کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
6762363 511720 2014 11 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
ASSERT-PV 3.2: Advanced subchannel thermalhydraulics code for CANDU fuel bundles
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
ASSERT-PV 3.2: Advanced subchannel thermalhydraulics code for CANDU fuel bundles
چکیده انگلیسی
Atomic Energy of Canada Limited (AECL) has developed the subchannel thermalhydraulics code ASSERT-PV for the Canadian nuclear industry. The most recent release version, ASSERT-PV 3.2 has enhanced phenomenon models for improved predictions of flow distribution, dryout power and CHF location, and post-dryout (PDO) sheath temperature in horizontal CANDU fuel bundles. The focus of the improvements is mainly on modeling considerations for the unique features of CANDU bundles such as horizontal flows, small pitch to diameter ratios, high mass fluxes, and mixed and irregular subchannel geometries, compared to PWR/BWR fuel assemblies. This paper provides a general introduction to ASSERT-PV 3.2, and describes the model changes or additions in the new version to improve predictions of flow distribution, dryout power and CHF location, and PDO sheath temperatures in CANDU fuel bundles.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 275, August 2014, Pages 69-79
نویسندگان
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