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Title: Improvements to the RELAP5/MOD3 reflood model and uncertainty quantification of reflood peak clad temperature

Technical Report ·
DOI:https://doi.org/10.2172/393372· OSTI ID:393372
; ; ;  [1]
  1. Korea Atomic Energy Research Institute, Yusung, Taejon (Korea, Republic of); and others

Assessment of the original REAP/N4OD3.1 code against the FLECHT SEASET series of experiments has identified some weaknesses of the reflood model, such as the lack of a quenching temperature model, the shortcoming of the Chen transition boiling model, and the incorrect prediction of droplet size and interfacial heat transfer. Also, high temperature spikes during the reflood calculation resulted in high steam flow oscillation and liquid carryover. An effort had been made to improve the code with respect to the above weakness, and the necessary model for the wall heat transfer package and the numerical scheme had been modified. Some important FLECHT-SEASET experiments were assessed using the improved version and standard version. The result from the improved REAP/MOD3.1 shows the weaknesses of REAP/N4OD3.1 were much improved when compared to the standard MOD3.1 code. The prediction of void profile and cladding temperature agreed better with test data, especially for the gravity feed test. The scatter diagram of peak cladding temperatures (PCTs) is made from the comparison of all the calculated PCTs and the corresponding experimental values. The deviation between experimental and calculated PCTs were calculated for 2793 data points. The deviations are shown to be normally distributed, and used to quantify statistically the PCT uncertainty of the code. The upper limit of PCT uncertainty at 95% confidence level is evaluated to be about 99K.

Research Organization:
US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research; Korea Inst. of Nuclear Safety, Taejon (Korea, Republic of)
Sponsoring Organization:
Nuclear Regulatory Commission, Washington, DC (United States); Korea Inst. of Nuclear Safety, Taejon (Korea, Republic of)
OSTI ID:
393372
Report Number(s):
NUREG/IA-0132; ON: TI97000708; TRN: 97:000094
Resource Relation:
Other Information: PBD: Oct 1996
Country of Publication:
United States
Language:
English