NUCLEAR DATA PRODUCTION, CALCULATION AND MEASUREMENT: A GLOBAL - - PowerPoint PPT Presentation

nuclear data production calculation and measurement a
SMART_READER_LITE
LIVE PREVIEW

NUCLEAR DATA PRODUCTION, CALCULATION AND MEASUREMENT: A GLOBAL - - PowerPoint PPT Presentation

NUCLEAR DATA PRODUCTION, CALCULATION AND MEASUREMENT: A GLOBAL OVERVIEW OF THE GAMMA HEATING ISSUE WONDER-2012 | A.C. Colombier, H. Amharrak, D. Fourmentel, S. Ravaux, D. Rgnier, O. Gueton, J.P. Hudelot, M. Lemaire CEA, DEN,DER, Cadarache


slide-1
SLIDE 1

| PAGE 1 CEA | 10 AVRIL 2012

NUCLEAR DATA PRODUCTION, CALCULATION AND MEASUREMENT: A GLOBAL OVERVIEW OF THE GAMMA HEATING ISSUE

25-28 september 2012

WONDER-2012| A.C. Colombier, H. Amharrak, D. Fourmentel, S. Ravaux, D. Régnier, O. Gueton, J.P. Hudelot, M. Lemaire CEA, DEN,DER, Cadarache

| PAGE 1 CEA | 10 AVRIL 2012

slide-2
SLIDE 2

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 2

Table of contents

  • 1. Context
  • 2. Nuclear data production
  • 3. Simulation Codes
  • 4. Integral experiments and instrumentation
  • 5. Conclusion

9 octobre 2012 | PAGE 2 WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012

slide-3
SLIDE 3

| PAGE 3 CEA | 10 AVRIL 2012

  • 1. CONTEXT

9 octobre 2012 | PAGE 3 CEA | 10 AVRIL 2012

slide-4
SLIDE 4

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 4

CONTEXT – Nuclear heating in power reactor

In the core : > 90% -> neutron (local deposite) In the reflector : > 90% -> photon

Nuclear heating

Energy deposition : charged particles (α, proton, e±), ions from n & γ interactions Photon production : . neutron interactions (fission, radiative capture, inelastic scattering) . fission products decay Photon interactions : . photoelectric effect . Compton scattering . pair production

slide-5
SLIDE 5

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 5

CONTEXT – Nuclear γ heating in power reactor Relative contribution in a fast reactor

Fission : 70% (~ 30% delayed gamma) Radiative capture : about 20% Inelastic scattering : the rest Depending on the reactor material balance

slide-6
SLIDE 6

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 6

CONTEXT – New reactor concepts New concept New design

PWR – GEN III+ : stainless steal heavy reflector Burnable poison (UO2-Gd2O3 pins for PWR…) GEN IV – Fast Reactor : steal control rod followers and diluent MTR – JHR : Hf control rods Aluminium structure Beryllium reflector Cd shielding design of experimental devices

To reduce neutron leakages and flatten the power distribution, the space between the polygonal core and the cylindrical core barrel is filled with a heavy neutron reflector. The heat generated inside the steel structure by absorption

  • f gamma radiation is removed by the primary coolant

through holes and gaps provided in the reflector structure.

Cooling system

slide-7
SLIDE 7

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 7

CONTEXT – so what ?

Nuclear data evaluations Experimental measurement uncertainties better description & simulation

5 PhD works at 1 collaboration : McMaster University (Canada) 2009 : Gamma heating Working Group

slide-8
SLIDE 8

| PAGE 8 CEA | 10 AVRIL 2012

  • 2. NUCLEAR DATA PRODUCTION
slide-9
SLIDE 9

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 9

Nuclear data library : JEFF3.1.1

Missing data for all n interactions1 : Gd, Cd, Ag, In, … Incoherent Qγ for (n,γ)1 :

54,56,57,58Fe, 62Ni

Old fashioned or missing data for prompt gamma fission production2 :

235U, 239, 241Pu

NUCLEAR DATA PRODUCTION

1 S. Ravaux, D. Bernard, A. Santamarina, New evaluation of photon production for JEFF3, Conf. PHYTRA2, (2011) 2 D. Regnier, O. Litaize, O. Serot, Monte Carlo simulation of prompt fission gamma emission, Phys. Proc. 31, 59-65, (2012)

