Assessment of Gamma Sensitivity of Platinum SPGD using Monte Carlo Method ,,,,,,

Size: px
Start display at page:

Download "Assessment of Gamma Sensitivity of Platinum SPGD using Monte Carlo Method ,,,,,,"

Transcription

1 2003 Monte Carlo Assessment of Gamma Sensitivity of Platinum SPGD using Monte Carlo Method,,,,,, Monte Carlo MCNP 4 5 H1-type Instrumentation Thimble MCNP Gamma Source Insulator Electron Charge Effect f-factor A( /cm 2 ) 1 MeV (Emitter, Insulator, Collector, Insulator Charge ) Abstract Gamma sensitivities depending on energy groups of Platinum incore detectors are calculated using the Monte Carlo transport calculation H1-type fuel assembly loaded in Yonggwang Unit 4 cycle 5 is modelled by MCNP4B code to get gamma spectrum in instrumentation thimble region and then calculated gamma spectrum is used as a source term for gamma sensitivity of Pt detector In addition, f-factor was defined to consider the effect of electron charge in insulator region Resulting energy dependent gamma sensitivity was about A( /cm 2 ) per unit length Generally, sensitivity is primarily dependent on gamma or neutron spectrum in sensitivity calculation, thus the accurate spectrum around detector assembly and optimizing the variables affected sensitivity like as density and size of emitter, insulator and collector, charge distribution in the insulator, and minimizing the uncertainties of these variables are required for the exact sensitivity calculation

2 1 (n,e), (g,e), (n,g,e) Platinum 1970 Monte Carlo Transport Code (MCNP MONK) Field Dominic G Napolitano Donald R Harris Seabrook Monte Carlo, SCK CEN, Nuclear Research Center Rh, Co, Hf Emitter Emitter ( ), Platinum LANL (Los Alamos National Laboratory) MCNP4B, H1-type Instrumentation Thimble 2 SPND (Self-Powered Neutron Detectors),,,, /,, Emitter, Emitter Background Noise Emitter < 2-1> Integral SPND (Rhodium )

3 < 2-1> Integral SPND Emitter Insulator Collector ( Sheath) Co-axial Cable SPND Emitter (Rh), (V), (Co), (Hf), (Pt) (Ag), < 2-1> Emitter < 2-1> Element Z V 23 Low depletion Co 27 Large prompt response Rh 45 Very large signal (small uncertainty) Signal interpretation easy Large signal Ag 47 Signal interpretation easy Low depletion Large signal Gd 64 Large prompt response Signal interpretation easy Er 68 Large prompt response Yb 70 Large prompt response Low depletion Hf 72 Large prompt response Pt 78 Large prompt response No depletion Very small signal Prompt response has opposite sign Very small signal Average depletion Small prompt response Average depletion Small prompt response Rapid depletion Rapid depletion Small signal Small signal Small signal Average depletion Small signal Emitter Insulator Collector Collector Insulator Emitter Insulator (+) (-) (n,e), (n,g,e), (g,e) (n,e) SPND Emitter (n,g,e), (g,e) SPGD (Self-Powered Gamma

4 Detector) SPGD Signal-to-Noise Ratio (, Background ) Gamma Spectrum Around the Detector Assembly,,,, ( ) ( ) Instrumentation Thimble H1-type 4 5 < 2-2>, < 2-2> < 2-2> Yonggwang Unit 4 Cycle 5 H1-type FA & 2x2 Instrumentation Thimble MCNP (0699g/cc) Flux Tally (F4:n,p) (Reflective Boundary Condition) < 2-3> Energy (En) Cell Instrumentation Thimble

5 Flux < 2-2> H-type Assembly Description of Yonggwang Unit 4 Assembly Type Fuel Enrichment (wt% U 235 ) No of Fuel Rods per Assembly No of Gd Poison Rods Per Assembly Poison Enrichment (wt% Gd 2O 3) H0 H1 H2 450/ / / /52 176/52 172/ < 2-3> Neutron & Gamma Energy Boundary Upper Energy Group Boundary (ev) Neutron Gamma Group Number 25-G 10-G 18-G E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E E+4 MCNP (Particle Flux), < 2-3> ~ < 2-5> Instrumentation Thimble

6 < 2-3> Instrumentation Thimble (25-Group) < 2-4> Instrumentation Thimble (18-Group) < 2-5> Instrumentation Thimble (10-Group) Charge Distribution in the Insulator (+) (-) Emitter Collector Insulator (Space Charge Field) Insulator Charge Space Charge Trap Energy Band Structure Space Charge Space Charge

7 Quasi-Static Charge Zero Point de dr Concentric Ring Emitter Insulator + E r = ρ (r) ε E (Electric Field) Insulator Potential Difference (zero), = 1 r 1 ro 1 r E ( r) r ρ( r ) dr dr r ρ( r ) dr rε ri ln( r ri ri o / ri ) r Poisson r i, r o Insulator r i~~r o (Critical Radius) Emitter Charge Emitter, f-fraction f ln( ro ) 1 = 1 = n ln( ro / ri ) ln( ro / ri ) n r ln( r ) ρ r = 1 r ρ r f-fraction Insulator 20 (typically n=20 or 30) r (Concentric Ring) Charge ( ) MCNP (,, ) f-fraction < 2-4> Platinum Emitter Insulator Collector Material Platinum Al 2O 3 Inconel Density(g/cc) Length(cm) 40 < 2-6> < 2-4> MCNP Platinum Emitter Platinum 2145g/cc Insulator Al 2O 3 19g/cc Collector Inconel 842g/cc Concentric Ring

8 0025cm-0056cm-0079cm SPND < 2-7> MCNP Insulator Charge Density, ( 3) f-fraction 047 < 2-5> < 2-6>, < 2-4> f=047 Rc : 0079 cm Re : 0025 cm Ri : cm L: 40 cm < 2-6> Platinum < 2-7> Insulator Charge Density Profile Emitter-Insulator Net Current J ei, Insulator-Collector Net Current J ic Emitter Collector Net Current, J ec J ei, J ic MCNP Current Tally MCNP Electron Current J ei, J ic Incoming (cos( )<0) outgoing (cos( )>0) Net Current Upper Limit Energy PHYS:E J ec = J f ( J J ) = (1 f ) J ei ei ic ei Current ( ) + f J ic (n,e) Rhodium Platinum Energy Dependent Gamma Sensitivities of Pt Detector Instrumentation Thimble MCNP SDEF Gamma Source Collector cos( ) Net Current Fn:e, Cn, Ftn elc, ( ) Current ( )

