Neutron Spectral Adjustment Exercise REAL-201X
Duration period of the new Exercise REAL-201X: 201X - 201X
Motivation/Purposes
The Workshop 5
"Cross Section, Nuclear Data, and Uncertainties"
at ISRD-15 (May 2014, Aix-en-Provance) requested the Nuclear Data Section of IAEA to organize a neutron spectral adjustment exercise similar to
REAL-88 (NMF-90)
(or predecessors REAL-84,
REAL-80).
RCM-2 (March 2015, see Report "INDC(NDS)-0682") of the IAEA CRP "Testing, Validation and Improving of IRDFF"
has elaborated following Recommendations for this Exercise.
Suggestions for datasets that might be used
- SINBAD has HB Robinson, VVER1000 and/or VVER400, Venus 3 cases
- Critical assembly data from LANL for Flattop
- 14 MeV from FNS graphite case
- 9Be(p,n) TOF data at 35 MeV
- 9Be(d,n) TOF data at various energies
- D2O(p,n) spectrum at 35 MeV
- Commercial reactor RPV surveillance
- Spallation source up to 60 MeV (which one ?)
Tentative Cases currently under analysis/selection/preparation for Exercise (not finished yet)
NB! The new REAL preparation phase goal is a collection of the INPUT information, i.e. RR and Spectra, which should also include the reasonably estimated uncertainties and correlations!
(we have to do this to be at least not worse than previous REAL-88 which had such 'complete inputs', see uncertainties and correlations below, e.g. in: PS1)
Tips for correlation matrix construction:
- RR: give a few % correlation among RRs that will try to account for commonly used standards, detectors, etc.
- Spectrum measured: estimate correlation for the ToF or other method used
- Spectrum calculated (fission): estimate correlation between thermal, 1/E and fast components, e.g. see J.G.Williams et al., "Covariance Matrixes for Calculated Neutron Spectra and Measured Dosimeter Response", ISRD-13 (May 2008), p.343
- Tool for construction of the correlation matrix from the (un)correlated uncertainties (in test yet): here (use, e.g. MERC - Medium Energy Range Correlation).
The cross sections for dosimetry reactions and cover materials schould be used from: IRDFF-1.05 and new evaluation 209Bi(n,xn), x=3-10
The dpa cross section for natural Fe is recommended to use: dpa for Fe
(details of NJOY-2012 processing of the ENDF/B-VII.1 isotope cross sections: input file, then you have to modify the beginning of tape90 as shown in tape81 to finish proccessing by GROUPR)
Cases rejected from this Exercise
Six Cases have been considered by previous Exercise REAL-88 (NMF-90) (see directory DEMO\disc1\refs) at IAEA or IAEA179 ZZ-NMF-90 at NEA (see directory PROGRAMS\DEMO\EXE\REF)
NB: All Spectra and Reaction Rates have covariance matrices!
- ANO - Pressure vessel cavity (between the pressure vessel wall and the concrete shielding) of the Arkansas Power and Light Reactor (Arkansas Nuclear One-1)
Origin: REAL84; Apriori Spectrum/Covariance: 55gr/16gr; Dosimeters (6): Cu63a, Ti46p, Ni58p, Fe54p, U238f, Np237f
Input file: ANO.DAN - PS1 - Oak Ridge Research Reactor, Poolside Facility; metallurgical irradiation experiment, simulated surveillance position Surv.Caps.
Origin: ??????; Apriori Spectrum/Covariance: 37gr/37gr; Dosimeters (9 - all in 1mm Gd): Cu63a, Ti46p, Ni58p, Sc45g, Fe54p, Fe58g, Co59g, U238f, Np237f
Input file: PS1.DAN - PS2 - Oak Ridge Research Reactor, Poolside Facility; metallurgical irradiation experiment, simulated pressure vessel capsule position T/4
Origin: ??????; Apriori Spectrum/Covariance: 37gr/37gr; Dosimeters (6): Ti46p, Ni58p, Sc45g, Fe54p, Fe58g, Co59g
Input file: PS2.DAN - RTN - Fusion simulation spectrum measured at RTNS-11, a 14 MeV neutron source at LLL (a simulation of the first wall spectrum of fusion reactor)
Origin: Greenwood; Apriori Spectrum/Covariance: 60gr/60gr; Dosimeters (12): Al27a, Ti46p, Ti47p, Ti48p, Ni58p, Ni60p, Sc45g, Fe54p, Fe58g, Co59g, Au197g, Co2n
Input file: RTN.DAN - U35 - Fission neutron spectrum of 235U
Origin: ??????; Apriori Spectrum/Covariance: 48gr/48gr; Dosimeters (22): Al27p, Al27a, Ti46p, Ti47p, Ti48p, Fe54p, Fe56p, Mn552, Ni58p, Ni582, Co59a, Cu63a, In115n, In115g, I1272, Au197g, Th232f, U235f, U238f, Np237f, Pu239f
Input file: U35.DNC - CFR - Neutron spectrum in the centre of the coupled fast reactivity measurement facility (CFRMF)
Origin: ??????; Apriori Spectrum/Covariance: 26gr/26gr; Dosimeters (23): Li6a, B10a, Al27p, Al27a, Sc45g, Ti46p, Ti47p, Ti48p, Ni58p, Co59g, Cu63g, In115g, In115n, Au197g, Th232g, U235f, U238g, Np237f, Pu239f
Input file: CFR.DAN
Dosimetry reaction cross sections database used: IRDF-90 (640 gr)
Exercise Requirements for each case
- Strongly recommend use of IRDFF cross sections and covariances, latest version: IRDFF-1.05
- Cross section library and origin (if not IRDFF)
- Computer code (and type) that was used for the adjustment
- Note on how data were processed and any problems or changes made to the data set
Exercise Reporting Requirements
- Total fluence
- Thermal fluence 0.5 eV
- Epithermal fluence between 0.5 eV and 0.1 MeV
- Fluence 0.1 MeV
- Fluence 1.0 MeV
- Fluence 20.0 MeV (for higher energies)
- Spectrum-averaged cross section (case dependent)
- dpa (need higher energy part)
- Adjusted neutron spectrum and uncertainties (lethargy)
- Adjusted reaction rates and uncertainties
- Metric for consistency of adjustment (similar to chi2?)
Potentially applicable computer codes
- STAYSL PNNL, Ref: STAYSL @ PNNL or STAYSL @ IAEA
- STAYSL'SL, Ref: ???
- LSL, Ref: RSICC PSR-233
- MAXED (part of UMG code package), Ref: NEA-1665 UMG 3.3
- CALMAR, Ref: RCM-2 presentation
- GRUPINT, Ref: ???
- FERRET, Ref: RSICC PSR-145
- NSVA, Ref: NSVA-3
- GRAVEL/SANDII, Ref: CCC-0112 SAND-II
- NEUPAC-JLOG, Ref: NEPAC-JLOG ,NEPAC-JLOG
- MIEKE, Ref: NMF-90 Codes
- MSITER, REf: Modified STAYSL code by M.Matzke NMF-90 Codes
- STAYNL, Ref: NMF-90 Codes
- KASKAD, Ref: V.Sevastyanov et al., "Characteristics of Neutron Fields" V. I and II (ISBN 978-5-903232-38-3, Mendeleevo, 2014); Izm.Tech 5(2003)58, Standards at ROSATOM