New evalutions

(n,γ) (n,n’)1 : gamma emission spectrum . Discrete level : EGAF/ENSDF libraries . Contiunum (A>70) : nuclear reaction code TALYS (RIPL3.0 param. library) Monte Carlo simulation code : FIFRELIN2

slide-10
SLIDE 10

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 10

NUCLEAR DATA PRODUCTION : 54Fe example

Integrated gamma production spectra : (n,γ) 54Fe Descrepancy > 50% ! 16 stable isotopes available3

  • 3S. Ravaux, D. Bernard, NEA Data bank, JEFDOC-1404 (2011)
slide-11
SLIDE 11

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 11

FIFRELIN: Monte Carlo simulation of fission fragments evaporation NUCLEAR DATA PRODUCTION : FIFRELIN

+ new module : de-excitation gamma cascade simulation density level distribution model strengh function + preliminary tests : 55Mn (n,γ) 144Ba fission fragment de-excitation 252Cf spontaneous fission

slide-12
SLIDE 12

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 12

NUCLEAR DATA PRODUCTION :252Cf

+ preliminary results : Discrepancy source : density level distribution model > strengh function Qualitative agreement : good Quantitative analisys: systematic overestimation

252Cf prompt gamma spectrum

slide-13
SLIDE 13

| PAGE 13 CEA | 10 AVRIL 2012

  • 3. SIMULATION CODE
slide-14
SLIDE 14

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 14

SIMULATION CODE

JEFF3.1.1 Library Monte Carlo 3D TRIPOLI4.8 npe prompt γ heating To be optimized PEPIN code: delayed γ spectrum pe delayed γ heating np APOLLO2-MOC QUALIFICATION

slide-15
SLIDE 15

| PAGE 15 CEA | 10 AVRIL 2012

  • 4. INTEGRAL EXPERIMENTS AND

INSTRUMENTATION

slide-16
SLIDE 16

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 16

INTEGRAL EXPERIMENTS AND INSTRUMENTATION : ADAPH+ in Minerve

MINERVE facility : R1-UO2 PWR standard spectrum TLD-400: CaF2:Mn OSLD : Al2O3:C γ heating measurement in zero power reactor

  • Thermo-Luminescent Detector TLD

Optically Stimulated Detector OSLD

  • H. Amharrak and al., Analysis and Recent Advances in Gamma Heating Measurements in MINERVE Facility by Using

TLD and OSLD Techniques, IEEE Trans. Nucl Scie. 59, 1360-1368, (2012)

slide-17
SLIDE 17

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 17

INTEGRAL EXPERIMENTS AND INSTRUMENTATION : ADAPH+ in Minerve

1- Improvement of the calibration : Standard 60Co source Al pillbox : electronic equilibrium Calibration curve Calibration uncertainty ~ 2% TLD/OSLD

slide-18
SLIDE 18

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 18

INTEGRAL EXPERIMENTS AND INSTRUMENTATION : ADAPH+ in Minerve

2- Incore measurement : absorbed dose experimental uncertainty (calib., repeatability) neutron dose correction : TLD : 8.6% OSLD : 5.9% 3- 3D Monte Carlo simulation : cavity corection 2 steps calculation TLD : 1.07 OSLD : 1.05 Delayed γ contribution : 32% C/E (k=2) TLD : 1.05±5.3% OSLD : 0.96±7.0% discrepancy TLD/OSLD ? n dose, delayed γ simulation methods

slide-19
SLIDE 19

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 19

INTEGRAL EXPERIMENTS AND INSTRUMENTATION : PERLE in EOLE PERLE in EOLE facility

A 22 cm stainless steel neutron reflector TLD gamma heating measurement in &

  • ut-core

27 X 27 3.7% 235U enriched fuel pins

Measurement points Steel reflector Water channels Fuel pins and moderator

Fe, 62Ni new evaluations qualification

slide-20
SLIDE 20

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 20

Fast neutron flux

INTEGRAL EXPERIMENTS AND INSTRUMENTATION : JHR general characteristics

In core Up to 5.5 1014 n/cm².s > 1MeV Up to 1015 n/cm².s > 0.1MeV In reflector Up to 5.5 1014 n.cm-².s-1 Fixed positions and displacement systems Fuel studies: up to 600 W/cm with a 1% 235U PWR rod Material ageing (up to 16 dpa/y) Displacement systems:

  • To adjust the fissile

power

  • To study transients

Thermal neutron flux

slide-21
SLIDE 21

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 21

INTEGRAL EXPERIMENTS AND INSTRUMENTATION : AMMON in EOLE

  • Experiment characteristics:

Central experimental zone : aluminum rack U3Si2-Al fuel (e=27%) Driver zone : 623 UOx fuel pins (e=3.7 %)

  • Main Configurations:
  • Reference core :

7 JHR assemblies

  • Hf rod:

completely inserted, ½ inserted

  • Beryllium
  • Voided assembly

Experimental Experimental data data: critical state, reactivity worth, power distributions, spectrum indices, conversion factor, T° coefficient, gamma-heating

slide-22
SLIDE 22

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 22

INTEGRAL EXPERIMENTS AND INSTRUMENTATION : AMMON in EOLE AMMON EXPERIMENTAL PROGRAM IN EOLE FACILITY

Experiment in progress gamma-heating measurements : . TLDs (7LiF, CaF2:Mn) , OSLDs (Al2O3:C ), ionization chamber . Where ? assembly center, aluminum filler, hafnium rod, beryllium block Validation : deposited energy in aluminum, hafnium and beryllium for JHR safety and performance study Interpretation : (TRIPOLI4/JEFF3): . Collaboration work in progress . PhD work starting at the end of 2012

slide-23
SLIDE 23

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 23

INTEGRAL EXPERIMENTS AND INSTRUMENTATION : CARMEN-1 in OSIRIS

I IN NC CO O R R E E

  • n,γ combined analysis => JHR core mapping

CARMEN-1 in OSIRIS facility

Neutron & photon measurements 2 experimental devices dedicated 4 out-core measuring locations scanned in 70 MW OSIRIS reflector (CEA-Saclay)

  • D. Fourmentel and al.,Combined analysis of neutron and photon flux measurements for Jules Horowitz reactor core mapping,
  • Conf. PHYTRA2, (2011)
slide-24
SLIDE 24

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 24

Differential calorimeter Ionisation chamber GT SPGD cable

(noise current measurement)

Bi SPGD Fission chamber cable

(noise current measurement)

CARMEN1-P

Gamma flux :

Ionization chamber, Self Powered Gamma Detector (SPGD)

Nuclear heating :

Differential calorimeter, Gamma Thermometer (commonly used in MTR)

OBJECTIVES

Reduce measurement uncertainties Testing 3 different methods to estimate nuclear heating from temperature measurement 2 sensors with different material (grahite vs stainless steel) & neutron dose sensitivity

INTEGRAL EXPERIMENTS AND INSTRUMENTATION : CARMEN-1 in OSIRIS

slide-25
SLIDE 25

WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 25

Signals evolution of gamma sensors between different locations

Evolution des signaux photoniques en fonction de l'éloignement du coeur en rangée H 0,0 0,2 0,4 0,6 0,8 1,0 1,2 H11 H10 H9 Emplacement Signaux normalisés

CALO (W/g) CFSD P CORR MOYEN (A) GT MOYEN (W/g) CALO "0" (W/g) BI CORR MOYEN (A)

Locations Normalized signals

INTEGRAL EXPERIMENTS AND INSTRUMENTATION : CARMEN-1 in OSIRIS

slide-26
SLIDE 26

| PAGE 26 CEA | 10 AVRIL 2012

  • 5. CONCLUSION
slide-27
SLIDE 27

| PAGE 27 WONDER-2012, AIX en PROVENCE | 25-28 SEPTEMBER 2012 | PAGE 27

WORKS ACTORS FURTHER MORE… CONTEXT NEEDS γ HEATING WG 2009

  • Nuc. Data

& model 5PhD

Guest collaborator Perf. Design Safety

slide-28
SLIDE 28

| PAGE 28 CEA | 10 AVRIL 2012

Direction DEN Département DER Service SPRC Commissariat à l’énergie atomique et aux énergies alternatives Centre de Saclay | 91191 Gif-sur-Yvette Cedex

  • T. +33 (0)1 XX XX XX XX | F. +33 (0)1 XX XX XX XX

Etablissement public à caractère industriel et commercial | RCS Paris B 775 685 019

9 octobre 2012 | PAGE 28 CEA | 10 AVRIL 2012

Thank You