9 ( ) MCNP Gamma Source Collector cos( ) φ = 4/( π d h) d, h 0158cm, 1cm ( 3) f-fraction ( 4) Net Current ( 5) < 2-8 > A( /cm 2 ) 1 MeV (n,e) SPND (10-21 ~ A( /cm 2 )) Photoelectric, Compton Scattering, Pair Production (g,e) High-Z Emitter Low-Z (Surrounding Materials) < 2-8> Energy Dependent Gamma Sensitivities of Pt SPGD 3 Monte Carlo Transport Platinum MCNP4B 4 5 H1-type Instrumentation Thimble Platinum MCNP Insulator Charge f-factor

10 10-23 A( /cm 2 ) SPND (g,e) Emitter-Insulator-Collector Current f-fraction Insulator (Unperturbed Condition) ( ) (Perturbed Condition) 4 1 H D Warren "Calculational Model for Self-Powered Neutron Detector," Nuclear Science and Engineering, 48, p , H D Warren and N H Shah, "Neutron and Gamma-Ray Effects on Self-Powered In-Core Radiation Detectors," Nuclear Science and Engineering, 54, pp , H D Warren and M F Sulcoski, "Performance of Prompt- and Delayed-Responding Self-Powered In-Core Neutron Detectors in a Pressurized Water Reactor," Nuclear Science and Engineering, 86, pp 1-9, D G Napolitano and D R Harris, " Sensitivity of Seabrook Station's Incore Platinum Detectors," Advances in Mathematics, Computations, and Reactor Physics, Topical Meeting, Pittsburgh, PA April 25-May 2, J P Gorski and a G Merrill, "Incore Power Monitoring Using Platinum Incore Detectors at Seabrook Station," Advances in Mathematics, Computations, and Reactor Physics, Topical Meeting, Pittsburgh, PA, April 28-May 2, J P Gorski and R J Cacciapouti, "Experience with Fixed Incore Detectors at Seabrook Station," International Conference on the Physics of Nuclear Science and Technology, Long Island, NY, October 5-8, R J Cacciapouti and J P Gorski, "Experience with Fixed Platinum Incore Detectors," Core Monitoring for Commercial Reactors: Improvements in Systems and Methods, Stockholm, Sweden, October 4-5, S Levy et al, "Integral Transport Computation of Gamma Detector Response With the CPM2 Code," EPRI NP-6527, Proect , Final Report, December J F Briesmeister, "MCNP - A General Monte Carlo N-Particle Transport Code, version 4B", LA-1265-M,

2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea

2017 Water Reactor Fuel Performance Meeting September 10 (Sun) ~ 14 (Thu), 2017 Ramada Plaza Jeju Jeju Island, Korea Neutronic evaluation of thorium-uranium fuel in heavy water research reactor HADI SHAMORADIFAR 1,*, BEHZAD TEIMURI 2, PARVIZ PARVARESH 1, SAEED MOHAMMADI 1 1 Department of Nuclear physics, Payame Noor

More information

VERIFICATION OF MONTE CARLO CALCULATIONS OF THE NEUTRON FLUX IN THE CAROUSEL CHANNELS OF THE TRIGA MARK II REACTOR, LJUBLJANA

VERIFICATION OF MONTE CARLO CALCULATIONS OF THE NEUTRON FLUX IN THE CAROUSEL CHANNELS OF THE TRIGA MARK II REACTOR, LJUBLJANA International Conference Nuclear Energy for New Europe 2002 Kranjska Gora, Slovenia, September 9-12, 2002 www.drustvo-js.si/gora2002 VERIFATION OF MONTE CARLO CALCULATIONS OF THE NEUTRON FLUX IN THE CAROUSEL

More information

DIRECT EXPERIMENTAL TESTS AND COMPARISON BETWEEN SUB-MINIATURE FISSION CHAMBERS AND SPND FOR FIXED IN-CORE INSTRUMENTATION OF LWR

DIRECT EXPERIMENTAL TESTS AND COMPARISON BETWEEN SUB-MINIATURE FISSION CHAMBERS AND SPND FOR FIXED IN-CORE INSTRUMENTATION OF LWR DIRECT EXPERIMENTAL TESTS AND COMPARISON BETWEEN SUB-MINIATURE FISSION CHAMBERS AND SPND FOR FIXED IN-CORE INSTRUMENTATION OF LWR G. Bignan, J.C. Guyard Commisariat à l Energie Atomique CE CADARACHE DRN/DER/SSAE

More information

USA HTR NEUTRONIC CHARACTERIZATION OF THE SAFARI-1 MATERIAL TESTING REACTOR

USA HTR NEUTRONIC CHARACTERIZATION OF THE SAFARI-1 MATERIAL TESTING REACTOR Proceedings of HTR2008 4 th International Topical Meeting on High Temperature Reactors September 28-October 1, 2008, Washington, D.C, USA HTR2008-58155 NEUTRONIC CHARACTERIZATION OF THE SAFARI-1 MATERIAL

More information

Validation of the MCNP computational model for neutron flux distribution with the neutron activation analysis measurement

Validation of the MCNP computational model for neutron flux distribution with the neutron activation analysis measurement Journal of Physics: Conference Series PAPER OPEN ACCESS Validation of the MCNP computational model for neutron flux distribution with the neutron activation analysis measurement To cite this article: K

More information

MONTE CALRLO MODELLING OF VOID COEFFICIENT OF REACTIVITY EXPERIMENT

MONTE CALRLO MODELLING OF VOID COEFFICIENT OF REACTIVITY EXPERIMENT MONTE CALRLO MODELLING OF VOID COEFFICIENT OF REACTIVITY EXPERIMENT R. KHAN, M. VILLA, H. BÖCK Vienna University of Technology Atominstitute Stadionallee 2, A-1020, Vienna, Austria ABSTRACT The Atominstitute

More information

Felix C. Difilippo. Oak Ridge National Laboratory P.O. Box 2008 Oak Ridge, TN 3783 l-6363 USA

Felix C. Difilippo. Oak Ridge National Laboratory P.O. Box 2008 Oak Ridge, TN 3783 l-6363 USA Design and Effects of the Proton Window of the Spallation Neutron Source Felix C. Difilippo Oak Ridge National Laboratory P.O. Box 2008 Oak Ridge, TN 3783 l-6363 USA Paper to be Presented and Published

More information

Experimental study of the flux trap effect in a sub-critical assembly

Experimental study of the flux trap effect in a sub-critical assembly Experimental study of the flux trap effect in a sub-critical assembly KORNILIOS ROUTSONIS 1,2 S. S T O U L O S 3, A. C L O U VA S 4, N. K AT S A R O S 5, M. VA R VAY I A N N I 5, M. M A N O LO P O U LO

More information

Neutron Dose near Spent Nuclear Fuel and HAW after the 2007 ICRP Recommendations

Neutron Dose near Spent Nuclear Fuel and HAW after the 2007 ICRP Recommendations Neutron Dose near Spent Nuclear Fuel and HAW after the 2007 ICRP Recommendations Gunter Pretzsch Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbh Radiation and Environmental Protection Division

