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