AMSTRAMGRAM AMélioration de la Section Thermique de capture l’Américium 241 par Mesure intéGRAle dans MINERVE P. Leconte CEA (SPRC/LEPh) A. Gruel, B.

Slides:



Advertisements
Similar presentations
1 Modal methods for 3D heterogeneous neutronics core calculations using the mixed dual solver MINOS. Application to complex geometries and parallel processing.
Advertisements

Combined evaluation of PFNS for 235 U(n th,f), 239 Pu(n th,f), 233 U(n th,f) and 252 Cf(sf) (in progress) V.G. Pronyaev Institute of Physics.
-1- IAEA-ICTP Workshop on Nuclear Reaction Data for Advanced Reactor Technologies ICTP – Trieste, Italy, May 2008 Gas-Cooled Reactors – International.
EMERALD1: A Systematic Study of Cross Section Library Based Discrepancies in LWR Criticality Calculations Jaakko Leppänen Technical Research Centre of.
PHYSICS DESIGN OF 30 MW MULTI PURPOSE RESEARCH REACTOR Archana Sharma Research Reactor Services Division BHABHA ATOMIC RESEARCH CENTRE, INDIA.
Outlook for the Requirements of the Nuclear Power Plant Irradiation Test in China SONG DANRONG Nuclear Power Institute of China.
SABR FUEL CYCLE C. M. Sommer, W. M. Stacey, B
Multi-physics coupling Application on TRIGA reactor Student Romain Henry Supervisors: Prof. Dr. IZTOK TISELJ Dr. LUKA SNOJ PhD Topic presentation 27/03/2012.
1Managed by UT-Battelle for the U.S. Department of Energy Simulation of βn Emission From Fission Using Evaluated Nuclear Decay Data Ian Gauld Marco Pigni.
1 MCNP simulation of salt channel in LR-0 reactor 12th session of the AER Working Group F - "Spent Fuel Transmutations" and 3rd meeting of INPRO Project.
Evaluation and Use of the Prompt Fission Neutron Spectrum and Spectra Covariance Matrices in Criticality and Shielding I. Kodeli1, A. Trkov1, R. Capote2,
Fundamentals of Neutronics : Reactivity Coefficients in Nuclear Reactors Paul Reuss Emeritus Professor at the Institut National des Sciences et Techniques.
USE OF VVER SPENT FUELS IN A THORIUM FAST BREEDER P. Vértes, KFKI Atomic Energy Research Institute, Budapest, Hungary 17 th AER Symposium Yalta,
Nuclear Data for ADS and Transmutation Joint TREND/SANDAT proposal for FP6 ADOPT- Meeting, Dec E. Gonzalez-Romero (CIEMAT) Introduction Sensitivity.
Some fission yields for 235U (n,f), 239Pu (n,f), 238U (n,f) reactions in ΣΣ neutron spectrum Dr. Cristina Garlea National Institute for R&D of Physics.
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.
1 Low Neutron Energy Cross Sections of the Hafnium Isotopes G. Noguère, A. Courcelle, J.M. Palau, O. Litaize CEA/DEN Cadarache, France P. Siegler JRC/IRMM.
Studies of neutron cross-sections by activation method in Nuclear Physics Institute Řež and in The Svedberg Laboratory Uppsala and experimental determination.
Radiation Heating of Thermocouple above Fuel Assembly.
Chapter 4. Power From Fission 1.Introduction 2.Characteristics of Fission 3. General Features 4. Commercial Reactors 5. Nuclear Reactor Safety 6. Nuclear.
Neutron inelastic scattering measurements at the GELINA facility of EC-JRC-IRMM A. Negret 1, C. Borcea 1, A. Plompen 2 1 NIPNE-HH, Romania 2 EC-JRC-IRMM,
Forschungszentrum Karlsruhe in der Helmholz-Gemeinschaft Karlsruhe Institute of Technology Nuclear Data Library for Advanced Systems – Fusion Devices (FENDL-3)
Walid DRIDI, CEA/Saclay n_TOF Collaboration Meeting, Paris December 4-5, 2006 DAPNIA Neutron capture cross section of 234 U Walid DRIDI CEA/Saclay for.
Status on 25 Mg(n,  ) and neutron flux in 2012 Bologna, 27 November 2013 C. Massimi.
Monte Carlo methods in ADS experiments Study for state exam 2008 Mitja Majerle “Phasotron” and “Energy Plus Transmutation” setups (schematic drawings)
Systematic studies of neutrons produced in the Pb/U assembly irradiated by relativistic protons and deuterons. Vladimír Wagner Nuclear physics institute.
Cross-sections of Neutron Threshold Reactions Studied by Activation Method Nuclear Physics Institute, Academy of Sciences of Czech Republic Department.
Advanced Heavy Water Reactor Amit Thakur Reactor Physics Design Division Bhabha Atomic Research Centre, INDIA.
FAST MOLTEN SALT REACTOR –TRANSMUTER FOR CLOSING NUCLEAR FUEL CYCLE ON MINOR ACTINIDES A.Dudnikov, P.Alekseev, S.Subbotin.