More information

DOPPLER COEFFICIENT OF REACTIVITY BENCHMARK CALCULATIONS FOR DIFFERENT ENRICHMENTS OF UO 2

DOPPLER COEFFICIENT OF REACTIVITY BENCHMARK CALCULATIONS FOR DIFFERENT ENRICHMENTS OF UO 2 Supercomputing in Nuclear Applications (M&C + SNA 2007) Monterey, California, April 15-19, 2007, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2007) DOPPLER COEFFICIENT OF REACTIVITY BENCHMARK

More information

Study on SiC Components to Improve the Neutron Economy in HTGR

Study on SiC Components to Improve the Neutron Economy in HTGR Study on SiC Components to Improve the Neutron Economy in HTGR Piyatida TRINURUK and Assoc.Prof.Dr. Toru OBARA Department of Nuclear Engineering Research Laboratory for Nuclear Reactors Tokyo Institute

More information

Nuclear Fission. 1/v Fast neutrons. U thermal cross sections σ fission 584 b. σ scattering 9 b. σ radiative capture 97 b.

Nuclear Fission. 1/v Fast neutrons. U thermal cross sections σ fission 584 b. σ scattering 9 b. σ radiative capture 97 b. Nuclear Fission 1/v Fast neutrons should be moderated. 235 U thermal cross sections σ fission 584 b. σ scattering 9 b. σ radiative capture 97 b. Fission Barriers 1 Nuclear Fission Q for 235 U + n 236 U

More information

Transmutation of Minor Actinides in a Spherical

Transmutation of Minor Actinides in a Spherical 1 Transmutation of Minor Actinides in a Spherical Torus Tokamak Fusion Reactor Feng Kaiming Zhang Guoshu Fusion energy will be a long-term energy source. Great efforts have been devoted to fusion research

More information

DETERMINATION OF THE SERVICE LIFE FOR THE EXCORE NEUTRON DETECTOR CABLES IN SEABROOK STATION

DETERMINATION OF THE SERVICE LIFE FOR THE EXCORE NEUTRON DETECTOR CABLES IN SEABROOK STATION DETERMINATION OF THE SERVICE LIFE FOR THE EXCORE NEUTRON DETECTOR CABLES IN SEABROOK STATION John R. White and Lee H. Bettenhausen Chemical and Nuclear Engineering Department University of Massachusetts-Lowell,

More information

Air Kerma Primary Standard: Experimental and. Simulation Studies on Cs-137. J. Cardoso, L. Santos, C. Oliveira

Air Kerma Primary Standard: Experimental and. Simulation Studies on Cs-137. J. Cardoso, L. Santos, C. Oliveira Air Kerma Primary Standard: Experimental and Simulation Studies on Cs-137 J. Cardoso, L. Santos, C. Oliveira SUMMARY: i. The primary standard ii. The irradiation room iii. Experimental results iv. Simulation

More information

High precision neutron inelastic cross section measurements

High precision neutron inelastic cross section measurements High precision neutron inelastic cross section measurements A. Olacel, C. Borcea, M. Boromiza, A. Negret IFIN-HH, DFN Outline The experimental setup GELINA GAINS Data analysis algorithm. Monte Carlo simulations

More information

Reactivity Monitoring with Imposed Beam Trips and Pulsed Mode Detectors in the Subcritical Experiment YALINA-Booster

Reactivity Monitoring with Imposed Beam Trips and Pulsed Mode Detectors in the Subcritical Experiment YALINA-Booster 1 ADS/P4-08 Reactivity Monitoring with Imposed Beam Trips and Pulsed Mode Detectors in the Subcritical Experiment YALINA-Booster V. Bécares Palacios 1, M. Fernández Ordóñez 1, D. Villamarín 1, E. M. González

More information

Evaluation of the Nonlinear Response Function and Efficiency of a Scintillation Detector Using Monte Carlo and Analytical Methods

Evaluation of the Nonlinear Response Function and Efficiency of a Scintillation Detector Using Monte Carlo and Analytical Methods Asian J. Exp. Sci., Vol. 28, No. 2, 2014; 23-31 Evaluation of the Nonlinear Response Function and Efficiency of a Scintillation Detector Using Monte Carlo and Analytical Methods Rahim Khabaz, Farhad Yaghobi

More information

Reactors and Fuels. Allen G. Croff Oak Ridge National Laboratory (ret.) NNSA/DOE Nevada Support Facility 232 Energy Way Las Vegas, NV

Reactors and Fuels. Allen G. Croff Oak Ridge National Laboratory (ret.) NNSA/DOE Nevada Support Facility 232 Energy Way Las Vegas, NV Reactors and Fuels Allen G. Croff Oak Ridge National Laboratory (ret.) NNSA/DOE Nevada Support Facility 232 Energy Way Las Vegas, NV July 19-21, 2011 This course is partially based on work supported by

More information

Neutronic Calculations of Ghana Research Reactor-1 LEU Core

Neutronic Calculations of Ghana Research Reactor-1 LEU Core Neutronic Calculations of Ghana Research Reactor-1 LEU Core Manowogbor VC*, Odoi HC and Abrefah RG Department of Nuclear Engineering, School of Nuclear Allied Sciences, University of Ghana Commentary Received

More information

Benchmark Test of JENDL High Energy File with MCNP

Benchmark Test of JENDL High Energy File with MCNP Benchmark Test of JENDL High Energy File with MCNP Masayuki WADA, Fujio MAEKAWA, Chikara KONNO Intense Neutron Source Laboratory, Department of Materials Science Japan Atomic Energy Research Institute,

More information

Problem P7. Stéphanie Ménard. Dosimetry Department Fontenay-aux FRANCE IRSN QUADOS IRSN

Problem P7. Stéphanie Ménard. Dosimetry Department Fontenay-aux FRANCE IRSN QUADOS IRSN Problem P7 Stéphanie Ménard Dosimetry Department 92262 Fontenay-aux aux-roses FRANCE What are the applications of Gamma-Ray Spectrometry in Radiological Protection and in Safety? In the environment: after

More information

Needs for Nuclear Reactions on Actinides

Needs for Nuclear Reactions on Actinides Needs for Nuclear Reactions on Actinides Mark Chadwick Los Alamos National Laboratory Talk at the Workshop on Nuclear Data Needs & Capabilities for Applications, May 27-29, 2015 Nuclear Data for National

More information

Nuclear waste management

Nuclear waste management Nuclear waste management Permanent staff : G. Ban, F-R. Lecolley, J-L. Lecouey, G. Lehaut, N. Marie-Nourry, J-C. Steckmeyer Emeritus : J-F. Lecolley PhD student: H-E. Thyebault Collaborations : LPSC Grenoble,

