1

Input format of FRENDY
Japan Atomic Energy Agency (JAEA)
Kenichi TADA

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Input format of FRENDY• FRENDY treats two types of the input formats.
• FRENDY original input format• NJOY compatible• Simple input format• Nuclear data file name and processing mode are only
required for the processing.
• FRENDY has recommended parameters in the source code.
• User can also change (override) parameters.

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Input format of
FRENDY and NJOY
• Input parameters of

FRENDY consist of “input
data name” and “input
data”.
• Comment line is similar to

C/C++.
• //~ or /* ~ */• Input format of FRENDY

is easy to understand.
• This input format is suitablefor beginners.

[Sample input of FRENDY]
ace_fast_mode // Processing mode
nucl_file_name U235.dat
ace_file_name U235.ace
temp
296.0

[Sample input of NJOY]
reconr/ command
20 21/ input(tape20), output(tape21)'pendf tape for JENDL-4 U235' / identifier for PENDF
9228
/ mat
1.00e-03 0.00
/ err, temp0/
broadr/ command
20 21 22
/ endf, pendf(in), pendf(out)9228 1/ mat, temp no1.00e-03 -5.0E+2/ err, thnmax
296.0/ temp0/
gaspr/ command
20 22 23
/ endf, pendf(in), pendf(out)purr/ command
20 23 25
/ endf, pendf(in), pendf(out)9228 1 10 20 500/ mat, temp no, sig no, bin no, lad no296.0/ temp
1E10 1E4 1E3 300 100 30 10 1.0 0.1 1.0E-5 / sig zero0/acer
/ command
20 25 0 30 31/ nendf, npend, ngend, nace, ndir
1 1 1 0.00
/ iopt(fast), iprint(max), itype, suffix'ACE file for JENDL-4 U235' / descriptive character
9228 296.0/ mat, temp
1 1
/ newfor(yes), iopp(yes)1 1 1/ thin(1), thin(2), thin(3)
stop
/

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Manual of FRENDY• Manual of FRENDY• JAEA-Data/Code 2022-009• https://jopss.jaea.go.jp/pdfdata/JAEA-Data-Code-2022-009.pdf• There are many sample inputs in this manual.

• FRENDY package has simple input

manual.
• It also has many sample inputs.

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FRENDY original input
format6

Basics of FRENDY input format• First line must be processing mode.
• ace_fast_mode： Neutron induced ACE file• ace_tsl_mode： ACE file of thermal scattering law data
• ace_dosi_mode： Dosimetry ACE file
• mg_neutron_mode : Neutron induced multi-group XS file

• Other lines are free format.
• Setting “input data name” and “input data”• Bracket is used to describe array data, e.g., (1.0 2.0 3.0).
• Text data is surrounded by single or double quotation mark, e.g.,“~” or ‘~’.
• Multiline is available for array data and text data.

• Comment line is similar to C/C++.
• //~ or /* ~ */

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Main input parameters• Required parameters• nucl_file_name：Evaluated nuclear data file name
• nucl_file_name_tsl：TSL data file name (TSL only)• Other main input parameters• temp：Temperature (K) (Default: 293.6 K)• ace_file_name：ACE file name• ace_dir_file_name ：XSDIR file name• suffix_id：Suffix ID of ACE file• ace_label_data：Comment line of ACE file (one line)• thermal_za_id_name： S(α, β) identifier of MCNP (TSL only)• Additional parameters• write_pendf_probability_table：PENDF file name after probability table
generation• write_pendf_tsl：PENDF file name after TSL data processing (TSL only)• PENDF (Point-wise ENDF) file is a processing result of NJOY.
• These PENDF file can be used as input PENDF of NJOY.

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Example of FRENDY input (Neutron induced)
ace_fast_mode // Processing modeFirst line must be set
nucl_file_name../lib/U235.dat
processing mode.
temp /* [K] */300.0
ace_file_name./ace/U235.ace
Relative path or
absolute path
ace_dir_file_name ./xsd/U235.xsdir
ace_label_data“U-235 from JENDL-4.0”
suffix_id
0.50• Processing conditions of above example• Evaluated nuclear data file name： ../lib/U235.dat• Temperature：
300.0 [K]• ACE file name：./ace/U235.ace• XSDIR file name：./xsd/U235.xsdir• Comment line of ACE file：U-235 from JENDL-4.0• Suffix ID：
0.50

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Modification of processing conditions(Neutron induced)• Please try to modify input file if processing conditions

are changed as follows:• Evaluated nuclear data file name： ./j40/lib/Fe056.dat• Temperature：• ACE file name：• XSDIR file name：• Comment line of ACE file：• Suffix ID：• PENDF file name:550.0 [K]./j40/ace/Fe056.ace./j40/xsd/Fe056.xsdir
Fe-056 from JENDL-4.0
0.10./j40/pendf/Fe056.pendf

The answer is next slide.

