Activation analysis of a tritium breeding blanket in the Korean fusion demonstration reactor using the SuperMC code
1
Citation
10
Reference
10
Related Paper
Citation Trend
Keywords:
Nuclide
Decay heat
Fusion power
Breeder (animal)
Fusion power
Nuclide
Cite
Citations (5)
In previous studies, energy generation in a fusion DEMO reactor was estimated by accounting for prompt heat production only, neglecting the decay heat generated from the decay of radioactive isotopes.In this work, based on a helium-cooled pebble bed (HCPB) ceramic blanket which is one of the European DEMO concepts, the decay heat generated in different components is estimated as a function of cooling time is performed in order to assess its contribution.The code system HERCULES, by coupling the MCNP particle transport and the activation inventory FISPACT, is used for the calculation of prompt energy deposition and decay heat for all components in the HCPB DEMO reactor.It is found that, relative to fusion power of 2.7GW, the activated nuclides generated decay heat are <3% at the cooling time of 1 second assuming a power plant operation scenarios.This study suggests that the material selection has a significant impact on decay heat.
Fusion power
Cite
Citations (2)
Fusion power
Cite
Citations (22)
Breeder (animal)
Cite
Citations (15)
China Fusion Engineering Test Reactor (CFETR) is a major scientific project independently designed and developed by China, which will demonstrate the engineering feasibility of continuous large-scale fusion energy for safe and stable power generation. One of the most critical issues for fusion reactors is to achieve tritium self-sufficiency with a tritium breeding ratio (TBR) of no less than 1.0, as it relates to the ability of the fusion reactor to fulfill the fuel cycle and continue stable operation. Moreover, the release and inventory of tritium is also a significant factor affecting the operation of CFETR. The temperature distribution inside the breeder blanket is precisely related to the tritium release. Therefore, it is particularly important for CFETR to optimize the temperature field inside the breeding blanket. It is significant that to ensure that the temperature of the mixed pebble bed zone reaches the limit of 900 °C as much as possible, which could maximize the tritium release efficiency. Simultaneously, it must make sure that other structural materials meet the allowable value of temperature. Tritium accumulation close to the cooling pipe is investigation, which will be adverse to tritium release. Hence, in order to solve this difficulty, the Be12 Ti tube was sleeved on the cooling pipe to increase the temperature of the mixed pebble bed zone near the cooling pipe. In this work, a water-cooled solid breeder blanket was proposed and the nuclear heat was calculated based on the 1.5 GW fusion power. The nuclear heat was used as the preprocessing data for thermal calculation carried out by the Monte Carlo N-Particle Transport Code (MCNP). With the given conditions, the thermal hydraulic was simulated with the commercial CFD code, the ANSYS CFX. In this way, a breeding blanket structure with a uniform temperature field of mixed bed zone close to 900 °C can be obtained. In addition, the selection of Be12 Ti tubes with the thickness of 0.525 cm can ensure a high TBR and increase the temperature around the cooling tubes to improve the tritium release efficiency. This work provides an important reference for the subsequent engineering design of CFETR breeding blanket.
Breeder (animal)
Fusion power
Decay heat
Cite
Citations (4)
Nuclide
Decay heat
Fusion power
Cite
Citations (1)
Breeder (animal)
Decay heat
Fusion power
Shut down
Cite
Citations (2)
The nuclear performance of the ELMO Bumpy Torus Reactor reference design has been calculated using the one-dimensional discrete ordinates code ANISN and the latest available ENDF/B-IV transport cross-section data and nuclear response functions. The calculated results include estimates of the spatial and integral heating rate with emphasis on the recovery of fusion neutron energy in the blanket assembly and minimization of the energy deposition rates in the cryogenic magnet coil assemblies. The tritium breeding ratio in the natural lithium-laden blanket was calculated to be 1.29 tritium nuclei per incident neutron. The radiation damage in the reactor structural material and in the magnet assembly is also given.
Neutron Transport
Fusion power
Nuclear data
Cite
Citations (1)
Nuclide
Neutron Transport
Decay heat
Fusion power
Cite
Citations (18)
Breeder (animal)
Neutron Transport
Fusion power
Water cooled
Decay heat
Cite
Citations (42)