More information

Int. Coaf. Physics of Nuclear Science and Technology

Int. Coaf. Physics of Nuclear Science and Technology BNL-6 5 2 43 Int. Coaf. Physics of Nuclear Science and Technology October S-8, 1998 RADIATION DOSIMETRY AT THE BNL HIGH FLUX BEAM REACTOR* NE Holden', J-P Hu', RN Reciniello* 1. Reactor Division, Brookhaven

More information

SOME ASPECTS OF MONTE CARLO SIMULATION FOR EFFICIENCY CALIBRATION OF GERMANIUM DETECTORS

SOME ASPECTS OF MONTE CARLO SIMULATION FOR EFFICIENCY CALIBRATION OF GERMANIUM DETECTORS ICRM Gamma Spectrometry Workshop Paris, France 23-24 February 2009 SOME ASPECTS OF MONTE CARLO SIMULATION S.Hurtado Universidad de Sevilla SPAIN 1 MONTE CARLO SIMULATION DISADVANTAGES Self-absorption correction

More information

ARACOR Eagle- Matched Operations and Neutron Detector Performance Tests

ARACOR Eagle- Matched Operations and Neutron Detector Performance Tests Idaho National Engineering and Environmental Laboratory INEEL/EXT-02-00823 June 2002 ARACOR Eagle- Matched Operations and Neutron Detector Performance Tests J. L. Jones K. J. Haskell J. M. Hoggan D. R.

More information

A New MCNPX PTRAC Coincidence Capture File Capability: A Tool for Neutron Detector Design

A New MCNPX PTRAC Coincidence Capture File Capability: A Tool for Neutron Detector Design Abstract A New MCNPX PTRAC Coincidence Capture File Capability: A Tool for Neutron Detector Design L. G. Evans, M.A. Schear, J. S. Hendricks, M.T. Swinhoe, S.J. Tobin and S. Croft Los Alamos National Laboratory

More information

YALINA-Booster Conversion Project

YALINA-Booster Conversion Project 1 ADS/ET-06 YALINA-Booster Conversion Project Y. Gohar 1, I. Bolshinsky 2, G. Aliberti 1, F. Kondev 1, D. Smith 1, A. Talamo 1, Z. Zhong 1, H. Kiyavitskaya 3,V. Bournos 3, Y. Fokov 3, C. Routkovskaya 3,

More information

Universal curve of the thermal neutron self-shielding factor in foils, wires, spheres and cylinders

Universal curve of the thermal neutron self-shielding factor in foils, wires, spheres and cylinders Journal of Radioanalytical and Nuclear Chemistry, Vol. 261, No. 3 (2004) 637 643 Universal curve of the thermal neutron self-shielding factor in foils, wires, spheres and cylinders E. Martinho, J. Salgado,

More information

The Lead-Based VENUS-F Facility: Status of the FREYA Project

The Lead-Based VENUS-F Facility: Status of the FREYA Project EPJ Web of Conferences 106, 06004 (2016) DOI: 10.1051/epjconf/201610606004 C Owned by the authors, published by EDP Sciences, 2016 The Lead-Based VENUS-F Facility: Status of the FREYA Project Anatoly Kochetkov

More information

Measurement and simulation of thermal neutron flux distribution in the RTP core

Measurement and simulation of thermal neutron flux distribution in the RTP core IOP Conference Series: Materials Science and Engineering PAPER OPEN ACCESS Measurement and simulation of thermal neutron flux distribution in the RTP core To cite this article: Mohamad Hairie B. Rabir

More information

MCNP TRANSPORT CODE SYSTEM & DETECTOR DESIGN

MCNP TRANSPORT CODE SYSTEM & DETECTOR DESIGN MCNP TRANSPORT CODE SYSTEM & DETECTOR DESIGN Name: MAHMUT CÜNEYT KAHRAMAN Matr. Nr:4021407 1 CONTENTS 1. Introduction of MCNP Code System 1.1. What is an input file? 1.2. What is an output file? 2. Detector

More information

Validation of the Monte Carlo Model Developed to Estimate the Neutron Activation of Stainless Steel in a Nuclear Reactor

Validation of the Monte Carlo Model Developed to Estimate the Neutron Activation of Stainless Steel in a Nuclear Reactor Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010 (SNA + MC2010) Hitotsubashi Memorial Hall, Tokyo, Japan, October 17-21, 2010 Validation of the Monte Carlo

More information

M.Cagnazzo Atominstitut, Vienna University of Technology Stadionallee 2, 1020 Wien, Austria

M.Cagnazzo Atominstitut, Vienna University of Technology Stadionallee 2, 1020 Wien, Austria Measurements of the In-Core Neutron Flux Distribution and Energy Spectrum at the Triga Mark II Reactor of the Vienna University of Technology/Atominstitut ABSTRACT M.Cagnazzo Atominstitut, Vienna University

More information

Neutronic Design and Analyses of A New Core- Moderator Assembly and Neutron Beam Ports for The Penn State Breazeale Reactor

Neutronic Design and Analyses of A New Core- Moderator Assembly and Neutron Beam Ports for The Penn State Breazeale Reactor Neutronic Design and Analyses of A New Core- Moderator Assembly and Neutron Beam Ports for The Penn State Breazeale Reactor D. Uçar, 1 K. Ünlü, 1,2 B. J. Heidrich, 1 K. N. Ivanov, 2 M. N. Avramova,2 Service

More information

Characteristics of Filtered Neutron Beam Energy Spectra at Dalat Reactor

Characteristics of Filtered Neutron Beam Energy Spectra at Dalat Reactor World Journal of Nuclear Science and Technology, 2014, 4, 96-102 Published Online April 2014 in SciRes. http://www.scirp.org/journal/wjnst http://dx.doi.org/10.4236/wjnst.2014.42015 Characteristics of

More information

2. The Steady State and the Diffusion Equation

2. The Steady State and the Diffusion Equation 2. The Steady State and the Diffusion Equation The Neutron Field Basic field quantity in reactor physics is the neutron angular flux density distribution: Φ( r r, E, r Ω,t) = v(e)n( r r, E, r Ω,t) -- distribution

More information

Neutronics Experiments for ITER at JAERI/FNS

Neutronics Experiments for ITER at JAERI/FNS Neutronics Experiments for ITER at JAERI/FNS C. Konno 1), F. Maekawa 1), Y. Kasugai 1), Y. Uno 1), J. Kaneko 1), T. Nishitani 1), M. Wada 2), Y. Ikeda 1), H. Takeuchi 1) 1) Japan Atomic Energy Research