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Modification of processing conditions(Neutron induced)
Input is modified to meetthe processing conditions.

ace_fast_mode // Processing mode
nucl_file_name./j40/lib/Fe056.dat
temp /* [K] */550.0
ace_file_name./j40/ace/Fe056.ace
Text data issurrounded by
ace_dir_file_name ./j40/xsd/Fe056.xsdir
single or double
ace_label_data‘Fe-056 from JENDL-4.0’ quotation mark.
suffix_id
0.10
write_pendf_probability_table ./j40/pendf/Fe056.pendf
Adding PENDF output option

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Example of FRENDY input (TSL)First line must be set
ace_tsl_mode // Processing mode
processing mode.
nucl_file_name../lib/H001.dat
nucl_file_name_tsl../lib_sab/01_h_in_h2o.txt
ace_label_data“HinH2O from JENDL-4.0”
temp
296.0
Temperature prepared in TSL
ace_file_name./ace_sab/lwtr.ace
data file (nucl_file_name_tsl)
is only available.
ace_dir_file_name./xsd_sab/lwtr.xsdir
suffix_id
0.50
S(α, β) identifier of MCNP
thermal_za_id_name “lwtr”(Maximum: 6 characters)• Processing conditions of above example• TSL data file name: ../lib_sab/01_h_in_h2o.txt• S(α, β) identifier of MCNP： lwtr
• lwtr：light water• This name is used in S(α, β) card of MCNP input.

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Modification of processing conditions (TSL)• Please try to modify input file if processing conditions arechanged as follows:• Evaluated nuclear data file name：./j40/lib/C000.dat• TSL data file name：./j40/lib/31_graphite.txe• Temperature：
500.0 [K]• ACE file name：./j40/ace/graphite.ace• XSDIR file name：./j40/xsd/graphite.xsdir• Comment line of ACE file：
Graphite from JENDL-4.0• Suffix ID：
0.10• S(α, β) identifier of MCNP：
grph• PENDF file name:./j40/pendf/graphite.pendf

The answer is next slide.

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Modification of processing conditions (TSL)
Input is modified to meetthe processing conditions.

ace_tsl_mode // Processing mode
nucl_file_name./j40/lib/C000.dat
nucl_file_name_tsl../lib_sab/31_graphite.txt
temp /* [K] */500.0
ace_file_name./j40/ace/graphite.ace
ace_dir_file_name./j40/xsd/graphite.xsdir
ace_label_data‘Graphite from JENDL-4.0’
suffix_id
0.10
thermal_za_id_name ‘grph’write_pendf_tsl./j40/pendf/graphite.pendf
Adding PENDF output option

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TSL data generation
for MCNP5 and PHITS 3.24

• Three types of ACE format is now available.
• IFENG=0 (discrete), 1 (skewed), 2 (continuous)• MCNP5 and PHITS ver.3.24 cannot treat IFENG=2.
• The default input option of FRENDY version 2 generates IFENG=2.
• Please add “weight_option” and modify parameter from “tabulated”
to “variable”.
ace_tsl_mode // Processing mode
nucl_file_name../lib/H001.dat
nucl_file_name_tsl../lib_sab/01_h_in_h2o.txt
ace_label_data“HinH2O from JENDL-4.0”
temp
296.0
ace_file_name./ace_sab/lwtr.ace
ace_dir_file_name./xsd_sab/lwtr.xsdir
suffix_id
0.50
thermal_za_id_name “lwtr”
weight_option
variable15

Difference of IWT options• IWT option affects the angular neutron flux

distribution• Angular neutron flux distribution may become jagged *).

• Recommend option: IWT=2• If users want to accurately
calculate the angular neutron
flux distribution.
• IWT must be 2 for the multigroup cross section generation.
• Do not use IWT=1 (constant).
• This option will affect not only
the angular neutron flux
distribution but also k-effective
value.
*) J. L. Conlin, et al., “Continuous-S(α, β) Capability in
MCNP, LA-UR-12-00155, LANL (2012).

