Status of the SAD Project V. Shvetsov, FLNP. SAD Project Objectives Coupling all major components of ADS; Core design, safety assessment, licensing; k.

Slides:



Advertisements
Similar presentations
PAC Nuclear Physics, 1-2 April, 2004 Construction of the IREN source (the theme /2004). Status&perspectives-proposal on the extension W.I.
Advertisements

HZDR FLUKA activities in support of the MYRRHA Project Short summary with a focus on activation problems Anna Ferrari, Stefan Müller, Jörg Konheiser.
SABR REACTOR CORE & TRITIUM BREEDING BLKT W. M. Stacey Georgia Tech September, 2009.
Lesson 17 HEAT GENERATION
Relevant Thermal-Hydraulic Aspects in the Design of the RRR A. Doval, C. Mazufri F.P. Moreno Bariloche, Rio Negro, Argentina.
FLUKA radioprotection calculations Maria – Ana Popovici Politehnica University of Bucharest.
Preliminary T/H Analyses for EFIT-MgO/Pb Reactor Design WP1.5 Progress Meeting KTH / Stockholm, May 22-23, 2007 G. Bandini, P. Meloni, M. Polidori Italian.
EUROTRANS – DM1 RELAP5 Model Evaluation with SIMMER-III Code and Preliminary Transient Analysis for EFIT Reactor WP5.1 Progress Meeting KTH / Stockholm,
INR Pitesti, D. Dobrea, L. Aioanei Task 4.3. Instrumentation Specifications 4. Core C& I devices 5. Primary coolant C&I devices Based on [1], [2] and [3],
Transmutation and ADS Safety Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Transient Analysis for EFIT (ENEA 384MWth 3-Zone core) Safety and.
First Wall Thermal Hydraulics Analysis El-Sayed Mogahed Fusion Technology Institute The University of Wisconsin With input from S. Malang, M. Sawan, I.
Survey of Space Nuclear Power Options. Dr. Andrew Kadak And Peter Yarsky MIT
Thermal Analysis of Helium- Cooled T-tube Divertor S. Shin, S. I. Abdel-Khalik, and M. Yoda ARIES Meeting, Madison (June 14-15, 2005) G. W. Woodruff School.
March 20-21, 2000ARIES-AT Blanket and Divertor Design, ARIES Project Meeting/ARR Status ARIES-AT Blanket and Divertor Design The ARIES Team Presented.
Alternative Energy Sources
Multi-physics coupling Application on TRIGA reactor Student Romain Henry Supervisors: Prof. Dr. IZTOK TISELJ Dr. LUKA SNOJ PhD Topic presentation 27/03/2012.
KIT – University of the State of Baden-Wuerttemberg and National Research Center of the Helmholtz Association Institute for Nuclear and Energy Technologies.
Investigation into the Viability of a Passively Active Decay Heat Removal System In ALLEGRO Laura Carroll, Graduate Physicist Physics & Licensing Team,
Nov. 9-11, 2004, Las Vegas, USA8th OECD/NEA Information Exchange Meeting on P&T1 R&D ACTIVITIES ON ACCELERATOR- DRIVEN TRANSMUTATION SYSTEM IN JAERI Hiroyuki.
Classification of Power Plants
Thermal Hydraulic Simulation of a SuperCritical-Water-Cooled Reactor Core Using Flownex F.A.Mngomezulu, P.G.Rousseau, V.Naicker School of Mechanical and.
Nuclear and Radiation Physics, BAU, 1 st Semester, (Saed Dababneh). 1 Nuclear Fission Q for 235 U + n  236 U is MeV. Table 13.1 in Krane:
High-Power Density Target Design and Analyses for Accelerator Production of Isotopes W. David Pointer Argonne National Laboratory Nuclear Engineering Division.
Why are you trying so hard to fit in, when you were born to stand out?
3D Coupled Fault Modelling for the Gas- cooled Fast Reactor Jason Dunstall KNOO PhD Student (EPSRC Funded) Applied Modelling and Computation Group (AMCG)
DESIGN SUMMARY AND T-H R&D NEEDS OF THE GT-MHR Workshop on R&D in the Areas of Thermal Fluids and Reactor Safety C. B. Baxi General Atomics, San Diego,
Nuclear Energy Options and Project-X Shekhar Mishra Fermilab Yousry Gohar ANL June 7 th 2010.
Exercise 7: Importance biasing Exercise 7: Importance biasing 7th FLUKA Course NEA Paris, Sept.29-Oct.3, 2008.
Neutronics Parameters for Preferred Chamber Configuration with Magnetic Intervention Mohamed Sawan Ed Marriott, Carol Aplin UW Fusion Technology Inst.
MA and LLFP Transmutation Performance Assessment in the MYRRHA eXperimental ADS P&T: 8th IEM, Las Vegas, Nevada, USA November 9-11, 2004 E. Malambu, W.