More information

Quartz-Crystal Spectrometer for the Analysis of Plutonium K X-Rays

Quartz-Crystal Spectrometer for the Analysis of Plutonium K X-Rays Quartz-Crystal Spectrometer for the Analysis of Plutonium K X-Rays Alison V. Goodsell, William S. Charlton alisong@tamu.edu, charlton@ne.tamu.edu Nuclear Security Science & Policy Institute Texas A&M University,

More information

WM2016 Conference, March 6 10, 2016, Phoenix, Arizona, USA. Recovering New Type of Sources by Off-Site Source Recovery Project for WIPP Disposal-16604

WM2016 Conference, March 6 10, 2016, Phoenix, Arizona, USA. Recovering New Type of Sources by Off-Site Source Recovery Project for WIPP Disposal-16604 Recovering New Type of Sources by Off-Site Source Recovery Project for WIPP Disposal-16604 Ioana Witkowski, Anthony Nettleton, Alex Feldman Los Alamos National Laboratory INTRODUCTION TO OSRP ACTIVITIES

More information

PhD Qualifying Exam Nuclear Engineering Program. Part 1 Core Courses

PhD Qualifying Exam Nuclear Engineering Program. Part 1 Core Courses PhD Qualifying Exam Nuclear Engineering Program Part 1 Core Courses 9:00 am 12:00 noon, November 19, 2016 (1) Nuclear Reactor Analysis During the startup of a one-region, homogeneous slab reactor of size

More information

Hybrid Low-Power Research Reactor with Separable Core Concept

Hybrid Low-Power Research Reactor with Separable Core Concept Hybrid Low-Power Research Reactor with Separable Core Concept S.T. Hong *, I.C.Lim, S.Y.Oh, S.B.Yum, D.H.Kim Korea Atomic Energy Research Institute (KAERI) 111, Daedeok-daero 989 beon-gil, Yuseong-gu,

More information

Principles of neutron TOF cross section measurements

Principles of neutron TOF cross section measurements Principles of neutron TOF cross section measurements J. Heyse, C. Paradela, P. Schillebeeckx EC JRC IRMM Standards for Nuclear Safety, Security and Safeguards (SN3S) H.I. Kim Korea Atomic Energy Research

More information

Monte Carlo Method: Theory and Exercises (1)

Monte Carlo Method: Theory and Exercises (1) united nations educational, scientific and cultural organization the abdus salam international centre for theoretical physics international atomic energy agency SMR.1555-12 Workshop on Nuclear Reaction

More information

Considerations for Measurements in Support of Thermal Scattering Data Evaluations. Ayman I. Hawari

Considerations for Measurements in Support of Thermal Scattering Data Evaluations. Ayman I. Hawari OECD/NEA Meeting: WPEC SG42 Thermal Scattering Kernel S(a,b): Measurement, Evaluation and Application May 13 14, 2017 Paris, France Considerations for Measurements in Support of Thermal Scattering Data

More information

Comparison of the Monte Carlo Adjoint-Weighted and Differential Operator Perturbation Methods

Comparison of the Monte Carlo Adjoint-Weighted and Differential Operator Perturbation Methods Progress in NUCLEAR SCIENCE and TECHNOLOGY, Vol., pp.836-841 (011) ARTICLE Comparison of the Monte Carlo Adjoint-Weighted and Differential Operator Perturbation Methods Brian C. KIEDROWSKI * and Forrest

More information

[This is not an article, chapter, of conference paper!]

[This is not an article, chapter, of conference paper!] http://www.diva-portal.org [This is not an article, chapter, of conference paper!] Gamma Emission Tomography of LOCA transient test rods Project title: Development and demonstration of quantitative detail

More information

Introduction. Problem Summary. Attila Code-to-Code Comparison Subcritical Spent Nuclear Fuel Canister with Primary Neutron and Gamma Sources

Introduction. Problem Summary. Attila Code-to-Code Comparison Subcritical Spent Nuclear Fuel Canister with Primary Neutron and Gamma Sources Introduction An example spent nuclear fuel canister calculation was performed with Attila, with results compared to the MCNPX Monte Carlo code. The canister contained representative subcritical neutron

More information

Neutronic studies on a pulsed thermal neutron source based on the Be(p,n) reaction by using a compact proton accelerator

Neutronic studies on a pulsed thermal neutron source based on the Be(p,n) reaction by using a compact proton accelerator Available online at www.sciencedirect.com Physics Procedia 26 (2012 ) 88 96 Union of Compact Accelerator-Driven Neutron Sources I & II Neutronic studies on a pulsed thermal neutron source based on the

More information

KamLAND. Studying Neutrinos from Reactor

KamLAND. Studying Neutrinos from Reactor KamLAND : Studying Neutrinos from Reactor Atsuto Suzuki KEK : High Energy Accelerator Research Organization KamLAND Collaboration Outline 1. KamLAND Overview 2. Reactor Neutrinos 3. e Detection in Liquid

More information

A Dummy Core for V&V and Education & Training Purposes at TechnicAtome: In and Ex-Core Calculations

A Dummy Core for V&V and Education & Training Purposes at TechnicAtome: In and Ex-Core Calculations A Dummy Core for V&V and Education & Training Purposes at TechnicAtome: In and Ex-Core Calculations S. Nicolas, A. Noguès, L. Manifacier, L. Chabert TechnicAtome, CS 50497, 13593 Aix-en-Provence Cedex

More information

MONTE CARLO SIMULATION OF THE GREEK RESEARCH REACTOR NEUTRON IRRADIATION POSITIONS USING MCNP

MONTE CARLO SIMULATION OF THE GREEK RESEARCH REACTOR NEUTRON IRRADIATION POSITIONS USING MCNP MONTE CARLO SIMULATION OF THE GREEK RESEARCH REACTOR NEUTRON IRRADIATION POSITIONS USING MCNP I.E. STAMATELATOS, F. TZIKA Institute of Nuclear Technology and Radiation Protection, NCSR Demokritos, Aghia

More information

A Monte Carlo Simulation for Estimating of the Flux in a Novel Neutron Activation System using 252 Cf Source

A Monte Carlo Simulation for Estimating of the Flux in a Novel Neutron Activation System using 252 Cf Source IOSR Journal of Applied Physics (IOSR-JAP) e-issn: 2278-4861.Volume 7, Issue 3 Ver. II (May. - Jun. 2015), PP 80-85 www.iosrjournals.org A Monte Carlo Simulation for Estimating of the Flux in a Novel Neutron

More information

Experimental Determination of Cross Sections for (n,x) Nuclear Reactions

Experimental Determination of Cross Sections for (n,x) Nuclear Reactions WDS'07 Proceedings of Contributed Papers, Part III, 188 192, 2007. ISBN 978-80-7378-025-8 MATFYZPRESS Experimental Determination of Cross Sections for (n,x) Nuclear Reactions N. Dzysiuk and I. Kadenko

More information

Lectures on Applied Reactor Technology and Nuclear Power Safety. Lecture No 1. Title: Neutron Life Cycle

Lectures on Applied Reactor Technology and Nuclear Power Safety. Lecture No 1. Title: Neutron Life Cycle Lectures on Nuclear Power Safety Lecture No 1 Title: Neutron Life Cycle Department of Energy Technology KTH Spring 2005 Slide No 1 Outline of the Lecture Infinite Multiplication Factor, k Four Factor Formula

More information

NEUTRONIC ANALYSIS STUDIES OF THE SPALLATION TARGET WINDOW FOR A GAS COOLED ADS CONCEPT.

