Ukraine: Passive shutdown of NBW fast reactor using the Autonomous Reactivity Control (ARC) system
Description
We present the results of computer simulation of the ARC system performance in the NBW reactor at the loss of flow accident in the second cooling circuit and during the restart of reactor operation after the accident. The problem is studied by means of numerical simulation of the NBW propagation in such a reactor with the depleted uranium metallic fuel and sodium as a coolant. For the neutronics simulation we use the deterministic approach based on solving the non-stationary neutron diffusion equation using the effective multi-group approximation together with a set of burn-up equations for fuel components and equations of nuclear kinetics for precursor nuclei of delayed neutrons. These calculations are complemented with the thermal-hydraulics simulation of the first sodium coolant circuit in the interaction with ARC system. Our simulation shows that ARC system shutdowns the reactor in a few minutes without fuel and coolant overheating. We analysed also the interference between two negative reactivity feedback mechanisms inherent to the NBW reactor and ARC system, which appears in the form of certain oscillations of the flux in a few days after the reactor shutdown. As a result of this interference, the system stabilizes automatically at the acceptable temperature (below 550 ºC) when almost all intermediate isotope neptunium decays into plutonium
Files
47013941.pdf
Files
(137.6 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:3afcb9a323e0ab6e47521b6c5f0577f2
|
137.6 kB | Preview Download |
Additional details
Identifiers
Publishing Information
- Imprint Title
- Technical Meeting on Passive Shutdown Systems for Liquid Metal-Cooled Fast Reactors. Working Material
- Imprint Pagination
- 26 p.
- Journal Page Range
- p. 15
- Report number
- TWG-FR--156
Conference
- Title
- Technical Meeting on Passive Shutdown Systems for Liquid Metal-Cooled Fast Reactors
- Dates
- 20-22 Oct 2015
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 47013941
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; COMPUTERIZED SIMULATION; DELAYED NEUTRONS; FAST REACTORS; LOSS OF FLOW; NEUTRON DIFFUSION EQUATION; REACTOR CORES; REACTOR INSTRUMENTATION; REACTOR OPERATION; RHR SYSTEMS; SCRAM; SODIUM; SODIUM COOLED REACTORS; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; ALKALI METALS; BARYONS; COOLING SYSTEMS; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ELEMENTARY PARTICLES; ELEMENTS; ENERGY SYSTEMS; EPITHERMAL REACTORS; EQUATIONS; FERMIONS; FISSION NEUTRONS; FLUID MECHANICS; HADRONS; HYDRAULICS; LIQUID METAL COOLED REACTORS; MECHANICS; METALS; NEUTRONS; NUCLEONS; OPERATION; PARTIAL DIFFERENTIAL EQUATIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR SHUTDOWN; REACTORS; SHUTDOWN; SIMULATION
Optional Information
- Secondary number(s)
- IAEA-TM--50159