Published May 2017 | Version v1
Miscellaneous

Influence of Relief Valves Operation in ITER Vacuum Vessel Pressure Suppression System during Hydrogen and Dust Explosion Accident

  • 1. Ulsan National Institute of Science and Technology(UNIST), Ulsan (Korea, Republic of)

Description

Safety is regarded as one of the highest priorities in nuclear industries. Several safety systems and alternative methods for generating electricity were studied after the Fukushima nuclear accident, including nuclear fusion reactor. ITER, an international nuclear fusion research project, holds no exception in safety since it may cause radiological risk to the public. ITER presented Accident Analysis Report(AAR) which demonstrated safety analysis for design basis accidents and beyond design basis accidents(BDBA) that could occur in the fusion reactor. Safety analysis of hydrogen and dust explosion in ITER vacuum vessel accident was performed using MELCOR code. The rapid pressurization of the VV induced confinement barrier rupture creating a penetration line into the port cell and NBI cell. The accident transient was similar with the results presented in ITER AAR. However, at accident situations such as the Fukushima accident where external power supply is blocked, the accident consequences may vary from the AAR results since less safety systems are under operation. Therefore, simulation with larger relief valve flow area was conducted as a comparative study. As a result, larger relief flow area condition guaranteed bigger pressure relief which lead to less radioactive material release into the environment. For future study in nuclear fusion research, various options for current safety system conditions must be evaluated to assure safety at any accident scenarios.

Part of:
Proceedings of the KNS 2017 Spring Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS 2017 Spring Meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[4 p.]

Conference

Title
2017 Spring Meeting of the KNS
Dates
17-19 May 2017
Place
Jeju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
49050519
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPARATIVE EVALUATIONS; DUSTS; ENGINEERED SAFETY SYSTEMS; EXPLOSIONS; HYDROGEN; ITER TOKAMAK; NUCLEAR INDUSTRY; RELIEF VALVES; SAFETY
Descriptors DEC
CLOSED PLASMA DEVICES; CONTROL EQUIPMENT; ELEMENTS; EQUIPMENT; EVALUATION; FLOW REGULATORS; INDUSTRY; NONMETALS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; VALVES

Optional Information

Notes
5 refs, 8 figs, 1 tab