NEUTRONIC ANALYSIS STUDIES OF THE SPALLATION TARGET WINDOW FOR A GAS COOLED ADS CONCEPT. NEUTRONIC ANALYSIS STUDIES OF THE SPALLATION TARGET WINDOW FOR A GAS COOLED ADS CONCEPT. A. Abánades, A. Blanco, A. Burgos, S. Cuesta, P.T. León, J. M. Martínez-Val, M. Perlado Universidad Politecnica

More information

MCNP. The neutron, photon, or electron current (particle energy) integrated over a surface:

MCNP. The neutron, photon, or electron current (particle energy) integrated over a surface: Chapter 10 TALLYING IN MCNP Tallying is the process of scoring the parameters of interest, i.e. providing the required answers. For each answer the fractional standard deviation (fsd), relative error,

More information

Benchmark Experiments of Accelerator Driven Systems (ADS) in Kyoto University Critical Assembly (KUCA)

Benchmark Experiments of Accelerator Driven Systems (ADS) in Kyoto University Critical Assembly (KUCA) Benchmark Experiments of Accelerator Driven Systems (ADS) in Kyoto University Critical Assembly (KUCA) C. H. Pyeon, T. Misawa, H. Unesaki, K. Mishima and S. Shiroya (Kyoto University Research Reactor Institute,

More information

Physics 736. Experimental Methods in Nuclear-, Particle-, and Astrophysics. Lecture 3

Physics 736. Experimental Methods in Nuclear-, Particle-, and Astrophysics. Lecture 3 Physics 736 Experimental Methods in Nuclear-, Particle-, and Astrophysics Lecture 3 Karsten Heeger heeger@wisc.edu Review of Last Lecture a colleague shows you this data... what type of reaction is this?

More information

Test Simulation of Neutron Damage to Electronic Components using Accelerator Facilities

Test Simulation of Neutron Damage to Electronic Components using Accelerator Facilities Test Simulation of Neutron Damage to Electronic Components using Accelerator Facilities Donald King, Patrick Griffin, Ed Bielejec, William Wampler, Chuck Hembree, Kyle McDonald, Tim Sheridan, George Vizkelethy,

More information

Atomic Physics. Chapter 6 X ray. Jinniu Hu 24/12/ /20/13

Atomic Physics. Chapter 6 X ray. Jinniu Hu 24/12/ /20/13 Atomic Physics Chapter 6 X ray 11/20/13 24/12/2018 Jinniu Hu 1!1 6.1 The discovery of X ray X-rays were discovered in 1895 by the German physicist Wilhelm Roentgen. He found that a beam of high-speed electrons

More information

We are IntechOpen, the world s leading publisher of Open Access books Built by scientists, for scientists. International authors and editors

We are IntechOpen, the world s leading publisher of Open Access books Built by scientists, for scientists. International authors and editors We are IntechOpen, the world s leading publisher of Open Access books Built by scientists, for scientists 4,100 116,000 120M Open access books available International authors and editors Downloads Our

More information

WM2010 Conference, March 7-11, 2010, Phoenix, AZ

WM2010 Conference, March 7-11, 2010, Phoenix, AZ Nondestructive Determination of Plutonium Mass in Spent Fuel: Preliminary Modeling Results using the Passive Neutron Albedo Reactivity Technique - 10413 L. G. Evans, S. J. Tobin, M. A. Schear, H. O. Menlove,

More information

ACTIVATION ANALYSIS OF DECOMISSIONING OPERATIONS FOR RESEARCH REACTORS

ACTIVATION ANALYSIS OF DECOMISSIONING OPERATIONS FOR RESEARCH REACTORS ACTIVATION ANALYSIS OF DECOMISSIONING OPERATIONS FOR RESEARCH REACTORS Hernán G. Meier, Martín Brizuela, Alexis R. A. Maître and Felipe Albornoz INVAP S.E. Comandante Luis Piedra Buena 4950, 8400 San Carlos

More information

Computational study of Passive Neutron Albedo Reactivity (PNAR) measurement with fission chambers

Computational study of Passive Neutron Albedo Reactivity (PNAR) measurement with fission chambers UNLV Theses, Dissertations, Professional Papers, and Capstones 5-2011 Computational study of Passive Neutron Albedo Reactivity (PNAR) measurement with fission chambers Sandra De La Cruz University of Nevada,

More information

Monte Carlo Simulation for Statistical Decay of Compound Nucleus

Monte Carlo Simulation for Statistical Decay of Compound Nucleus CNR20, Prague, Czech Republic, Sep. 9 23, 20 Monte Carlo Simulation for Statistical Decay of Compound Nucleus T. Kawano, P. Talou, M.B Chadwick Los Alamos National Laboratory Compound Nuclear Reaction,

More information

DEVELOPMENT OF ADVANCED NEUTRON INDUCED PROMPT GAMMA- RAY ANALYSIS SYSTEM FOR SURVEY OF ANTI-PERSONNEL MINES

DEVELOPMENT OF ADVANCED NEUTRON INDUCED PROMPT GAMMA- RAY ANALYSIS SYSTEM FOR SURVEY OF ANTI-PERSONNEL MINES DEVELOPMENT OF ADVANCED NEUTRON INDUCED PROMPT GAMMA- RAY ANALYSIS SYSTEM FOR SURVEY OF ANTI-PERSONNEL MINES T. Iguchi 1, J. Kawarabayashi 1, K. Watanabe 1, K. Nishimura 2, T. Handa 2 and H. Sawamura 2

More information

Neutron Generation from 10MeV Electron Beam to Produce Mo99

Neutron Generation from 10MeV Electron Beam to Produce Mo99 From the SelectedWorks of Innovative Research Publications IRP India Winter January 1, 2015 Neutron Generation from 10MeV Electron Beam to Produce Mo99 Innovative Research Publications, IRP India, Innovative

More information

The Neutron Diagnostic Experiment for Alcator C-Mod

The Neutron Diagnostic Experiment for Alcator C-Mod PFC/JA-9-16 The Neutron Diagnostic Experiment for Alcator C-Mod C. L. Fiore, R. S. Granetz Plasma Fusion Center Massachusetts Institute of Technology -Cambridge, MA 2139 May, 199 To be published in Review

