A list of 116 Thermal-Hydraulic Phenomena T-HP is derived 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 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). A dozen WCNR types are considered: Pressurized Water Reactors (PWR), Boiling Water Reactors (BWR), Russian designs (VVER-440, VVER-1000 and RBMK), pressure tube heavy water reactor designs by Canada (CANDU) and India (PHWR) and so-called ‘advanced’ reactors (e.g. AP-1000 and APR-1400 designed in US and Korea, respectively). A variety of applications for the T-HP list is envisaged in nuclear thermal-hydraulics, e.g. a) to address the scaling issue; b) perform uncertainty evaluations; c) to characterize constitutive equations and ‘special models’ for modeling purposes; d) to prioritize research in nuclear reactor thermal-hydraulics.
Thermal-hydraulic Phenomena List
D'Auria F.
Primo
Writing – Original Draft Preparation
;
2020-01-01
Abstract
A list of 116 Thermal-Hydraulic Phenomena T-HP is derived 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 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). A dozen WCNR types are considered: Pressurized Water Reactors (PWR), Boiling Water Reactors (BWR), Russian designs (VVER-440, VVER-1000 and RBMK), pressure tube heavy water reactor designs by Canada (CANDU) and India (PHWR) and so-called ‘advanced’ reactors (e.g. AP-1000 and APR-1400 designed in US and Korea, respectively). A variety of applications for the T-HP list is envisaged in nuclear thermal-hydraulics, e.g. a) to address the scaling issue; b) perform uncertainty evaluations; c) to characterize constitutive equations and ‘special models’ for modeling purposes; d) to prioritize research in nuclear reactor thermal-hydraulics.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
