Transient experiments from the thermal-hydraulic ADS lead bismuth loop (TALL) and comparative TRAC/AAA analysis

Ma, Weimin; Bubelis, E.; Karbojian, Aram; Sehgal, Bal Raj; Coddington, Paul

doi:10.1016/j.nucengdes.2006.01.006

Cited by 46 publications

(16 citation statements)

References 3 publications

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“…The oxide layers, which are formed on the steels by oxygen dissolved in the lead alloy, can be expected to have a protective effect against dissolution of steels. In practical system, thermal stress can be generated on the structural materials by the temperature distribution in a cooling system, a hydrostatic pressure, a nuclear heat generation and a buckling of the structural element [1]. Therefore it is important to investigate how oxide layers behave while their substrate is deformed.…”

Section: Introductionmentioning

confidence: 99%

A stability of oxide layers formed in LBE on HCM12A to external loading

Yamaki

Kikuchi

2010

Journal of Nuclear Materials

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Section: Introductionmentioning

confidence: 99%

A stability of oxide layers formed in LBE on HCM12A to external loading

Yamaki

Kikuchi

2010

Journal of Nuclear Materials

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“…This paper mainly focuses on configuration “A.” Key parameters of the facility were scaled by the prototypic ratio of the XADS (eXperimental Accelerator Driven System) design to reproduce the phenomena in XADS as much as possible. Typical operation transients and abnormal transients that might occur in XADS were performed in this facility, including start‐up of forced circulation, loss of heat sink, overpower transient, overcooling transient, loss of primary flow, heater trip transient, shut down of operation, and primary and secondary side driving head loss transient 7 . Also, natural circulation characteristics of LBE loop was studied using this facility 39 .…”

Section: Benchmarking Of Lethac With Tall Facilitymentioning

confidence: 99%

“…Using these experimental data, several one‐dimensional thermal‐hydraulic codes (such as TRAC/AAA, RELAP/MOD3.0, RELAP/SCDAP, etc.) were benchmarked to evaluate their extended function for lead/lead‐bismuth system 7‐9,39 . Later, with the purpose to validate multidimensional CFD/STH codes, a third leg with a 3D test section was added to the original TALL facility 41 .…”

Section: Benchmarking Of Lethac With Tall Facilitymentioning

confidence: 99%

“…Based on TRACE, LANL (Los Alamos National Laboratory) developed TRAC/AAA version for the Generation IV reactors 6 . Then Ma et al, benchmarked TRAC/AAA by transient experiments conducted on TALL facility in Royal Institute of Technology (KTH) and demonstrated its capability for simulating LBE systems 7,8 . With TALL data, Fiori and Zhou proved the capability of RELAP5/SCDAP for LBE thermal‐hydraulic behavior predicting 9 .…”

Section: Introductionmentioning

confidence: 99%

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Development and validation of transient thermal‐hydraulic evaluation code for a lead‐based fast reactor

Wei

Wang

et al. 2021

Int J Energy Res

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Summary In this paper, development and preliminary validation of an in‐house code LETHAC (lead‐based fast reactor thermal‐hydraulic analysis code) is introduced. LETHAC is developed for predicting the thermal‐hydraulic transient performance of a lead‐bismuth reactor. The mathematical models and module relations of LETHAC are presented in detail. The most‐used LBE (lead‐bismuth eutectic) flow and heat transfer correlations are compared against data from KYLIN‐II 61‐rod wire‐wrapped bundle experiments. Results show little difference between the chosen heat transfer correlations as the relative error of these correlations is all within 2%. Novendstern correlation is recommended for wire‐wrapped bundle frictional resistance coefficient calculation as it fits the experimental data best. Besides, the transient calculation capability of LETHAC is also preliminarily evidenced by TALL transient tests. Good agreements are shown between the calculated temperatures and the experiment ones. Relative errors between calculation results and experimental data are almost within 10% during the whole transient process, which indicates LETHAC can be used for predicting the transient behavior of lead/lead‐bismuth cooled systems.

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“…Advanced computational tools are therefore required and developed to simulate the reactor behavior during operational transient and other accident scenarios. So far, several codes for LWRs have been developed for the safety analysis, such as RELAP5, RELAP5/PARCS, TRAC-AAA, EAC, SAS4/SASSYS, and SIMMER [7]. Also, a lot of comparisons of the simulation results have been performed using different computing codes [8 -10].…”

Section: Simulation Toolmentioning

confidence: 99%

Validation of TRACE Code Against ROSA/LSTF Test for SBLOCA of Pressure Vessel Upper-Head Small Break

Xing¹,

Chen³

et al. 2013

Volume 4: Thermal Hydraulics

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OECD/NEA ROSA/LSTF project tests are performed on the Large Scale Test Facility (LSTF). LSTF is a full-height, full-pressure and 1/48 volumetrically-scaled two-loop system which aims to simulate Japanese Tsuruga-2 Westinghouse-type 4-loop PWR. ROSA-V Test 6-1 simulates a pressure vessel (PV) upper-head small break loss-of-coolant accident (SBLOCA) with a break size equivalent to 1.9% of the volumetrically scaled cross-sectional area of the reference PWR cold leg.The main objective of present thesis is to build a TRACE calculation model for simulating thermal hydraulic behaviors in LSTF and PV upper-head SBLOCA, so as to assess different modeling options and parameters of TRACE code. The results show that TRACE code well reproduce the complex physical phenomena involved in this type of SBLOCA scenarios. Almost all the events in the experiment are well predicted by the model based on TRACE code. In addition, the sensitivity of different models and parameters are investigated. For example, the code slightly overestimates the break mass flow from upper head which affects the accuracy of the results significantly. The rising of core exit temperature (CET) is significantly influenced by the flow area of leakage between downcomer and hot leg. Besides, the effect of the break location, low pressure injection system (LPIS) and accumulator setup are also studied.

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Transient experiments from the thermal-hydraulic ADS lead bismuth loop (TALL) and comparative TRAC/AAA analysis

Cited by 46 publications

References 3 publications

A stability of oxide layers formed in LBE on HCM12A to external loading

A stability of oxide layers formed in LBE on HCM12A to external loading

Development and validation of transient thermal‐hydraulic evaluation code for a lead‐based fast reactor

Validation of TRACE Code Against ROSA/LSTF Test for SBLOCA of Pressure Vessel Upper-Head Small Break

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