1 / 18

Ali Ahmad

Study on the Neutronic Characteristics of Subcritical Reactors Driven by an Accelerated Pulsed Proton Beam. Ali Ahmad. Motivation The Simulation Set-up Results & Analysis Conclusions. Outline. Three main components: Accelerator Spallation target Subcritical core

jin
Download Presentation

Ali Ahmad

An Image/Link below is provided (as is) to download presentation Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author. Content is provided to you AS IS for your information and personal use only. Download presentation by click this link. While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server. During download, if you can't get a presentation, the file might be deleted by the publisher.

E N D

Presentation Transcript

  1. Study on the Neutronic Characteristics of SubcriticalReactors Driven by an Accelerated Pulsed Proton Beam Ali Ahmad

  2. Motivation The Simulation Set-up Results & Analysis Conclusions Outline

  3. Three main components: Accelerator Spallation target Subcritical core Possible deployment of thorium fuel cycle www.thorea.org ADSR in question?

  4. Motivation : Why pulsed beam operation? • LINAC is expensive • Classic cyclotron technology is mature and approaching its power limit • FFAG has the potential to be both affordable and technologically capable of doing the job (Takahishi. 2001) • FFAG is a pulsed accelerator

  5. Motivation : cont.Why is neutronic analysis required? • Pulsed proton beam means pulsed production of spallation neutrons • Oscillations in the power profile are inevitable • Frequent and rapid temperature transients • Thermal cyclic fatigue • Modeling of flux variation with time is needed

  6. The Simulation Set-up • Simulations performed using the MCNPX neutron transport code. • En < 20 MeV : Nuclear data tables (ENDF/B-VI) • En > 20 MeV : Nuclear models • Bertini Model (Bertini 1969) • Delayed neutrons and thermal treatment are included

  7. The Simulation Setup…cont • Reactor Materials: - Target: Pb-208 - Fuel: Th-Pu MOX - Clad: Stainless steel - Coolant: Pb-208 / Water - Radiation shield: Lead • Core arrangement: - Core geometry: hexagonal - Bundle geometry: hexagonal - Number of bundles: 125 - Number of fuel pins: 96 - Fuel active height = 202 cm

  8. Results & Analysis (1) : Neutron spectrum evolution

  9. Results & Analysis (1) : Neutron spectrum evolution • Very fast neutrons (En > 20 MeV) decay in less than 30 ns • This means that primary neutrons aren’t of interest to the core neutronics study • Hypothesis: Neutron generators can be used instead of a proton beam to study neutrons’ kinetic characteristics

  10. Results & Analysis (1) …cont • 14 MeV DT-n-source and beam-operated n-source have very similar core neutronic characteristics • A 14 MeV n-source can potentially replace the proton accelerator in an ADSR for research purposes • Similar results have been obtained by Yamamoto & Shiroya (2003)

  11. Results & Analysis (2) : Spatial variations and diffusion • The diffusion of neutrons in a thermal ADSR is characterised by: - The spallation neutrons are dominant for a period τ  10 µs - After that time, the fission neutrons become dominant

  12. Results & Analysis (2) : ... cont • A pulsed beam of frequency 1 kHz almost allows four orders of magnitude reduction in the neutron flux level in a fast ADSR • The sharp decrease in the neutron flux in a fast ADSR is instantaneous in all assemblies • The perturbation in the neutron flux due to a 1 kHz beam in a thermal ADSR is observed only in the assemblies close to the target • After a few pulses, the fission neutrons become dominant elsewhere Thermal Fast

  13. Results & Analysis (3) : Monitoring of ADSR reactivity • The ideal monitoring of core reactivity should be: • On-line • Accurate • Simple and robust measurement technique • Experiments done to measure the subcritical reactivity: • MUSE (Billeboud et al. 2003) • YALINA (Fernandez-Ordonez et al. 2003) • None of the experimental techniques meet all of the requirements

  14. Results & Analysis (3) : Cont. • All of the proposed techniques rely on deliberate gaps in the beam to measure the subcritical reactivity • The diffusion equation in a thermal ADSR: • Using • At a certain spatial position in the reactor (detector position):

  15. Results & Analysis (3) : Cont. • For the case when the beam is off the last equation has the solution: • Using the definition of neutron life time: • Then, • Define • α can be estimated from the flux decrease rate when the beam is off

  16. Results & Analysis (3) : Cont. • Once the neutron life time of a certain core configuration is known, a reactivity measurement will be straightforward • To perform on-line measurement of Keff in a thermal ADSR, the separation time between pulses should be more than several tens of microseconds

  17. Conclusions • Experimental investigations of the neutronic transients in an ADSR can be done through a relatively cheap neutron source • In a thermal ADSR the diffusion time of spallation neutrons is around 10 microseconds, while it is much quicker in a fast ADSR • The flux fluctuations due to pulsed operation are almost independent of the spatial position in a fast ADSR • The reactivity of a thermal ADSR can be measured on-line if the beam frequency is less than 10 kHz • The next step in my research is to study the thermal issues related to pulsed operation and their consequences Thank you

More Related