contact dose rate, all the components of the blanket, divertor, HTS and LTS could potentially be recycled after shutdown by using advanced remote handling equipment. In addition, the selection of Eurofer97 or RAFM for the divertor is better than that of SS316 because SS316 makes the activity of the divertor-body keep at a relatively high level. The water-cooled ceramic breeder (WCCB) blanket is one of the three candidates of China’s Fusion Engineering Test Reactor (CFETR). The evaluation of the radioactivity and decay heat produced by neutrons for the in-vacuum vessel components is essential for the assessment of The radioactive wastes and the safety of CFETR. The activation calculation of CFETR in-vacuum vessel components was carried out by using the Monte Carlo N-Particle Transport Code MCNP, IAEA Fusion Evaluated Nuclear Data Library FENDL 2.1, and the nuclear inventory code FISPACT- 2007 and corresponding EAF-2007 libraries. In these analyzes, the three-dimensional (3-D) neutronics model was employed and the WCCB blanket, the divertor, and the shield were modeled in detail to provide the detailed spatial distribution of the neutron flux and energy spectra. Then the neutron flux, energy spectra and the materials specification were transferred to FISPACT for the activation calculation with an adapted irradiation scenario of CFETR. T his paper presents the main results of the activation analysis to evaluate the radioactivity, the decay heat, the contact dose, and the waste classification of the radioactive materials. At the time of shutdown, the activity of the WCCB blanket is 1.88 × 10 ~ ( 19) Bq and the specific activity, the decay heat and the contact dose rate are 1.7 × 10 ~ (13) Bq / kg, 3.05 MW, and 2.0 × 10 ~ 3Sv / h respectively. After cooling for 100 years, 79% 4166.4 tons) radioactive wastes produced from the blanket, divertor, high temperature shield (HTS) and low temperature shield (LTS) need near surface disposal, while while 21% (1112.3 tons) need geological disposal. the components of the blanket, divertor, HTS and LTS could potentially be recycled after shutdown by using advanced remote handling equipment. In addition, the selection of Eurofer97 or RAFM for the divertor is better than that of SS316 because SS316 makes the activity of the divertor -body keep at a relatively high h level.
其他文献
对W涂层和Mo合金在1600℃下的互扩散行为进行了研究,单晶样品长期(最长5000 h)高温退火后仍然保持单晶形貌,多晶材料W晶界多垂直于Mo表面方向。由线扫描结果:W向Mo基体的扩散
鸡西矿业集团公司张辰煤矿西三采区3
“中国发展核电不是一个选项,而是一个必然。中国要发展核电,必须形成国家意志。”在调任中核集团任职之前,孙勤分别在涉核的主管部门国防科工委与国家能源局任职。这一经历,
在新课程改革的大背景下,高等体育教育专业改革工作整如火如荼的进行中。在具体改革实践中,应该根据自身培养目标进行重新定位,加强对基础体育教育的有效整合与对接。然而,现