Preliminary Safety Performance Assessment of ESFR CONF-2 Sphere-Pac-Fueled Core
Creators
- 1. Kungliga Tekniska Högskolan, Stockholm (Sweden)
- 2. LeadCold Reactors, Stockholm (Sweden)
Description
A preliminary safety assessment of the CONF-2 version of the European Sodium Fast Reactor core loaded with both pellet and sphere-pac fuels was performed. The reference Unprotected Loss Of Flow (ULOF) and an Unprotected Transient Over-Power (UTOP) accidents were simulated, along with a set of sensitivity studies aimed at evaluating the influence of uncertainties affecting both safety coefficients and the fuel thermal conductivity. Among the major outcomes, it could be preliminarily concluded that the use of sphere-pac fuel may bring some disadvantages from the safety point of view in the event of a UTOP accident, whereas no concerns are raised for a ULOF scenario. Consistently, uncertainties in the determination of the fuel thermal conductivity and Doppler constant were found to have no significant impact on the ULOF transient predictions, but to influence the UTOP simulations, making their accurate determination critical for the system safety assessment. (author)
Additional details
Identifiers
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- ISBN
- 978-92-0-108618-1
- Imprint Title
- Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Proceedings of an International Conference. Companion CD-ROM
- Imprint Pagination
- [1 CD-ROM]
- Series
- Proceedings Series
- Journal Page Range
- 11 p.
- ISSN
- 0074-1884
Conference
- Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development
- Acronym
- FR17
- Dates
- 26-29 Jun 2017
- Place
- Yekaterinburg (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51006280
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; FAST REACTORS; FORECASTING; LOSS OF FLOW; NUCLEAR FUELS; REACTOR CORES; RISK ASSESSMENT; SAFETY; SENSITIVITY ANALYSIS; SODIUM COOLED REACTORS; THERMAL CONDUCTIVITY
- Descriptors DEC
- ACCIDENTS; ENERGY SOURCES; EPITHERMAL REACTORS; FUELS; LIQUID METAL COOLED REACTORS; MATERIALS; PHYSICAL PROPERTIES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SIMULATION; THERMODYNAMIC PROPERTIES
Optional Information
- Notes
- 12 refs., 7 figs., 5 tabs.
- Secondary number(s)
- IAEA-CN--245-428