AERB Safety Research Institute 1 TIC Benchmark Analysis Subrata Bera Safety Research Institute (SRI) Atomic Energy Regulatory Board (AERB) Kalpakkam –
Physics Design of 600 MWth HTR & 5 MWth Nuclear Power Pack Brahmananda Chakraborty Bhabha Atomic Research Centre, India.
ThEC13, Geneva, 28th-31st Oct., 2013 C. H. Pyeon, Kyoto Univ. 1 Cheolho Pyeon Research Reactor Institute, Kyoto University, Japan
Measurement of 7 Be(n,  ) and 7 Be(n,p) cross sections for the Cosmological Li problem in Addendum to CERN-INTC /INTC-P-417 Spokepersons:
Implementation of an analytical model accounting for sample inhomogeneities in REFIT K. Kauwenberghs EC – JRC – IRMM Standards for Nuclear Safety, Security.
Nuclear Reactors, BAU, 1st Semester, (Saed Dababneh).
Re-analysis of the RRR/SEG Experiments Andrew Hummel Idaho National Laboratory SG39 Meeting NEA Paris, December 4, 2015.
MASSIMO (Measurements in Adapted Spectra of Spectral Indices and Material Oscillations): A Proposed Experimental Campaign at the NRAD Reactor.
Results of First Stage of VVER Rod Simulator Quench Tests 11th International QUENCH Workshop Forschungszentrum Karlsruhe October 25-27, 2005 Presented.
Institute for Reference Materials and Measurements (IRMM) Geel, Belgium CRP Th - U, Vienna December 2004.
IEA IMPLEMENTING AGREEMENT ON NUCLEAR TECHNOLOGY OF FUSION REACTORS International Workshop on Subtask Neutronics Report on ENEA activity in 2004 Paola.
UCN Source at the NCSU PULSTAR Reactor Bernard Wehring and Albert Young North Carolina State University International Workshop on Neutron-Antineutron Transition.
Presentation for WPEC/SG39 meeting, 2015 Nov.30 th to Dec. 4 th Paris, France 1/20 A Stress Test on 235 U(n, f) in adjustment with HCI and HMI benchmarks.
1 FRENCH ATOMIC ENERGY COMMISION (CEA) - NUCLEAR ENERGY DIVISION Nuclear Data Needs, SG26, NEA data bank, 3 May 2006CEA/DER Cadarache Centre Gérald Rimpault.
Monte-Carlo calculations in reactor design G.B. Bruna FRAMATOME-ANP.
Comparison of deterministic and Monte Carlo sensitivity analysis including SAD/SED Ivo Kodeli, SG39 Meeting, NEA, Dec. 4, 2015.
Development of a Data-Based Fission Fragment Generator using the Geant4 Framework FISSION FRAGMENT GENERATOR Idaho State UniversityBrycen Wendt.
School of Mechanical and Nuclear Engineering North-West University
1st Meeting of WPEC Subgroup 26 (May 3, 2006) Proposed Agenda 9:00-9:30 Objectives of the meeting, methodology and relation with HPRL (M.Salvatores, G.Palmiotti,
The design of a hybrid FNS "fusion-fission" system for manufacture of artificial nuclear fuel and nuclide transmutation is actual [1-4]. At a stage of.
NEAR-COMPLETE TRANSURANIC WASTE INCINERATION IN THORIUM-FUELLED LIGHT WATER REACTORS Ben Lindley.
Report (2) on JPARC/MLF-12B025 Gd(n,  ) experiment TIT, Jan.13, 2014 For MLF-12B025 Collaboration (Okayama and JAEA): Outline 1.Motivation.
M-C simulation of reactor e flux;
Study on Neutronics of plutonium and Minor Actinides Transmutation in Accelerator Driven System Reactor By Amer Ahmed Abdullah Al-Qaaod Ph.D student Physics.
of the Muse-4 Experiments with the JEF-2.2 and JEFF-3.1 libraries
Measurement of the fission cross-section of 240Pu and 242Pu at CERN’s n_TOF facility CERN-INTC , INTC-P-280 Spokespersons: M. Calviani (CERN),
Bayesian Monte-Carlo and Experimental Uncertainties
CHEM 312: Lecture 19 Forensics in Nuclear Applications
Paul Scherrer Institut
M-C simulation of reactor e flux;
Overview of Serpent related activities at HZDR E. Fridman
for collaboration “Energy plus transmutation”
Analysis of Reactivity Insertion Accidents for the NIST Research Reactor Before and After Fuel Conversion J.S. Baek, A. Cuadra, L-Y. Cheng, A.L. Hanson,
Measurements of the 238U radiative capture cross section using C6D6
Susan Hogle, Julie G. Ezold
Jordan University of Science and Technology
Pebble Bed Reactors for Once Trough Nuclear Transmutation
Sensitivity analysis in burnup calculations with Monte Carlo
LOW-POWER RESEARCH REACTOR FOR EDUCATION AND TRAINING
Design of A New Wide-dynamic-range Neutron Spectrometer for BNCT with Liquid Moderator and Absorber S. Tamaki1, I. Murata1 1. Division of Electrical,
O. Svoboda, A. Krása, A. Kugler, M. Majerle, J. Vrzalová, V. Wagner
Presentation transcript:

