Laboratory Experiment 1 Vasily Arzhanov. HT2004Lab 12 Safety Distance: keep yourself as far from radiation sources as possible Time: expose yourself to.

Slides:



Advertisements
Similar presentations
Fourier’s Law and the Heat Equation
Advertisements

NE Introduction to Nuclear Science Spring 2012
X-Ray Astronomy Lab X-rays Why look for X-rays? –High temperatures –Atomic lines –Non-thermal processes X-ray detectors X-ray telescopes The Lab.
Interaction of radiation with matter - 5
DIFFUSION OF NEUTRONS OVERVIEW Basic Physical Assumptions
HT2005: Rector PhysicsT09: Thermalisation1 SLOWING DOWN OF NEUTRONS Elastic scattering of neutrons. Lethargy. Average Energy Loss per Collision. Resonance.
ULTRASHORT LASER PULSE PROPAGATION IN HIGHLY SCATTERING MEDIA A.P. Popov.
A. Dokhane, PHYS487, KSU, 2008 Chapter3- Thermal Neutrons 1 NEWS Need to fix a date for the mid-term exam? The first week after vacation!
Safety Review: RF Issues Derun Li Absorber Safety Review December 9-10, 2003 Lawrence Berkeley National Laboratory Berkeley, CA
Properties of Definite Integrals
Can people meet from 2:40 to 3:30 on Tuesday, September 5?
SPIN 2004 Oct. 14, 2004 W. Kim, S.S. Stepanyan, S. Woo, M. Rasulbaev, S. Jin (Kyungpook National University) S. Korea Polarization Measurements of the.
Concentration Measurements of Porphyrin Solutions using the Cavity Ring-Down and Integrated Cavity Output Spectroscopy Techniques Deirdre O’Leary PY4060.
Institute for Safety Research Dávid Légrády IP-EUROTRANS ITC2 Development of a Neutron Time-of-Flight Source at the ELBE Accelerator ELBE Neutron source.
Laws of Radiation Heat Transfer P M V Subbarao Associate Professor Mechanical Engineering Department IIT Delhi Macro Description of highly complex Wave.
ICESat TM 04/21/20031 MIT Activities Two main areas of activity: –Validation of atmospheric delays being computed for ICESat –Assessment of statistics.
Abstract A time resolved radial profile neutron diagnostic is being designed for the National Spherical Torus Experiment (NSTX). The design goal is to.
Higher Physics – Unit 3 3.5Dosimetry and Safety. Activity of Radiation The activity of a radioactive source is the average number of nuclei decaying per.
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:
Radiation Protection III NUCP 2331
Attenuation by absorption and scattering
R2D2 fast overview Sept version This document is a short description of the R2D2 test beam line at the JEEPII reactor at IFE, Norway. (Contact: Isabel.
Advanced Heat Transfer - Prof. Dr.-Ing. R. Weber - Winter 2005/ Lecture 1 (Governing Laws) Lecture-1. Governing Laws for Thermal Radiation Contents.
Physics Impact of MPC-EX on other Subsystems Oleg Eyser UCR/BNL MPC-EX Internal Review December 9, 2011.
Quaesta Instruments Tucson Arizona Founded in 2008 Staff: 10 Electronic devices: radiation detection environmental monitoring data logging telemetry Off-the-shelf.
Ionic Conductors: Characterisation of Defect Structure Lecture 15 Total scattering analysis Dr. I. Abrahams Queen Mary University of London Lectures co-financed.
1 Atmospheric Radiation – Lecture 9 PHY Lecture 10 Infrared radiation in a cloudy atmosphere: approximations.
Beam Polarimetry Matthew Musgrave NPDGamma Collaboration Meeting Oak Ridge National Laboratory Oct. 15, 2010.
PHYS-H406 – Nuclear Reactor Physics – Academic year CH.VII: NEUTRON SLOWING DOWN INTRODUCTION SLOWING DOWN VIA ELASTIC SCATTERING KINEMATICS.
Scattering of particles - topic 1 - june 2007 Particle Scattering: –Differential cross section –Trajectories and currents –Mean free path Quantal Scattering:
CosmicMolecularQuanta Does the inertia of a body depend on its energy content? Annalen der Physik, 18(1905), pp E = m c 2 On the electrodynamics.
Building a CANDU reactor
Lesson 4: Computer method overview
Production & Measurement of Thermal Neutron at RCNP Chhom Sakborey Nguyen Thi Duyen An Tran Hoai Nam Li Chunjuan Wang Mian.
Neutron detection in LHe ( HMI run 2004) R.Golub, E. Korobkina, J. Zou M. Hayden, G. Archibold J. Boissevain, W.S.Wilburn C. Gould.
Nuclear Reactors, BAU, 1st Semester, (Saed Dababneh). 1 Controlled Fission Note that  is greater than 2 at thermal energies and almost 3 at.
CH.III : APPROXIMATIONS OF THE TRANSPORT EQUATION
Nuclear Reactors, BAU, 1st Semester, (Saed Dababneh). 1 One-speed neutron diffusion in a finite medium Steady State Diffusion Equation A B At.
The Third Moscow Solar System Symposium 8 – 12 October 2012, Moscow, Russia First Data from DAN Instrument onboard MSL Curiosity Rover M. Litvak and I.
Russian Aviation and Space Agency Institute for Space Research NASA 2001 Mars Odyssey page 1 Workshop HEND Procedures of HEND data convolution for.
Laboratory photo-ionized plasma David Yanuka. Introduction  Photo-ionized plasmas are common in astrophysical environments  Typically near strong sources.
Fick’s Law The exact interpretation of neutron transport in heterogeneous domains is so complex. Assumptions and approximations. Simplified approaches.
Nuclear Reactors, BAU, 1st Semester, (Saed Dababneh).
An electron/positron energy monitor based on synchrotron radiation. I.Meshkov, T. Mamedov, E. Syresin, An electron/positron energy monitor based on synchrotron.
A. Dokhane, PHYS487, KSU, 2008 Chapter3- Thermal Neutrons 1 CHAPTER 3 LECTURE 2 THERMAL NEUTRONS.
meeting, Oct. 1 st 2015 meeting, Oct. 1 st Gas Pixel: TRD + Tracker.
A. Dokhane, PHYS487, KSU, 2008 Chapter1- Neutron Reactions 1 NEWS Lecture1: Chapter 0 is already on my Website.
Mullard Space Science Laboratory Using a CCD for the direct detection of electrons in a low energy space plasma spectrometer A CCD in place of an MCP:
PHYS-H406 – Nuclear Reactor Physics – Academic year CH.VII: NEUTRON SLOWING DOWN INTRODUCTION SLOWING DOWN VIA ELASTIC SCATTERING KINEMATICS.
Distance & Acceleration Chapter 3. When you know an object’s acceleration, initial velocity, and the length of time it accelerated, you can calculate.
NEM433 Radiation Detection and Measurement Laboratory Fall 2013 Osman Şahin ÇELİKTEN.
Chapter 2 Radiation Interactions with Matter East China Institute of Technology School of Nuclear Engineering and Technology LIU Yi-Bao Wang Ling.
CH.III : APPROXIMATIONS OF THE TRANSPORT EQUATION
Equation of Continuity
Fast neutron flux measurement in CJPL
Fourier’s Law and the Heat Equation
Fourier’s Law and the Heat Equation
Experimental approaches to s-process branchings
NEUTRON DIFFUSION THE CONTINUITY EQUATION
Stevens Institute of Technology
REACTOR THEORY The basic principles are simple but detailed calculations are difficult Use very simplified models to understand principles of calculations.
Bell Ringer A wave is a disturbance that transfers ______.
Perimeter.
Design of A New Wide-dynamic-range Neutron Spectrometer for BNCT with Liquid Moderator and Absorber S. Tamaki1, I. Murata1 1. Division of Electrical,
More on One-Speed Diffusion
Gas Pixel TRD/Tracker With the support of the TRT collaboration
Optimization of tower design
Perimeter.
Hard X-ray Albedo: A Spatial Perspective
Presentation transcript:

Laboratory Experiment 1 Vasily Arzhanov

HT2004Lab 12 Safety Distance: keep yourself as far from radiation sources as possible Time: expose yourself to radiation as short time as possible Number: expose to radiation only minimal number of people

HT2004Lab 13 Experimental Setup d d = 6 ÷ 47 cm Cd Sphere Without CdWith Cd NoCd08cm100sWithCd08cm50s NoCd12cm200sWithCd12cm400s 1.Naming convention 2.Same distances 3.Time scaling

HT2004Lab 14 Detection Technique α γ Fiss. prod. γ Channel 1: 97% Channel 2: 3% 6 Li Eu α t PM n γ γ Detector

HT2004Lab 15 Multi-Channel Analyser 0 Amplitude A max … A n-1 A1A1 AnAn Counts Time Channel n-1 Channel n

HT2004Lab 16

HT2004Lab 17 Summary Set/remove the Cd sphere Set a distance Acquire data Save to a file Set channels to sum up counts Scale the counts to the reference time Write down the result

HT2004Lab 18 One-Speed Diffusion Theory S0S0 r > 3λ s Isotropic source of thermal (slow) neutrons Distance at which Diffusion theory is valid

HT2004Lab 19 Differential Measurement

HT2004Lab 110 Diffusion Length r Thermal (slow) neutron borne Thermal neutron absorbed Average over the neutron population

HT2004Lab 111 Migration Area (Length) Fast neutron borne Thermal neutron absorbed Fast neutron thermalized r rsrs r th Differential measurement Ordinary measurement

HT2004Lab 112 θ θ θ ave = 0 θ ave = 90 Fast neutron borne Fast neutron thermalized Thermal neutron absorbed Orthogonality Property

HT2004Lab 113 Calculation of Migration

HT2004Lab 114 log r 2 A(r) Evaluating Integrals Ordinary meas.

HT2004Lab 115 Relaxation Length S0S0 r Uncollided flux First collision Absorption No absorption Absorption

HT2004Lab 116 Summary