More information

Analysis of the TRIGA Reactor Benchmarks with TRIPOLI 4.4

Analysis of the TRIGA Reactor Benchmarks with TRIPOLI 4.4 BSTRCT nalysis of the TRIG Reactor Benchmarks with TRIPOLI 4.4 Romain Henry Jožef Stefan Institute Jamova 39 SI-1000 Ljubljana, Slovenia romain.henry@ijs.si Luka Snoj, ndrej Trkov luka.snoj@ijs.si, andrej.trkov@ijs.si

More information

EFFICIENCY SIMULATION OF A HPGE DETECTOR FOR THE ENVIRONMENTAL RADIOACTIVITY LABORATORY/CDTN USING A MCNP-GAMMAVISION METHOD

EFFICIENCY SIMULATION OF A HPGE DETECTOR FOR THE ENVIRONMENTAL RADIOACTIVITY LABORATORY/CDTN USING A MCNP-GAMMAVISION METHOD 2011 International Nuclear Atlantic Conference - INAC 2011 Belo Horizonte,MG, Brazil, October 24-28, 2011 ASSOCIAÇÃO BRASILEIRA DE ENERGIA NUCLEAR - ABEN ISBN: 978-85-99141-04-5 EFFICIENCY SIMULATION OF

More information

Reactor Physics: Basic Definitions and Perspectives. Table of Contents

Reactor Physics: Basic Definitions and Perspectives. Table of Contents Reactor Physics - Basic Definitions and Perspectives Reactor Physics: Basic Definitions and Perspectives prepared by Wm. J. Garland, Professor, Department of Engineering Physics, McMaster University, Hamilton,

More information

THREE-DIMENSIONAL INTEGRAL NEUTRON TRANSPORT CELL CALCULATIONS FOR THE DETERMINATION OF MEAN CELL CROSS SECTIONS

THREE-DIMENSIONAL INTEGRAL NEUTRON TRANSPORT CELL CALCULATIONS FOR THE DETERMINATION OF MEAN CELL CROSS SECTIONS THREE-DIMENSIONAL INTEGRAL NEUTRON TRANSPORT CELL CALCULATIONS FOR THE DETERMINATION OF MEAN CELL CROSS SECTIONS Carsten Beckert 1. Introduction To calculate the neutron transport in a reactor, it is often

More information

AN ABSTRACT OF THE THESIS OF. Edward K. Kropp for the degree of Master of Science in Radiation Health Physics presented on August 12, 1998.

AN ABSTRACT OF THE THESIS OF. Edward K. Kropp for the degree of Master of Science in Radiation Health Physics presented on August 12, 1998. AN ABSTRACT OF THE THESIS OF Edward K. Kropp for the degree of Master of Science in Radiation Health Physics presented on August 12, 1998. Title: Design and Simulation of Abstract approved: Self-Powered

More information

Some thoughts on Fission Yield Data in Estimating Reactor Core Radionuclide Activities (for anti-neutrino estimation)

Some thoughts on Fission Yield Data in Estimating Reactor Core Radionuclide Activities (for anti-neutrino estimation) Some thoughts on Fission Yield Data in Estimating Reactor Core Radionuclide Activities (for anti-neutrino estimation) Dr Robert W. Mills, NNL Research Fellow for Nuclear Data, UK National Nuclear Laboratory.

More information

The investigations in the field of advanced nuclear power systems for energy production and transmutation of RAW in NAS of Belarus

The investigations in the field of advanced nuclear power systems for energy production and transmutation of RAW in NAS of Belarus The investigations in the field of advanced nuclear power systems for energy production and transmutation of RAW in NAS of Belarus on behalf of YALINA team Dr. Kiyavitskaya H. ISTC meeting «Feature technology:

More information

On the Use of Shannon Entropy of the Fission Distribution for Assessing Convergence of Monte Carlo Criticality Calculations.

On the Use of Shannon Entropy of the Fission Distribution for Assessing Convergence of Monte Carlo Criticality Calculations. Organized and hosted by the Canadian Nuclear Society. Vancouver, BC, Canada. 2006 September 10-14 On the Use of Shannon Entropy of the Fission Distribution for Assessing Convergence of Monte Carlo Criticality

More information

Physics 663. Particle Physics Phenomenology. April 23, Physics 663, lecture 4 1

Physics 663. Particle Physics Phenomenology. April 23, Physics 663, lecture 4 1 Physics 663 Particle Physics Phenomenology April 23, 2002 Physics 663, lecture 4 1 Detectors Interaction of Charged Particles and Radiation with Matter Ionization loss of charged particles Coulomb scattering

More information

Upcoming features in Serpent photon transport mode

Upcoming features in Serpent photon transport mode Upcoming features in Serpent photon transport mode Toni Kaltiaisenaho VTT Technical Research Centre of Finland Serpent User Group Meeting 2018 1/20 Outline Current photoatomic physics in Serpent Photonuclear

More information

Applied Nuclear Physics (Fall 2006) Lecture 21 (11/29/06) Detection of Nuclear Radiation: Pulse Height Spectra

Applied Nuclear Physics (Fall 2006) Lecture 21 (11/29/06) Detection of Nuclear Radiation: Pulse Height Spectra 22.101 Applied Nuclear Physics (Fall 2006) Lecture 21 (11/29/06) Detection of Nuclear Radiation: Pulse Height Spectra References: W. E. Meyerhof, Elements of Nuclear Physics (McGraw-Hill, New York, 1967),

More information

MC simulation of a PGNAA system for on-line cement analysis

MC simulation of a PGNAA system for on-line cement analysis Nuclear Science and Techniques 21 (2010) 221 226 MC simulation of a PGNAA system for on-line cement analysis YANG Jianbo 1 TUO Xianguo 1,* LI Zhe 1 MU Keliang 2 CHENG Yi 1 MOU Yunfeng 3 1 State Key Laboratory

More information

Contrabands detection with a low energy electron linac driven photoneutron source

Contrabands detection with a low energy electron linac driven photoneutron source Contrabands detection with a low energy electron linac driven photoneutron source Yigang Yang Tsinghua University, Beijing, China yangyigang@mail.tsinghua.edu.cn Outline 1. Research motivation 2. e-linac

More information

Chem 481 Lecture Material 4/22/09

Chem 481 Lecture Material 4/22/09 Chem 481 Lecture Material 4/22/09 Nuclear Reactors Poisons The neutron population in an operating reactor is controlled by the use of poisons in the form of control rods. A poison is any substance that

More information

Characterization and Monte Carlo simulations for a CLYC detector

Characterization and Monte Carlo simulations for a CLYC detector Characterization and Monte Carlo simulations for a CLYC detector A. Borella 1, E. Boogers 1, R.Rossa 1, P. Schillebeeckx 1 aborella@sckcen.be 1 SCK CEN, Belgian Nuclear Research Centre JRC-Geel, Joint