AMSTRAMGRAM AMélioration de la Section Thermique de capture l’Américium 241 par Mesure intéGRAle dans MINERVE P. Leconte CEA (SPRC/LEPh) A. Gruel, B. Geslot CEA (SPEx/LPE) L. Mathieu CNRS/CENBG A. Plompen, P. Siegler IRMM NEEDS meeting, Paris, 07-08 january 2016

OUTLINE Context Design of the experimental program Preliminary results Conclusions CEA | 10 AVRIL 2012

NEEDS Project CEA + IRMM + CNRS CONTEXT Collaborative framework NEEDS Project CEA + IRMM + CNRS Improvement of thermal capture xs of Am241 to solve integral vs microscopic inconsistencies CHANDA/WP12 Project CIEMAT + CEA + IRMM Work on samples of common interest for consistent measurement by TOF and oscillation techniques: Am241 and Tc99 I3P CEA + EDF + AREVA Improvement of nuclear data for the validation of the APOLLO2/JEFF3.1.1 code package NEEDS meeting, Paris, 07-08 january 2016

Current status of evaluations and covariances CONTEXT Current status of evaluations and covariances 99Tc thermal capture 241Am thermal capture JEF-2.2 19.1 b 22.8 ± 1.2 b ENDF/B-VII.0 JEFF-3.1 22.8 b 20.0 ± 1.2 b ENDF/B-VII.1 JEFF-3.2 21.0 b 23.6 b JENDL-4.0 241Am and 99Tc capture are involved in several situations Reactivity of MOX assemblies (Am) Cycle length (both) Burn-Up Credit (both) Both isotopes show differences higher than 5% on the thermal value NEEDS meeting, Paris, 07-08 january 2016

OUTLINE Context Design of the experimental program Preliminary results Conclusions CEA | 10 AVRIL 2012

DESIGN OF THE EXPERIMENTAL PROGRAM Sample availability Samples from IRMM (Geel, Belgium) 7 americium oxide in Al2O3 matrix + 3 « dummies » (Al2O3 only) 10 technetium oxide (without matrix) Samples from past MINERVE programmes Burn-Up Credit (natUO2 + 99Tc) OSMOSE (natUO2 + 241Am)  30 mg 241Am / sample  1g 99Tc / sample 10 cm 1 cm  2g 99Tc  60 – 200 mg NEEDS meeting, Paris, 07-08 january 2016

DESIGN OF THE EXPERIMENTAL PROGRAM Core configuration Main goal Highest precision (so sensitivity) on the thermal capture cross-section of 241Am and 99Tc Target uncertainty on integral capture cross section: <3% Reactivity worth measurements by the pile-oscillation technique  Mesurements in an over-thermalized spectrum Lattice with a water hole at the center New configuration of the MINERVE reactor Exp. zone: MAESTRO AMSTRAMGRAM NEEDS meeting, Paris, 07-08 january 2016

Overall reactivity worth energy distribution DESIGN OF THE EXPERIMENTAL PROGRAM Sensitivity calculations Overall reactivity worth energy distribution NEEDS meeting, Paris, 07-08 january 2016

