3.4. Card 3.5: Data library selection

Table 3.4.1 INXSLIB PHITS: same name

Value	(hnxslib)	Description
(D=0, DP=100)		Neutron reaction cross section library selection. Only when inxslib=-1 does hnxslib also have to be included.
= 0, 40	(none)	JEFF-3.1A [KFK+06]
= 1	(Legacy2001)	FENDL/A-2.0, 175-group (WARNING [1]) [PWK+97]
= 2, 20	(JENDL-AD17)	JENDL/AD-2017 (NOTE [2]) [SIK+15]
= 21	(JENDL-4-0-)	JENDL-4.0 [SIN+11]
= 30	(ENDF-B-7-1)	ENDF/B-VII.1 [CHOblovzinsky+11]
= 31	(ENDF-B-8-0)	ENDF/B-VIII.0 [BCC+18]
= 41	(JEFF-3-3--)	JEFF-3.3 [PCDSJ+20]
= 50	(FENDL-A-30)	FENDL/A-3.0 [FCO+12]
= 51	(EAF-2010--)	EAF-2010 [SPK+10]
= 60	(BROND-3-1-)	BROND-3.1 [BGI+16]
= 70	(CENDL-3-1-)	CENDL-3.1 (NOTE [3]) [GZX+11]
= 90	(TENDL-2017)	TENDL-2017 (file distributed separately [4]) [RKS+17]
= 100 [5]	(h-JP-US-EU)	hybrid library composed of, in order: Jendl-5 + Fendl/a-3.0 + Jendl-4.0 + Endf/b-viii.0 + Jeff-3.3
= 101	(h-US-JP-EU)	hybrid library: Endf/b-viii.0 + Jendl-5 + Fendl/a-3.0 + Jendl-4.0 + Jeff-3.3
= 102	(h-EU-US-JP)	hybrid library: Fendl/a-3.0 + Jendl-5 + Jeff-3.3 + Endf/b-viii.0 + Jendl-4.0
= 120	(h-JENDLAD4)	hybrid library: Jendl/ad-2017 + Jendl-4.0 + Endf/b-viii.0 + Jeff-3.3 + Fendl/a-3.0 (The default library before version 3.34)
= -1	(custom-lib)	custom neutron reaction library file named hnxslib_n_act_xs_lib in DCHAIN data folder

When selecting an individual library with INXSLIB = 41, 30, 31, 60, 70, or 21, take care regarding the treatment of isomeric (metastable) states. See Section 4.6.1 for details.

Table 3.4.2 IDCYLIB PHITS: same name

Value	(hdcylib)	Description
(D=0, DP=5)		Decay data library selection.
= 0	(none)	original decay library (80s/90s evaluations [6])
= 2	(JENDLDDF15)	new decay data from JENDL/DDF-2015 [KM16]
= 3	(ENDFBVIII0)	new decay data from ENDF/B-VIII.0 [BCC+18]
= 4	(EB8-J15-ES)	new hybrid library from, in preferential order, ENDF/B-VIII.0, JENDL/DDF-2015, and ENSDF
= 5	(J15-EB8-ES)	new hybrid library from, in preferential order, JENDL/DDF-2015, ENDF/B-VIII.0, and ENSDF
= -1	(custom-lib)	user-provided custom decay data library files

Table 3.4.3 INFYLIB PHITS: same name

Value	Description	(hnfylib)
(D=0, DP=17, requires IFISYD\(>\)0)	Evaluated induced fission yield data library selection [7], used in addition to energy-dependent, model-calculated yields (GEF code [SJAS16]) where evaluated data is unavailable.
= 0	No evaluated nuclear data files are used; only the GEF code’s calculated induced fission yields are used.
= 10	ENDF/B-VI [Ros91]	(endfb6)
= 11	JNDC-FP_V2 [TKI+90]	(jndcfp2)
= 12	ENDF/B-VIII.0 [BCC+18]	(endfb8)
= 13	JENDL/FPY-2011 [Kat12]	(jendlfpy2011)
= 14	JEFF-3.3 [PCDSJ+20]	(jeff33)
= 16	hybrid: Endf/b-viii.0 + Jeff-3.3	(h-ENDF8-JEFF)
= 17	hybrid: Jendl/fpy-2011 + Jeff-3.3	(h-JENDL-JEFF)
= 18	hybrid: Jeff-3.3 + Endf/b-viii.0	(h-JEFF-ENDF8)
= 19	hybrid: Jeff-3.3 + Jendl/fpy-2011	(h-JEFF-JENDL)
= -1	custom evaluated induced fission yield library file named fyield.hnfylib	(custom-lib)

Table 3.4.4 INFYERG PHITS: same name

Value	Description
(D=4, requires IFISYD\(>\)0 and INFYLIB\(\neq\)0)	Specify the neutron energy used for the evaluated induced fission yield library. [8]
= 1	Thermal \(\,\) (0.0253 eV)
= 2	Fast \(\qquad\) (500 keV)
= 3	Fusion \(\quad\) (14 MeV)
= 4	All 3 energies. If using this option, ERGTHFA and ERGFAFU control the energies at which the above three sets of data transition from one to the next. If the data is missing one of the three energies, yields from the next lowest energy are used instead.

