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EXFOR Data in Resonance Region and Spectrometers' Response Function

(Consultants' Meeting, 8 to 10 October 2013, IAEA Headquarters, Vienna, Austria)

Background

   Neutron-induced reaction cross section data in the resonance region are important for many fields of science and technology. Regarding nuclear energy applications such data are needed for analysis of nuclear criticality safety, advanced fuel cycle developments, nuclear safeguards applications, nuclear waste managements, etc. There are very few experimental facilities worldwide providing data in the resonance region: GELINA (IRMM, Belgium), J-PARC (Japan), n_TOF (CERN), ORELA (Oak Ridge, USA), RPI (NY, USA), each with its own characteristics. All facilities employ accelerators for production of neutrons in a broad energy range and data are obtained by transmission and capture measurements by time-of-flight method. Proper analysis of the data in the resonance region (total, capture, fission cross sections, and time-of-flight spectra) requires knowledge of response functions of the complete target to detector set-up.
   The IAEA Nuclear Data Section is collecting experimental neutron-induced reaction data for the EXFOR library in collaboration with other data centres constituting the International Network of Nuclear Reaction Data Centres (NRDC). Data for neutron induced reactions in the resonance energy region are essential part of the EXFOR database. However, there are many EXFOR entries where resonance parameters are compiled without energy dependent data (cross sections, time-of-flight spectra). To make optimum use of the results of such experiments for an evaluation of cross sections it would be advisable to have the experimental observables available in a form that they can be used to extract the required parameters. We recognize that such time-of-flight data must be documented with supplemental information (e.g., experimental condition, resolution function) in order to properly process the experimental information.
   Complementary to the data obtained by conventional time-of-flight method are the results from lead slowing-down spectrometer (LSDS) measurements. Correct interpretation of the LSDS data requires additional information on spectrometer resolution function as well.


Objectives

  • Identify all observables and experimental information required for proper evaluation of neutron induced reaction data and associated uncertainties in the resonance energy range
  • Prepare templates that include the information required to be compiled in EXFOR and submit such information for different type of experiments and facilities based on the developed templates
  • Provide information and examples of response functions in order to allow NRDC community to develop rules and format for the compilation of the observables and uncertainties resulting from TOF measurements
  • Experimentalist are encourage to provide all available data and response functions for experiments already compiled in EXFOR for addition to the database

Summary Report

INDC(NDS)-0647

Recommendations for Experimentalists for Submission of Time-of-Flight Spectra (excerpt from Report INDC(NDS)-0647)

Recommendations

Template for Submission of Time-of-Flight Spectra

Template_TOF


    Templates_TOF     Response functions_TOF     Presentations     Response functions_LSDS    

#Template / Info / EXFOR SubentryReference
Title
EXFOR entry
Facility
1Template / natCd transmission/ 23077.003 J,NIM/B,267,2345,2009
The total cross section and
resonance parameters for the
0.178 eV resonance of Cd-113
EXFOR entry 23077
GELINA
2Template / 244Cm Captire/ 23141.003 J,NST,49,(7),708,2012
Neutron-capture cross-sections
of Cm-244 and Cm-246 measured
with an array of large
germanium detectors in the
ANNRI at J-PARC/MLF
EXFOR entry 23141
ANNRI
3Template / Capt(epi) 153Eu 5mil / 14382.013
Template / Capt(epi) natEu 10mil / 14382.014
Template / Capt(epi) natEu 20mil / 14382.015
Template / Capt(epi) natEu 40mil / 14382.016
Template / Trsm(epi) 153Eu 15mil / 14382.007
Template / Trsm(epi) natEu 40mil / 14382.008
Template / Capt(th) 153Eu 5mil / 14382.002
Template / Capt(th) natEu 5mil / 14382.003
Template / Capt(th) 153Eu 10mil / 14382.004
Template / Capt(th) 153Eu 15mil / 14382.005
Template / Capt(th) 153Eu 20mil / 14382.006
Template / Trsm(th) 153Eu 5mil / 14382.009
Template / Trsm(th) natEu 5mil / 14382.011
Template / Trsm(th) natEu 10mil / 14382.012
Template / Trsm(th) 153Eu 15mil / 14382.010
J,ANE,69,74,2014
Europium resonance parameters
from neutron capture and
transmission measurements in
theenergy range 0.01-200 eV
EXFOR entry 14382
RPI
4Template / natHf 1.1E-3at/b 10m / 23250.002
Template / natHf 3.3E-4at/b 10m / 23250.003
Template / natHf 9.7E-5at/b 10m / 23250.004
Template / natHf 4.6E-3at/b 60m / 23250.005
Template / natHf 4.6E-3at/b 30m / 23250.015
Template / natHf 4.6E-3at/b 10m / 23250.010
Template / 176Hf 2.2E-3at/b 30m / 23250.011
Template / 176Hf 2.2E-3at/b 30m / 23250.016
Template / 177Hf 1.9E-3at/b 10m / 23250.006
Template / 177Hf 1.9E-3at/b 30m / 23250.012
Template / 178Hf 1.8E-3at/b 30m / 23250.013
Template / 178Hf 1.8E-3at/b 10m / 23250.007
Template / 178Hf 0.8E-3at/b 10m / 23250.008
Template / 179Hf 2.1E-3at/b 10m / 23250.009
Template / 179Hf 2.1E-3at/b 30m / 23250.014
Template / 179Hf 2.1E-3at/b 30m / 23250.017
INDC(EUR)-0032
Results of time-of-flight
neutron capture measurements
of 176,177,178,179Hf enriched and
natHf samples at 10 m, 30 m,
and 60 m stations of GELINA
EXFOR entry 23250
GELINA
5Template / 59Ni(n,a) Yield and SIG / 23278.002 J,Nuclear Data Sheets 120(2014)208
The (n,alpha) Reaction in the s-process
Branching Point 59Ni
EXFOR entry 23278
n_TOF CERN
6Template / 58Ni Capture yield / 23210.006 J,Phys. Rev. C 89, 014605 (2014).
Experimental neutron capture data
of 58Ni from the CERN n TOF facility
EXFOR entry 23210
n_TOF CERN
7Template / 235U(n,f) SIG / 23294.002 EPJ Web of Conferences 111(2016)02003
High accuracy 235U(n,f) data in the
resonance energy region
EXFOR entry 23294
n_TOF CERN
8Template / 56Fe neutron inelastic scattering/ 23313 ND’97, p. 529, Trieste, Italy
PhD thesis E. Dupont
High resolution measurements of the neutron inelastic scattering
cross section of 56Fe

EXFOR entry 23313
GELINA
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