Neutron Activation Cross Sections for Fusion
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1 Neutron Activation Cross Sections for Fusion Adelle Hay The University of York/Culham Centre for Fusion Energy March 30, 2015 Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
2 Overview 1 Introduction 2 Validating Cross-section Data Differential and Integral Data 3 Experimental Procedure and Activation Analysis Experimental Procedure Analysis of ASP data 4 Current Work Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
3 Motivation for Determination of Cross-sections Single D-T reaction releases a 14 MeV-neutron, which can activate first wall components. Neutron activation cross sections must therefore be known to a high precision to aid in the design of first wall components. Inventory code (FISPACT) used to determine how long materials can be left in the tokamak until they need replacing. Results from FISPACT also help determine the safest way of conducting maintenance. Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
4 Aim: To Validate Existing Cross-section Data European Activation File (EAF): neutron cross sections Ÿ816 targets (H-1 to Fm-257) Ÿ86 reaction types Ÿ2233 nuclides ŸStable and isomeric states 212 (T ½ > 1s) 82 0 EAF neutron induced reactions 5096 important reactions Cross sections 2265 major reactions Validation: 1728 reactions with any experimental data SACS Pb hours β Tl 0 γ Bi60.55 mins β α Po 0.3 μs γ α γ 3 mins 0 β Pb stable Decay data 470 reactions with integral data Validation: C/E Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
5 Experimental and Theoretical Cross-Section Data Validation of EASY-2007 using integral measurements UKAEA FUS 547 (2008) Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
6 C/E values Validation of EASY-2007 using integral measurements UKAEA FUS 547 (2008) Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
7 Differential and Integral Data To validate cross-section data, require: Integral results in several complementary neutron spectra. Adequate experimental differential data. Differential Data: Cross-section measurements taken at a single, well-defined incident neutron energy. E.g. Neutron time-of-flight data. Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
8 Integral Data Neutron energy spectrum with wide peaks, eg: Validation of EASY-2007 using integral measurements UKAEA FUS 547 (2008) Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
9 Experimental Procedure ASP facility at AWE. Fusion Engineering and Design 87 (2012) Deuterons accelerated towards a tritiated target. D-T fusion reaction releases 14 MeV-neutrons. 14 MeV-neutron beam irradiates a thin (0.5mm), cylindrical (diameter 5-12mm) foil of chosen material. The foil is moved (remotely) from the irradiation site to the HPGe detector. Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
10 Experimental Procedure ASP facility at AWE. Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
11 Experimental Procedure Data from the ASP neutron generator is considered integral at the position of the rabbit system. Due to a broad neutron energy peak. Beam is roughly the same diameter as the foil. Foil further away = consider the data differential. Too much flux lost at this distance. Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
12 Reactions Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
13 Activation Analysis activity, A (Bq) A0 t 0 = irradiation time time, t (s) t d = delay time (transfer time) Adelle Hay (UoY/CCFE) t m = measurement time Neutron activation cross sections March 30, / 17
14 Activation Analysis activity, A (Bq) A0 t 0 = irradiation time time, t (s) t d = delay time (transfer time) t m = measurement time A0 = Nφσ 1 e λt0 σ= A0 Nφ (1 e λt0 ) Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
15 Activation Analysis activity, A (Bq) A0 t 0 = irradiation time time, t (s) t d = delay time (transfer time) A0 = Nφσ 1 e λt0 σ= A0 Nφ (1 e λt0 ) t m = measurement time A0 = activity at time t0 N= no. of atoms in sample σ = neutron activation cross section φ = neutron flux λ = decay constant Glenn F. Knoll, Radiation Detection and Measurment, John Wiley and Sons Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
16 Experimental Determination of Cross Section counts per live second, C C0 t 0 = irradiation time time, t (s) t d = delay time (transfer time) Adelle Hay (UoY/CCFE) t m = measurement time Neutron activation cross sections March 30, / 17
17 Experimental Determination of Cross Section counts per live second, C C0 t 0 = irradiation time time, t (s) t d = delay time (transfer time) ln2 C (t) = C0 exp [t + td ] T1 t m = measurement time! 2 A= C Iγ Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
18 Experimental Determination of Cross Section counts per live second, C C0 time, t (s) t 0 = irradiation time t d = delay time (transfer time) ln2 C (t) = C0 exp [t + td ] T1 2 t m = measurement time! C0 = count rate at time t0 T 1 = half life of radioactive daughter 2 C A= Iγ Iγ = intensity of γ peak = absolute efficiency of detector M. R. Gilbert, L.W. Packer, and S. Lilley, Nuclear Data Sheets, Article DC8, 2013 Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
19 Corrections to Data Analysis and Automated Processing True coincidence summing effects. Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
20 Corrections to Data Analysis and Automated Processing True coincidence summing effects. Consderation of errors, and how to correctly carry these through the data analysis. Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
21 Corrections to Data Analysis and Automated Processing True coincidence summing effects. Consderation of errors, and how to correctly carry these through the data analysis. Making the equations used for calculating differential cross-sections suitable for integral data: Variation of neutron energy with time. Variation of flux with time. Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
22 Corrections to Data Analysis and Automated Processing True coincidence summing effects. Consderation of errors, and how to correctly carry these through the data analysis. Making the equations used for calculating differential cross-sections suitable for integral data: Variation of neutron energy with time. Variation of flux with time. Aim: to produce a robust, standard method of calculating cross-sections and associated error using integral data. Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
23 Gamma Spectroscopy at Culham Characterisation of detectors recently available at Culham: Well detector Compton-suppressed BEGe detector Co-axial HPGe detector Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
24 Acknowledgements Supervisor: David Jenkins The Nuclear Physics Group, The University of York Supervisor: Steven Lilley The Applied Radiation Physics Group, CCFE Andrew Simons, and the ASP team at AWE Adelle Hay (UoY/CCFE) Neutron activation cross sections March 30, / 17
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