Nuclear Data Section
International Atomic Energy Agency
P.O.Box 100, A-1400 Vienna, Austria
Memo CP-D/592 (Rev.)
Date:
To:
From:

13 November 2009
Distribution
N. Otsuka, R Capote Noy

Subject:

Prompt gamma production below threshold of 2nd level excitation

If we consider reactions where mass numbers of both projectile and outgoing particle
are 1, discrete gamma production cross sections are usually coded as follows:
If SF1=SF4 (inelastic scattering),(SF1(SF2,INL)SF4,PAR,SIG,G) with γ energy under heading E, else
(SF1(SF2,SF3)SF4,PAR,SIG,G) with γ energy under heading E.

(1a)
(1b)

If the part of the data table is for incident energy below than threshold of the 2nd level
excitation, this part can be also expressed by the following codes:
If SF1=SF4 (inelastic scattering),(SF1(SF2,INL)SF4,,SIG), else(SF1(SF2,SF3)SF4,PAR,SIG)with the 1st level energy under E-LVL.

(2a)
(2b)

The expression (2) is a more general quantity than (1) and convenient for end users.
For example, the current translation program from the EXFOR to C4 format does nottranslate gamma production cross sections (1) to the C4 format and therefore
evaluators have not paid attention to the gamma production cross sections. We would
recommend to use REACTION code (2) (after separation of the relevant part from thedata table if necessary) when all or a part of measured incident energy range is lower
than the threshold of 2nd level excitation of the reaction product. Note that it isgenerally asked not to split a data set by threshold energies. See also the LEXFOR
entry “Threshold”.
Note that we should use ,DA,,4PI instead of ,SIG if authors measured angulardifferential cross section at an angle (b/sr) and multiplied 4π to it to obtain the data inbarn.

Example: 55Mn(n,inl)55Mn cross section below 0.9 MeV
E exc (55Mn)= 0 keV (5/2-), 126 keV (7/2-), 984 keV (9/2-), …
(Huo Junde, Nucl.Data Sheets 109,787,2008)

AuthorEXFOR

A.I.Lashuk et al. (1994)
D.L.Broder et al. (1968)
J.B.Guernsey et al. (1956)
N.P.Glazkov (1963)
N.P.Glazkov (1963)

41186.011
40322.003
11691.002
40680.019
40680.020

Ju.G.Degtjarev et al. (1971)

40278.004

REACTION(SF6-8)
PAR,SIG,G
PAR,SIG,G
PAR,SIG,G,SIG
PAR,SIG

PAR,SIG=PAR,SIG,G

Secondary energy
(keV)
E=126
E=130
E=130
E=128
Not shown in the figure.
(=40680.019)
E-LVL=126, 208, 308

In the current EXFOR database, three subentries (40680.019=40680.020, 40278.004)
are coded without G in SF7. Evaluated cross section in JENDL-3.3 (=JEFF-3.1,ENDF-B/VII.0) agrees with them (except 40278.004 above 0.5 MeV). Theoreticalcalculations with the EMPIRE code (undertaken within a new evaluation effort) show
calculated inelastic cross section (Hauser Feshbach + width fluctuation method) to bemuch higher than Glazkov’s data, in agreement with (n,n’γ) measurements by Lashuk
et al. Similar trend can be seen in TENDL-08 library obtained by TALYS code.
Actions to CJD:
1) 41186.All: Search data sets from the same measurement in other area 4 entries.
2) 40278.004: Check suspicious level energies (208 keV, 308 keV). “Old” levels?

Distribution:
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