Example of angular neutron
flux distribution with IWT=0/2

IWT=0

IWT=2
μ=cosθ

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IFENG option and weight_option• The value of weight_option (0~2) is identical to

iwt option in NJOY/ACER module• iwt=0 (variable), 1 (constant), 2 (tabulated)• The values of weight_option (iwt) and those of

IFENG are different.
• IFENG=0 (discrete), 1 (skewed), 2 (continuous)

IFENG

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FRENDY original input format(Multi-group generation)

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Input format of multi-group generation• Input format of multi-group generation is similar tothat of ACE file generation.
• Difference is only processing mode name• Multi-group file can be generated from ENDF and ACE files• Processing of U-235
mg_neutron_mode//Process mode
nucl_file_name ( ../lib/U235.dat ) //ENDF file name• Processing of H in H2O
mg_neutron_mode//Process mode
nucl_file_name ( ../lib/H001.dat ) //ENDF file namenucl_file_name_tsl ( ../lib/01_h_in_h2o.txt )mg_tsl_data_type (hh2o) //This data type is used for MATXS

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Default option of multi-group generation• Output format: GENDF• Weighting spectrum: 1/E• Energy group structure: XMAS 172-groupstructure• Flux calculation mode: ultra-fine group slowing
down calculation (120,000 groups)• Maximum Legendre order: 3 (P3)

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Input Example (1/7): H-001
mg_neutron_mode
nucl_file_name ( ../lib/H001.dat )mg_file_nameH001
mg_edit_option ( MATXS GENDF )temperature
300.0 //[K]mg_structure ( xmas_nea-lanl_172 )mg_weighting_spectrum ( 1/e )//Process mode//ENDF file name//Output file name//Output format//ign=18 in GROUPR/NJOY//iwt=3 in GROUPR/NJOY

Multi-group generation from ACE filemg_neutron_mode
ace_file_name ( ../ace/H001.ace )mg_file_nameH001
mg_edit_option ( MATXS GENDF )mg_structure ( xmas_nea-lanl_172 )mg_weighting_spectrum ( 1/e )//Process mode//ACE file name//Output file name//Output format//ign=18 in GROUPR/NJOY//iwt=3 in GROUPR/NJOY

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Input Example (2/7): U-235
mg_neutron_mode//Process mode
nucl_file_name ( ../lib/U235.dat )//ENDF file namemg_file_name U235//Output file namemg_edit_option ( SimpleGENDF SimpleMATXS
GENDF MATXS MGFlux )//SimpleGENDF: MATXS format consistent with NJOY99//SimpleMATXS: GENDF format consistent with NJOY99//GENDF: GENDF format consistent with NJOY2016//MATXS: MATXS format consistent with NJOY2016
temp
300.0 //[K]mg_structure ( ign18 )//ign=18 in GROUPR/NJOY
mg_weighting_spectrum ( iwt03 )// iwt=3 in GROUPR/NJOY
legendre_order3

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Input Example (3/7): U-235 with specified
energy group structure and spectrum
mg_neutron_mode//Process mode
nucl_file_name ( ../lib/U235.dat )//ENDF file namemg_file_name U235//Output file namemg_edit_option ( GENDF MATXS )temp
300.0 //[K]mg_structure ( 1.0E-5 0.625 5.0E5 1.0E6 2.0E+7 ) //4-groups
mg_weighting_spectrum ( 1.0E-5 1.0 2.0E+7 1.0 ) //constantlegendre_order3

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Input Example (4/7): H in H2O
mg_neutron_mode//Process mode
nucl_file_name( ../lib/H001.dat )//ENDF file namenucl_file_name_tsl ( ../lib/01_h_in_h2o.txt ) //TSL file namemg_edit_option ( MATXS GENDF )//Output format
mg_file_name
H_in_H2O//Output file nametemperature
293.6 //[K]mg_structure ( xmas_nea-lanl_172 )//ign=18 in GROUPR/NJOY
mg_weighting_spectrum ( 1/e )//iwt=3 in GROUPR/NJOY
mg_tsl_data_type(hh2o)

Multi-group generation from ACE filemg_neutron_mode//Process mode
ace_file_name ( ../ace/H001.ace )//ACE file nameace_file_name_tsl ( ../ace/01_h_in_h2o.ace ) //ACE file name (TSL data)
mg_edit_option ( MATXS GENDF )//Output format
mg_file_name
H_in_H2O//Output file namemg_structure ( xmas_nea-lanl_172 )// ign=18 in GROUPR/NJOY
mg_weighting_spectrum ( 1/e )//iwt=3 in GROUPR/NJOY
mg_tsl_data_type(hh2o)

