Numerical investigation of rod bundle thermal–hydraulic behavior during reflood transients using COBRA-TF

Jin, Yue; Cheung, F. B.; Shirvan, Koroush; Bajorek, Stephen M.; Tien, Kirk; Hoxie, Chris L.

doi:10.1016/j.anucene.2020.107708

Cited by 18 publications

(3 citation statements)

References 33 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Predicted 'uniform' advancements of QF from bottom-totop and from top-to-bottom of channel (full lines) leads to gathering of two fronts at about middle of channel height at around 250 s, while experimental data ('+' points) exhibit a 'same-time reflood' at around 220 s, top diagram. Similar experimental and corresponding calculated data are reported in [25] for high velocity reflood. 'Same-time' reflood, or homogeneous reflood, is inconsistent with the derivation of eq.…”

Section: Spread Of Model Results (Bulletssupporting

confidence: 84%

Physical Phenomena in Nuclear Thermal Hydraulics and Current Status

D'Auria¹,

Aksan²,

Glaeser³

2021

TI-IJES

View full text Add to dashboard Cite

116 nuclear Thermal-Hydraulic Phenomena T-HP are identified in the present paper, following documents issued during the last three decades by the Committee on the Safety of Nuclear Installations of Nuclear Energy Agency of the Organization for Economic Cooperation and Development (OECD/NEA/CSNI) and by the International Atomic Energy Agency (IAEA). The derived T-HP list includes consideration of experiments performed in Separate Effect Test (SET) and Integral Effect Test (IET) facilities relevant to reactor coolant system and containment of Water Cooled Nuclear Reactors (WCNR). We consider a dozen WCNR types: Pressurized Water Reactors (PWR), Boiling Water Reactors (BWR), Russian reactors (VVER-440, VVER-1000 and RBMK), pressure tube heavy water reactors by Canada (CANDU) and India (PHWR) and so-called ‘advanced’ reactors (e.g. AP-1000 and APR-1400 designed in US and Korea, respectively). We envisage a variety of applications for the T-HP list. Four of the phenomena are helpful to characterize the current state of art in nuclear thermal-hydraulics: Counter Current Flow Limitation (CCFL), Critical Heat Flux (CHF), reflood and Two-Phase Critical Flow (TPCF). Furthermore, the T-HP identification contributes to addressing the scaling issue, performing uncertainty evaluations, developing constitutive equations and ‘special models’ in codes and prioritizing the research.

show abstract

Section: Spread Of Model Results (Bulletssupporting

confidence: 84%

Physical Phenomena in Nuclear Thermal Hydraulics and Current Status

D'Auria¹,

Aksan²,

Glaeser³

2021

TI-IJES

View full text Add to dashboard Cite

show abstract

“…In addition, the facility utilizes two carryover tanks, one small and one large, to quantify the fraction of liquid carried over during the reflood phase. For a more extensive overview of the RBHT facility, a detailed description can be found in (Hochreiter et al, 2010;Hochreiter et al, 2012;Jin, 2019).…”

Section: Rbht Experimental Facilitymentioning

confidence: 99%

“…RBHT tests have been extensively employed to validate the thermal hydraulics code TRACE by the US-NRC (Hochreiter et al, 2010;Hochreiter et al, 2012;Jin, 2019;Perret et al, 2019). The RBHT model utilized in this paper is based on the one referred to as 'Trace-v5p5′ in (Perret et al, 2019).…”

Section: Rbht Trace Input Modelmentioning

confidence: 99%