PARET-ANL Modeling of a SPERT-IV Experiment under Different Departure from Nucleate Boiling Correlations

Modeling of SPERT IV Reactivity Initiated Transient Tests in EUREKA-2/RR Code

“…However, some inconsistency is noticed for few tests which correspond to a reactivity insertion less than $1. If one traces back work of Chatzidakis et al, 2012 [3], it is found that three DNB correlations, namely, Tong, Mirshak, and Bernath, facilitated in the PARET code, have been applied for a range of tests to identify use of which correlation provides peak clad temperature values that agree with the experimental results. Peak power values have not been shown to compare with the experiment in this paper.…”

“…However, in modeling the research reactor transient condition, the analyst has to consider some conservative assumptions due to lack of experimental data which may lead to false prediction of the real physical phenomenon that takes place in the reactor. One common point that came out from reactor analysis is the importance of proper selection of input parameters such as DNB correlations to obtain the real characteristic of the transient parameters [2,3]. In this context, reactivity initiated transient analysis code EUREKA-2/RR [4] has been used whether it could be able to model the SPERT IV transient experiment.…”

Modern design and safety analysis of the University of Florida Training Reactor

“…Obenchain (1969) validates the PARET-ANL code against experimental data from tests on the high-enriched, plate-type SPERT III C-core. Additionally, Chatzidakis et al (2012), in a more extensive analysis of the DNB correlations used in PARET, show that agreement within 50% can be expected when using the Tong correlation for DNB heat transfer. The uncertainties associated with the input parameters (i.e.…”

“…The PARET-ANL (Obenchain, 1969) code was used to conduct this examination, which is a coupled reactor kinetics/hydraulics code. Previous work has validated this code using experimental data and quantified the resulting uncertainties (Chatzidakis et al, 2012). Combined with the uncertainties associated with the core input parameters, a total uncertainty of 70% on temperature differences (increase during the accident) must be included when analyzing the final temperature results.…”

Tính Toán Thủy Nhiệt Và Phân Tích an Toàn Lò Phản Ứng Nghiên Cứu Đa Mục Tiêu Công Suất 10 Mw Sử Dụng Nhiên Liệu VVR-Kn Độ Giàu Thấp

“…Các chương trình tính toán được sử dụng cho phân tích an toàn đã được thương mại và được hiệu lực hóa thông qua việc so sánh với các kết quả thí nghiệm cũng như các kết quả tính toán từ các chương trình tính toán khác đã được công bố (Arinkin, 2014;Arne, & M, 2015Arne, & M, , 2016CHATZIDAKIS et al, 2012;Hanan, & Garner, 2015;International Atomic Energy Agency, 2019;Nakipov, 2015).…”