DESIGN OF THE EXPERIMENTAL PROGRAM Experimental techniques Lattice neutronic characterization Activation foils (Au, In, Ni…) (238U capture rate / total fission) ratio γ-spectrometry on fuel pins around the water hole Integral xs measurements Oscillations (reactivity effect) Neutron activation (capture rate measurement) Fission cross section ratio measurements 241Am/235U -> special fission chambers with absolute mass deposit calibration NEEDS meeting, Paris, 07-08 january 2016

DESIGN OF THE EXPERIMENTAL PROGRAM Mechanical design So… … heterogeneous designs … have to fit in a single common device … in which we can pile-up samples … that must be easy to handle … and must remain watertight  watertight sample holder + aluminum wedges for axial positionning  new oscillating rod larger diameter, watertight  new central device aluminum cylinder NEEDS meeting, Paris, 07-08 january 2016

DESIGN OF THE EXPERIMENTAL PROGRAM Mechanical design Am and calibration samples New containers for: void samples (ref.) Al2O3 samples (ref.) Calibration samples + Al wedges of differents sizes NEEDS meeting, Paris, 07-08 january 2016

DESIGN OF THE EXPERIMENTAL PROGRAM Mechanical design Tc samples New containers for: void samples (ref.) + special Al wedges of different sizes

DESIGN OF THE EXPERIMENTAL PROGRAM Mechanical design Calibration samples To avoid the determination of absolute reactivity worrth, all measurements are normalised with calibration samples  Must be neutron standard isotopes + to fullfill our mechanical constraints must be: easy to manufacture as metallic foils not too expansive… Gold Usually used in past programs Easy to manufacture Easy to handle Other isotope ? Lithium was chosen NEEDS meeting, Paris, 07-08 january 2016

DESIGN OF THE EXPERIMENTAL PROGRAM Neutronic design 1st step: critical configuration Find the number of fuel elements that will fullfill all safety criterias keff all absorbers out Control rods reactivity worth keff of exp. lattice surrounded by graphite %fission in breeding zone 3 types of fuel assemblies 3% UO2 fuel pins 90% and 93% MTR assemblies Keep as possible the core symmetry  Based on MCNP calculations NEEDS meeting, Paris, 07-08 january 2016

DESIGN OF THE EXPERIMENTAL PROGRAM Neutronic design 2nd step: samples reactivity worth Range of measurement Δρ ≈ 1 to 10 pcm Typical uncertainty of ±0.01 pcm MC direct calculations  numerical CV ≈ 3 pcm on keff For Am and Tc MCNP calculations for safety purposes (no choice in the masses) Results were controled with the newly implemented IFP-perturbation method in TRIPOLI4 For Au and Li Calculations for mass determination  MC T4 IFP calculations NEEDS meeting, Paris, 07-08 january 2016

DESIGN OF THE EXPERIMENTAL PROGRAM Neutronic design Reactivity worth of samples IRMM samples 7 241Am containers MCNP, direct calculation: -2.1 ± 3 pcm TRIPOLI4, IFP-perturbation calculation: -2.08 ± 0.02 pcm 10 99Tc containers MCNP, direct calculation: -18.4 ± 3 pcm Calibration samples (10 mm) 7 natAu disk (thick. 0.25 mm) TRIPOLI4, IFP-perturbation calculation: -11.7 ± 0.2 pcm 7 natAu disk (thick. 0.125 mm) TRIPOLI4, IFP-perturbation calculation: -6.4 ± 0.1 pcm 5 natLi disk (thick. 0.6 mm) TRIPOLI4, IFP-perturbation calculation: -10.6 ± 0.2 pcm 7 natLi disk (thick. 0.2 mm) -5.9 ± 0.1 pcm NEEDS meeting, Paris, 07-08 january 2016

OUTLINE Context Design of the experimental program Preliminary results Conclusions CEA | 10 AVRIL 2012

PRELIMINARY RESULTS (1/2) 241Am results NEEDS meeting, Paris, 07-08 january 2016

PRELIMINARY RESULTS (2/2) 99Tc results NEEDS meeting, Paris, 07-08 january 2016

OUTLINE Motivation for new measurements on Am and Tc Design of the experimental program Preliminary results Conclusions CEA | 10 AVRIL 2012

AMSTRAMGRAM: a challenging program CONCLUSIONS AMSTRAMGRAM: a challenging program Unusual sample size and mass Lots of mechanical devices to design (most of them from scratch)  Experiments are ongoing till end of february A future experimental phase is under consideration Supplying of an Am241 source for neutron activation experiment Manufacturing of a flat fission chamber for capture and fission measurements with the same sample A possible extension to the fast energy range with TAPIRO (ENEA) Transport of Am caps to TAPIRO for neutron activation experiments NEEDS meeting, Paris, 07-08 january 2016