Table 3.4.5 ERGTHFA PHITS: same name

Value	Description
(D=0.1, requires INFYERG=4)	Specify neutron energy threshold, in MeV, to switch from Thermal to Fast evaluated neutron fission yield data.

Table 3.4.6 ERGFAFU PHITS: same name

Value	Description
(D=10.0, requires INFYERG=4)	Specify neutron energy threshold, in MeV, to switch from Fast to Fusion evaluated neutron fission yield data.

Table 3.4.7 ISFYLIB PHITS: same name

Value	Description	(hsfylib)
(D=1, requires IFISYD\(=\)2)	Evaluated spontaneous fission yield data library selection, used in addition to model-calculated yields (from GEFY [Sch20] and the GEF code [SJAS16]) where evaluated data is unavailable.
= 0	No evaluated nuclear data files are used; only the GEF code’s calculated spontaneous fission yields are used.
= 1	Adopt the same data source as specified by INFYLIB
= 10	ENDF/B-VI [Ros91]	(endfb6)
= 11	JNDC-FP_V2 [TKI+90]	(jndcfp2)
= 12	ENDF/B-VIII.0 [BCC+18]	(endfb8)
= 13	JENDL/FPY-2011 [Kat12]	(jendlfpy2011)
= 14	JEFF-3.3 [PCDSJ+20]	(jeff33)
= 16	hybrid: Endf/b-viii.0 + Jeff-3.3	(h-ENDF8-JEFF)
= 17	hybrid: Jendl/fpy-2011 + Jeff-3.3	(h-JENDL-JEFF)
= 18	hybrid: Jeff-3.3 + Endf/b-viii.0	(h-JEFF-ENDF8)
= 19	hybrid: Jeff-3.3 + Jendl/fpy-2011	(h-JEFF-JENDL)
= -1	custom evaluated spontaneous fission yield library file named sfyield.hsfylib	(custom-lib)

Table 3.4.8 HNXSLIB PHITS: same name

Value	Description
(D=“custom-lib”, DP=“h-JP-US-EU”)	Identification tag of custom neutron reaction cross section library files [9]. Only used if INXSLIB = -1.

Table 3.4.9 HDCYLIB PHITS: same name

Value	Description
(D=“custom-lib”, DP=“J15-EB8-ES”)	Identification tag of custom decay data library files [10]. Only used if IDCYLIB = -1.

Table 3.4.10 HNFYLIB PHITS: same name

Value	Description
(D=“custom-lib”, DP=“h-JENDL-JEFF”)	Identification tag of custom induced fission yield library files [11]. Only used if IFISYE = -1.

Table 3.4.11 HSFYLIB PHITS: same name

Value	Description
(D=“custom-lib”, DP=“h-JENDL-JEFF”)	Identification tag of custom spontaneous fission yield library files [12]. Only used if IFISYS = -1.

[1]

The neutron flux energy binning must match that of the data library. [T-Dchain] automatically generates a [T-Track] tally for neutrons which uses the ECCO 1968-group structure. To use the old FENDL/A-2.0 library whose data is binned in the VITAMIN-J 175-group structure, one must create a custom [T-Track] neutron flux tally with the desired energy binning and list its output file in HNFLUXS (or use a very old output file already in this format). All other libraries use the ECCO 1968-group structure.

[2]

Mainly intended for use with long-lived (\(t_{1/2}>30\) days) nuclides; see 4.6.1.

[3]

Missing isotopic data for S, Cl, K, Ca, V, Zn, W, Hg, and Tl; see 4.6.1.

[4]

Due to its large size, TENDL-2017 is available separately by download from https://phits.jaea.go.jp/image/TENDL-2017_n_act_xs_lib.zip. Unzip the file and place it in the dchain-sp/data/ folder to use it.

[5]

Hybrid libraries are composed of reactions preferentially selected from various sources; see 4.6.2.

[6]

EAF-3.1, FENDL/D-1, ENSDF (1997), Table of Isotopes 8^th ed., and Chart of the Nuclides 1996

[7]

A list of fissioning nuclides in each library is provided in 4.6.3; hybrid libraries consist of the primary source plus extra fission targets/energies in the secondary library source.

[8]

If INFYERG = 1/2/3, evaluated data for fission induced by the stated single neutron energy is used, meaning all fissions result in the same yield distribution, regardless of the true neutron energies. INFYERG = 4 allows for this to be expanded into a simple 3-group structure. Fission yields from nuclei not in the selected evaluated database are taken from the energy-dependent GEF-calculated yields automatically.

[9]

Refer to Section 4.6 for further explanation of these parameters and their usage with custom libraries.

[10]

Refer to Section 4.6 for further explanation of these parameters and their usage with custom libraries.

[11]

Refer to Section 4.6 for further explanation of these parameters and their usage with custom libraries.

[12]

Refer to Section 4.6 for further explanation of these parameters and their usage with custom libraries.