کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
11019756 | 1717620 | 2019 | 8 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Verification and validation of radiation source term capabilities in STREAM
دانلود مقاله + سفارش ترجمه
دانلود مقاله ISI انگلیسی
رایگان برای ایرانیان
کلمات کلیدی
موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
![عکس صفحه اول مقاله: Verification and validation of radiation source term capabilities in STREAM Verification and validation of radiation source term capabilities in STREAM](/preview/png/11019756.png)
چکیده انگلیسی
This paper presents the verification and validation of the radiation source term calculation capability implemented in the reactor analysis code STREAM for pressurized water reactor (PWR) spent nuclear fuel (SNF) analysis. Activity, decay heat, neutron and gamma source spectra of irradiated PWR fuel assemblies are calculated with STREAM and ORIGEN and the results obtained are compared. The verification is performed with Westinghouse 15â¯Ãâ¯15, 17â¯Ãâ¯17 and Combustion Engineering 16â¯Ãâ¯16 designs with enrichment of 3-5â¯wt.% 235U, burnup of 30-60â¯GWd/t and cooling times of 0.3-1000â¯years. The radiation source term comparison between STREAM and ORIGEN indicates that the implementation of the source term equations is correct. The validation is done by comparing STREAM calculation results against 91 decay heat calorimetric measurements for 52 PWR fuel assemblies performed at the Swedish central storage facility for spent nuclear fuel, CLAB, and United States Hanford Engineering Development Laboratory (HEDL) and General Electric Morris Operations. The measured fuel assemblies have enrichment of 2-4â¯wt.% 235U, burnup of 28-51â¯GWd/t and cooling times of 2-27â¯years. The comparison between calculated and measured decay heat shows good agreement. For most of the measurements analyzed, the calculated decay heat is within the range of the measurement uncertainty. The average, overall C/E over 71 CLAB decay heat measurements is 1.000â¯Â±â¯0.017, and 0.997â¯Â±â¯0.013 for 20 US measurements. Overall, this work demonstrates that STREAM can be reliably used to predict PWR SNF radiation source terms.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 124, February 2019, Pages 80-87
Journal: Annals of Nuclear Energy - Volume 124, February 2019, Pages 80-87
نویسندگان
Bamidele Ebiwonjumi, Sooyoung Choi, Matthieu Lemaire, Deokjung Lee, Ho Cheol Shin, Hwan Soo Lee,