Iris small break loca phenomena identification and ranking table (PIRT)

Larson, Thomas K.; Moody, F. J.; Wilson, G.E.; Brown, William L.; Frepoli, Cesare; Hartz, J.; Woods, Brian; Oriani, L.

doi:10.1016/j.nucengdes.2006.09.028

Cited by 21 publications

(8 citation statements)

References 7 publications

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“…The design of the SPES3 facility was finalized thanks to an iterative calculation-design feedback process that allowed to verify the adequacy of containment pressure and reactor vessel mass inventory simulation, objectives of the SBLOCA PIRT for the IRIS reactor [7].…”

Section: Discussionmentioning

confidence: 99%

“…The SPES3 nodalization was completely developed for the RELAP5 code (Figures 6,7,and 8). It includes 1499 volumes, 1639 junctions, 1839 heat structures, and 19322 mesh points.…”

Section: Iris Plant and Spes3 Facility Layout And Nodalizationmentioning

confidence: 99%

“…The above-mentioned process allowed to verify the SBLOCA PIRT objectives for the IRIS reactor, as defined by a group of international experts [7]. The Phenomena Identification and Ranking Table put in evidence the thermalhydraulic phenomena playing an important role in operation of IRIS safety systems.…”

Section: Introductionmentioning

confidence: 99%

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SPES3 Facility RELAP5 Sensitivity Analyses on the Containment System for Design Review

Achilli

Congiu

Ferri

et al. 2012

Science and Technology of Nuclear Installations

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An Italian MSE R&D programme on Nuclear Fission is funding, through ENEA, the design and testing of SPES3 facility at SIET, for IRIS reactor simulation. IRIS is a modular, medium size, advanced, integral PWR, developed by an international consortium of utilities, industries, research centres and universities. SPES3 simulates the primary, secondary and containment systems of IRIS, with 1:100 volume scale, full elevation and prototypical thermal-hydraulic conditions. The RELAP5 code was extensively used in support to the design of the facility to identify criticalities and weak points in the reactor simulation. FER, at Zagreb University, performed the IRIS reactor analyses with the RELAP5 and GOTHIC coupled codes. The comparison between IRIS and SPES3 simulation results led to a simulation-design feedback process with step-by-step modifications of the facility design, up to the final configuration. For this, a series of sensitivity cases was run to investigate specific aspects affecting the trend of the main parameters of the plant, as the containment pressure and EHRS removed power, to limit fuel clad temperature excursions during accidental transients. This paper summarizes the sensitivity analyses on the containment system that allowed to review the SPES3 facility design and confirm its capability to appropriately simulate the IRIS plant.

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Section: Discussionmentioning

confidence: 99%

“…The SPES3 nodalization was completely developed for the RELAP5 code (Figures 6,7,and 8). It includes 1499 volumes, 1639 junctions, 1839 heat structures, and 19322 mesh points.…”

Section: Iris Plant and Spes3 Facility Layout And Nodalizationmentioning

confidence: 99%

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SPES3 Facility RELAP5 Sensitivity Analyses on the Containment System for Design Review

Achilli

Congiu

Ferri

et al. 2012

Science and Technology of Nuclear Installations

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“…The FSA provides the tools to verify the accomplishment of the two Figures of Merit for IRIS specified in the PIRT [9], which are (a) the Reactor Vessel coolant inventory, which should be enough to avoid significant fuel cladding temperature excursions and (b) the Containment pressure within design value through successful heat removal to the environment, to limit the initial containment overpressurization and guarantee its following depressurization.…”

Section: Iris Scaling Approach and Spes3 Simulation Choicesmentioning

confidence: 99%

The SPES3 Experimental Facility Design for the IRIS Reactor Simulation

Carelli

Conway

Dzodzo

et al. 2009

Science and Technology of Nuclear Installations

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IRIS is an advanced integral pressurized water reactor, developed by an international consortium led by Westinghouse. The licensing process requires the execution of integral and separate effect tests on a properly scaled reactor simulator for reactor concept, safety system verification, and code assessment. Within the framework of an Italian R&D program on Nuclear Fission, managed by ENEA and supported by the Ministry of Economic Development, the SPES3 facility is under design and will be built and operated at SIET laboratories. SPES3 simulates the primary, secondary, and containment systems of IRIS with 1 : 100 volume scale, full elevation, and prototypical thermal-hydraulic conditions. The simulation of the facility with the RELAP5 code and the execution of the tests will provide a reliable tool for data extrapolation and safety analyses of the final IRIS design. This paper summarises the main design steps of the SPES3 integral test facility, underlying choices and phases that lead to the final design.

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“…3. Based on IRIS phenomena identification and ranking table (PIRT) [7], which is EMDAP element 1, step 4, two figures of merits are established. One is pressure response of the containment vessel, while the other is the water level in the reactor vessel.…”

Section: Introductionmentioning

confidence: 99%

Application of Fractional Scaling Analysis for Development and Design of Integral Effects Test Facility

Dzodzo

Oriolo

Ambrosini

et al. 2019

Journal of Nuclear Engineering and Radiation Science

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The aim of this paper is to present a fractional scaling analysis (FSA) application for a system with interacting components where multiple figures of merits need to be respected during complex transient accident scenario with several consecutive time sequences. This paper presents FSA application to the International Reactor Innovative and Secure (IRIS) reactor and Simulatore Pressurizzato per Esperienze di Sicurezza 3 (SPES3) integral effects test (IET) facility. The FSA was applied for the small break loss of coolant accident (SBLOCA) on the direct vessel injection (DVI) line as the most challenging transient scenario. The FSA methodologies were applied for two figures of merits: (1) reactor and containment vessels pressure responses, and (2) reactor vessel water collapsed level response. The space decomposition was performed first. The reactor vessel and containment vessel were divided in components so that important phenomena and their consequences can be evaluated in each of them. After that, the time decomposition in consecutive time sequences was performed for the considered transient (DVI SBLOCA) based on the starts, or ends, of the defining events. The configuration of the system in each time sequence might be different and dependent on the control system actions connecting, or disconnecting, various components of the system due to the valves openings, or closings. This way, the important phenomena and their consequences can be evaluated for each component and time sequence. Also, this paper presents and discusses options for deriving nondimensional groups and calculation of distortions between prototype and model responses for complex transients containing multiple consecutive time sequences. The input data for scaling analysis are based on the results of RELAP/GOTHIC analysis performed for IRIS and RELAP analysis performed for SPES3. The scaling analysis was applied iteratively several times for different IRIS and SPES3 configurations. Based on the intermediate results, some components in the IRIS and SPES3 were redesigned so that the distortions between IRIS and SPES3 responses are decreased.

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Iris small break loca phenomena identification and ranking table (PIRT)

Cited by 21 publications

References 7 publications

SPES3 Facility RELAP5 Sensitivity Analyses on the Containment System for Design Review

SPES3 Facility RELAP5 Sensitivity Analyses on the Containment System for Design Review

The SPES3 Experimental Facility Design for the IRIS Reactor Simulation

Application of Fractional Scaling Analysis for Development and Design of Integral Effects Test Facility

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