More information

Design and Use of an Interim Noble Gas Effluent Monitor at Columbia Generating Station

Design and Use of an Interim Noble Gas Effluent Monitor at Columbia Generating Station Design and Use of an Interim Noble Gas Effluent Monitor at Columbia Generating Station RETS-REMP & EPRI Groundwater Protection Workshop June 25-27th, 2013 Westminster, CO Eric L. Darois, CHP (RSCS) Jim

More information

Measuring the Photoneutrons Originating from D(γ, n)h Reaction after the Shutdown of an

Measuring the Photoneutrons Originating from D(γ, n)h Reaction after the Shutdown of an Journal of Nuclear Science and Technology ISSN: 0022-3131 (Print) 1881-1248 (Online) Journal homepage: https://www.tandfonline.com/loi/tnst20 Measuring the Photoneutrons Originating from D(γ, n)h Reaction

More information

CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR WITH UO 2 GD 2 O 3 BURNABLE POISON RODS

CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR WITH UO 2 GD 2 O 3 BURNABLE POISON RODS CRITICAL LOADING CONFIGURATIONS OF THE IPEN/MB-01 REACTOR WITH UO 2 GD 2 O 3 BURNABLE POISON RODS Alfredo Abe 1, Rinaldo Fuga 1, Adimir dos Santos 2, Graciete S. de Andrade e Silva 2, Leda C. C. B. Fanaro

More information

An Optimized Gamma-ray Densitometry Tool for Oil Products Determination

An Optimized Gamma-ray Densitometry Tool for Oil Products Determination International Journal of Innovation and Applied Studies ISSN 2028-9324 Vol. 4 No. 2 Oct. 2013, pp. 408-412 2013 Innovative Space of Scientific Research Journals http://www.issr-journals.org/ijias/ An Optimized

More information

at Oak Ridge National Laboratory.

at Oak Ridge National Laboratory. 361 Designs for Neutron Radiography at Oak Ridge National Laboratory and Computed Tomography Dudley A. Raine lipv4, Camden R. Hubbard, Paul M. Whaley, and Michael C. Wright3 Oak Ridge National Laboratory

More information

Nuclear Reactions A Z. Radioactivity, Spontaneous Decay: Nuclear Reaction, Induced Process: x + X Y + y + Q Q > 0. Exothermic Endothermic

Nuclear Reactions A Z. Radioactivity, Spontaneous Decay: Nuclear Reaction, Induced Process: x + X Y + y + Q Q > 0. Exothermic Endothermic Radioactivity, Spontaneous Decay: Nuclear Reactions A Z 4 P D+ He + Q A 4 Z 2 Q > 0 Nuclear Reaction, Induced Process: x + X Y + y + Q Q = ( m + m m m ) c 2 x X Y y Q > 0 Q < 0 Exothermic Endothermic 2

More information

Evaluation of radiation dose rates due to calibration and interrogation neutron sources while using the AWCC in horizontal configuration

Evaluation of radiation dose rates due to calibration and interrogation neutron sources while using the AWCC in horizontal configuration IOSR Journal of Applied Physics (IOSR-JAP) e-issn: 2278-4861.Volume 8, Issue 5 Ver. I (Sep - Oct. 2016), PP 60-64 www.iosrjournals.org Evaluation of radiation dose rates due to calibration and interrogation

More information

Neutrons For Science

Neutrons For Science Neutrons For Science NFS is one of the two facilities of the LINAG Experimental Area se of the LINAG s beams to produce neutrons between 1 and 40 MeV The NFS is composed of : - A neutron beam in a Time-Of-Flight

More information

MUSE-4 BENCHMARK CALCULATIONS USING MCNP-4C AND DIFFERENT NUCLEAR DATA LIBRARIES

MUSE-4 BENCHMARK CALCULATIONS USING MCNP-4C AND DIFFERENT NUCLEAR DATA LIBRARIES MUSE-4 BENCHMARK CALCULATIONS USING MCNP-4C AND DIFFERENT NUCLEAR DATA LIBRARIES Nadia Messaoudi and Edouard Mbala Malambu SCK CEN Boeretang 200, B-2400 Mol, Belgium Email: nmessaou@sckcen.be Abstract

More information

TITLE: Air Kerma Primary Standard: Experimental and Simulation Studies on Cs-137

TITLE: Air Kerma Primary Standard: Experimental and Simulation Studies on Cs-137 TITLE: Air Kerma Primary Standard: Experimental and Simulation Studies on Cs-137 AUTHORS: J. Cardoso, L. Santos, C. Oliveira ADRESS: Instituto Tecnológico e Nuclear Estrada Nacional 10; 2686-953 Sacavém;

More information

On the use of SERPENT code for few-group XS generation for Sodium Fast Reactors

On the use of SERPENT code for few-group XS generation for Sodium Fast Reactors On the use of SERPENT code for few-group XS generation for Sodium Fast Reactors Raquel Ochoa Nuclear Engineering Department UPM CONTENTS: 1. Introduction 2. Comparison with ERANOS 3. Parameters required

More information

DETERMINATION OF CORRECTION FACTORS RELATED TO THE MANGANESE SULPHATE BATH TECHNIQUE

DETERMINATION OF CORRECTION FACTORS RELATED TO THE MANGANESE SULPHATE BATH TECHNIQUE DETERMINATION OF CORRECTION FACTORS RELATED TO THE MANGANESE SULPHATE BATH TECHNIQUE Ján Haščík, Branislav Vrban, Jakub Lüley, Štefan Čerba, Filip Osuský, Vladimír Nečas Slovak University of Technology

More information

Researchers at the University of Missouri-Columbia have designed a triple crystal

Researchers at the University of Missouri-Columbia have designed a triple crystal Childress, N. L. and W. H. Miller, MCNP Analysis and Optimization of a Triple Crystal Phoswich Detector, Nuclear Instruments and Methods, Section A, 490(1-2), 263-270 (Sept 1, 2002). Abstract Researchers

More information

D-D FUSION NEUTRONS FROM A STRONG SPHERICAL SHOCK WAVE FOCUSED ON A DEUTERIUM BUBBLE IN WATER. Dr. Michel Laberge General Fusion Inc.

D-D FUSION NEUTRONS FROM A STRONG SPHERICAL SHOCK WAVE FOCUSED ON A DEUTERIUM BUBBLE IN WATER. Dr. Michel Laberge General Fusion Inc. D-D FUSION NEUTRONS FROM A STRONG SPHERICAL SHOCK WAVE FOCUSED ON A DEUTERIUM BUBBLE IN WATER Dr. Michel Laberge General Fusion Inc. SONOFUSION Sonofusion is making some noise A bit short in energy, ~mj

More information