Study of a new high power spallation target concept
IAEA International Atomic Energy Agency IAEA Activities in the Area of Partitioning and Transmutation Alexander Stanculescu Nuclear Energy Department Nuclear.
4/2003 Rev 2 I.4.8 – slide 1 of 60 Session I.4.8 Part I Review of Fundamentals Module 4Sources of Radiation Session 8Research Reactors IAEA Post Graduate.
Simulations of Accelerator Driven Systems (ADS) Aleksander Polanski Joint Institute for Nuclear Research, Dubna, Russia. The Andrzej Soltan Institute for.
Radiation Test Facilities G. Spiezia. Engineering Department ENEN Radiation tests facilities  Radiation test in the accelerator sector  External facilities.
1 KING FAHD UNIVERSITY CIVIL ENGINEERING DEPARTMENT A New Prefab Panel As a flooring slab Web Grid Core Panel ABDUL FATTAH DARWISH.
The Proposed Materials Test Station at LANSCE Eric Pitcher Los Alamos National Laboratory Presented at the Workshop on High-Power Targetry for Future.
NML High Energy Beam Absorbers and Dump 29-August-2011 Beams-doc-3928.
3. Core Layout The core loading pattern for the proliferation resistant advanced transuranic transmuting design (PRATT) was optimized to obtain an even.
Development of a RELAP5-3D thermal-hydraulic model for a Gas Cooled Fast Reactor D. Castelliti, C. Parisi, G. M. Galassi, N. Cerullo (San Piero A Grado.
Chapter 4. Power From Fission 1.Introduction 2.Characteristics of Fission 3. General Features 4. Commercial Reactors 5. Nuclear Reactor Safety 6. Nuclear.
Safety And Power Multiplication Aspects Of Mirror Fusion-Fission Hybrids K. Noack 1, O. Ågren 1, J. Källne 1, A. Hagnestål 1, V. E. Moiseenko 2 1 Uppsala.
February 21-21, 2008JINR Scientific Council 103-d session IREN project status.
FAST MOLTEN SALT REACTOR –TRANSMUTER FOR CLOSING NUCLEAR FUEL CYCLE ON MINOR ACTINIDES A.Dudnikov, P.Alekseev, S.Subbotin.
Troitsk ADS project Russia Institute for Nuclear Research RAS, Moscow
Physics Design of 600 MWth HTR & 5 MWth Nuclear Power Pack Brahmananda Chakraborty Bhabha Atomic Research Centre, India.
Characteristics of Transmutation Reactor Based on LAR Tokamak Neutron Source B.G. Hong Chonbuk National University.
PAC on Nuclear Physics 20-th Session April 1-2, 2004, Dubna SAD STATUS REPORT ON THE SAD PROJECT & LONGTIME PERSPECTIVES V. Shvetsov FLNP.
MASSIMO (Measurements in Adapted Spectra of Spectral Indices and Material Oscillations): A Proposed Experimental Campaign at the NRAD Reactor.
Mitja Majerle for the “Energy Plus Transmutation” collaboration.
KIT TOWN OFFICE OSTENDORFHAUS Karlsruhe, 21 st November 2012 CIRTEN Consorzio universitario per la ricerca tecnologica nucleare Antonio Cammi, Stefano.
UCN Source at the NCSU PULSTAR Reactor Bernard Wehring and Albert Young North Carolina State University International Workshop on Neutron-Antineutron Transition.
Study on the Neutronic Characteristics of Subcritical Reactors Driven by an Accelerated Pulsed Proton Beam Ali Ahmad.
Italian National Agency for New Technologies, Energy and Environment Advanced Physics Technology Division Via Martiri di Monte Sole 4, Bologna, Italy.
A report on the ALISIA Information Day
The ESS Target Station F. Mezei ESS target division NPPatLPS, 2013.
Chemical Properties – Those properties of a substance that describe how it changes while being converted into a different substance.
DCLL TBM Reference Design
The report on the IBR-2 modernization
What are fission and fusion? What fuels a nuclear reaction?
Summary of session 5: Innovative Ideas and New R&D
Integrated Design: APEX-Solid Wall FW-Blanket
Nuclear Power Plant.
Paper 1 Chemistry Exam questions and markschemes to project
SCWR Thermal-Hydraulic Instability Analysis
Jordan University of Science and Technology
JOINT INSTITUTE FOR NUCLEAR RESEARCH
LOW-POWER RESEARCH REACTOR FOR EDUCATION AND TRAINING
TRANSPORTATION CASK AND CONCRETE MODULE DESIGN FOR MANAGING NUCLEAR SPENT FUEL PRODUCED IN BUSHEHR NUCLEAR POWER PLANT A.M. TAHERIAN Iran Radioactive Waste.
Egyptian Atomic Energy Authority (EAEA), Egypt
Presentation transcript:

Status of the SAD Project V. Shvetsov, FLNP

SAD Project Objectives Coupling all major components of ADS; Core design, safety assessment, licensing; k eff control and monitoring; Shielding from high energy neutrons; Experiments on core neutronics, reactivity feedbacks, transmutation reaction rates

Participating Organizations JINR JINR NIKIET NIKIET GSPI GSPI VNIINM VNIINM IA “Mayak” IA “Mayak”

International Cooperation ISTC project, supported by EU (Germany, France, Spain, Sweden) Foreign collaborators supervision on the project Cooperation with EUROTRANS IP within VI FP

Basic Data k eff ~0,95 Fuel loading< 420 kg Fission power27,6 kW Coolingair Core Coolant flow rate, G~ 0,6 kg/s velocity, v10 m/s Presure, P (inlet) 0,12-0,135 MPa Temperature, T (inlet, outlet) 50/96 ºC Target (Pb) Coolant flow rate, G~ 0,0067 kg/s Velocity, v50 m/s Pressure, P (inlet) 0,12-0,135 MPa Temperature, T (inlet, outlet) 50/125 ºC

Core Design Beam input from the bottom Fuel assemblies and lead reflectors not shown

SAD Neutronics Calculated K eff Neutron lifetime 2.4∙10 -5 s Fission power 27.6 kW Averaged neutron flux 1.7∙ /(сm 2 ∙s) Peak factor of heat generation (height) 1.21 Heat generation in SAD parts: Heat generation in SAD parts: Fuel kW Target (neutron and photon from fissions) 97.3 W Core cladding W Side Pb reflector W B 4 C W Concrete W Pudecay ~250 W Fuel Max power density 18 W/cm 3 Max flux of fast neutrons (Е> 0,1 MeV)2.4∙ /(cm 2  s) Max fluence of fast neutrons 8.0∙ /cm 2

SAD Neutronics

Beam Transport Channel

Fuel Element

Fuel Mass share of U and Pu sum, %, not less Pu conditional mass in Pu dioxide, %, not less U conditional mass in U dioxide, % not more Pu conditional mass share to U and Pu sum, %30.0±0.3 Oxygen ratio1.98 Density, g/sm ±0.2 Impurities mass share, %, not more Aluminum0.02 Calcium0.02 Magnesium0.02 Iron0.03 Silicon0.02 Nickel0.02 Chromium0.02 Nitrogen0.01 Carbon0.01 Fluorine + Chlorine0.005 Grain size, µm, not more70

Fuel

Fuel

General Layout Blanket Vert. magnets Shielding

Building

Project Status Technical project of the subcritical blanket: completed; Technical project of the beam line: completed; Technical project of the fuel element: completed; Fuel pellets manufacturing technology: developed; Preproduction batch of the fuel pellets: manufactured; General engineering project: completed; Licensing started some project documents already approved by Rostechnadzor (former Gosatomnadzor)

Technical and Economic Indices Project budget is around 500 M Rubles in 2004 prices Including: Building design & construction 100 MR Reactor 100 MR Fuel 57 MR Beam channel 43 MR

Future Prospects Negotiations with equipment manufacturers and construction firms Working design for “0” level of the building Materials for fuel production Negotiations with AFK-”Sistema” and EUROTRANS Looking for support in Rosatom Project scheduled for 4 years

Conclusion The design stage of the project completed Project is supported by EU During project implementation strong team from JINR and Rosatom organizations was formed In case of decision of financing SAD facility could be put into operation in 4 years