The document (in Italian) constituted the first of a series dealing with the design, the construction and the operation of the PIPER-ONE loop installed at the Scalbatraio Laboratory managed by IIN (Istituto di Impianti Nucleari) and later on by DCMN (Dipartimento di Costruzioni Meccaniche e Nucleari) of University of Pisa. PIPER-ONE was built in Italy as a consequence of the Three-Mile accident (1979): it aim at simulating the Boiling Water Reactor (BWR) performance following Small Break Loss of Coolant Accidents (SBLOCA). The natural circulation which occurs between down-comer and core into the vessel constitutes the reference thermal-hydraulic phenomenon which needed to be simulated. The concerned document allowed the identification of the minimum scale (i.e. size of the loop) which was consistent with the simulation of the phenomenon; this was also the maximum scale which was consistent with the available budget. At the end of the process documented in the current report, a 4X4 fuel bundle full height was selected leading to an about 15 m high loop. Full pressure, full temperature and full linear heat power (for the nuclear fuel rod simulators) scales were selected. The PIPER-ONE loop was used for an International Standard Problem (ISP) by Organization for Economic Cooperation and Development (OECD) / Nuclear Energy Agency (NEA) / Committee on the Safety of Nuclear Installations (CSNI) during the middle of 80’s. The design and the operation of the loop constituted a milestone achievement in the area of nuclear thermal-hydraulics with main reference to the scaling.
Feasibility analysis of PIPER-ONE loop: a system to simulate SBLOCA in BWRs" (in Italian), University of Pisa Report, IIN - RP 416(80), Pisa (I), Sept. 1980
D'Auria F.
Primo
Writing – Review & Editing
;
1980-01-01
Abstract
The document (in Italian) constituted the first of a series dealing with the design, the construction and the operation of the PIPER-ONE loop installed at the Scalbatraio Laboratory managed by IIN (Istituto di Impianti Nucleari) and later on by DCMN (Dipartimento di Costruzioni Meccaniche e Nucleari) of University of Pisa. PIPER-ONE was built in Italy as a consequence of the Three-Mile accident (1979): it aim at simulating the Boiling Water Reactor (BWR) performance following Small Break Loss of Coolant Accidents (SBLOCA). The natural circulation which occurs between down-comer and core into the vessel constitutes the reference thermal-hydraulic phenomenon which needed to be simulated. The concerned document allowed the identification of the minimum scale (i.e. size of the loop) which was consistent with the simulation of the phenomenon; this was also the maximum scale which was consistent with the available budget. At the end of the process documented in the current report, a 4X4 fuel bundle full height was selected leading to an about 15 m high loop. Full pressure, full temperature and full linear heat power (for the nuclear fuel rod simulators) scales were selected. The PIPER-ONE loop was used for an International Standard Problem (ISP) by Organization for Economic Cooperation and Development (OECD) / Nuclear Energy Agency (NEA) / Committee on the Safety of Nuclear Installations (CSNI) during the middle of 80’s. The design and the operation of the loop constituted a milestone achievement in the area of nuclear thermal-hydraulics with main reference to the scaling.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