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Input Example (5/7): Graphite
mg_neutron_mode//Process mode
nucl_file_name( ../lib/C012.dat )//ENDF file namenucl_file_name_tsl ( ../lib/31_graphite.txt ) //TSL file namemg_edit_option ( MATXS GENDF ) //Output format
mg_file_name
C_in_Graphite//Output file nametemperature
293.6 //[K]mg_structure ( xmas_nea-lanl_172 ) //ign=18 in GROUPR/NJOY
mg_weighting_spectrum ( 1/e )//iwt=3 in GROUPR/NJOY
mg_tsl_data_type(graph)//This data type is used//for MATXS file generation

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Input Example (6/7): UO2
mg_neutron_mode//Process mode
nucl_file_name ( ../lib/O016.dat ../lib/U235.dat ../lib/U238.dat )mg_edit_option ( SimpleGENDF SimpleMATXS GENDF MATXS"1DXS 1, 2, 4, -50" "2DXS 1, 2, 4, -50" MGFlux )//"1DXS 1, 2, 4, -50": 1D cross-section data//"2DXS 1, 2, 4, -50": 2D cross-section data//MGFlux: Multi group flux data
mg_file_name mix_UO2//Output file namemg_structure ( xmas_nea-lanl_172 ) //ign=18 in GROUPR/NJOY
mg_weighting_spectrum ( 1/e )// iwt=3 in GROUPR/NJOY
temp
600.0 //[K]legendre_order
3
//O16
U235
U238
mg_number_density(4.58e-2 7.18e-4 2.22e-2) //[1/barn/cm]
Atomic number density of each nuclide must be required
to process compound of different isotopes.

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Input example (7/7): U-235(Automated setting of background XS)
mg_neutron_mode
nucl_file_name ( ../lib/U235.dat )mg_file_name U235
mg_edit_option ( GENDF MATXS )temp
300.0 //[K]mg_structure ( ign18 )mg_weighting_spectrum ( iwt03 )//Process mode//ENDF file name//Output file name//ign=18 in GROUPR/NJOY// iwt=3 in GROUPR/NJOY

sigma_zero_data(auto 0.1 50 1.0e-10 rr linear)//Tolerance = 0.1 (10%)//Maximum number of background XS = 50//Minimum background XS = 1.0E-10 (barn)//Target of interpolation (factor / rr) = reaction rate)//Interpolation method (cubic / linear) = linear interpolation

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IFENG (weight_option) for TSL data
generation• Please check the IFENG value in the ACE file.
• IFENG=2 (weight_option: tabulated) is strongly

recommended to generate multi-group crosssection file.
• The prediction accuracy of transport calculation

becomes lower when IFENG=0 or 1.
IFENG

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NJOY compatible input
format29

Basics of NJOY compatible input format (1/2)• Each module is independent.
• RECONR, BROADR, GASPR, PURR, THERMR, …
• Input for each module is required.
• Order of module has impact on processing result.
• RECONR must be set before BROADR.
• BROADR must be set before PURR and THERMR.
• Comment line is after slash “/”.
• Input information is written in NJOY manual and source files.
• Input information uses Fortran language.
• A.gt.B→A＞B, A.ge.B→A≧B, A.lt.B→A＜B, A.le.B→A≦B• Text data is surrounded by single quotation mark.
• For example, ‘This PENDF file is U-235 from JENDL-4.0’.

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Basics of NJOY compatible input format (2/2)• Card number of input information is line number.
• The input parameters written in Card N must be set in
one line.
• If user sets slash, other input data are default values.
• Third, forth, and fifth data use default values if five data are

required in Card N and only two data are set.

• NJOY needs MAT number to identify nuclide or material.
• NJOY considers that data of many nuclides are written in

one file.
• NJOY can process data of several nuclides with one
input file.
• “tapeNN” is only available for file name.
• tape20, tape21, tape22, …, tape99

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MODER module and binary tape file• Many NJOY sample input files use MODER module

before processing.
• MODER module changes file format (ASCII, binary).
• NJOY considers that this file is binary data if users set

minus value.
• Binary data is effective to reduce data size and readout time of files.

• FRENDY cannot handle binary data.
• FRENDY considers that this file is ASCII data even if user
sets minus value.

moder
20 -21/ command/ nin, nout
Original ENDF file name：tape20
Changed file name (binary)：tape21

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NJOY modules handled in FRENDY• FRENDY version 2 handles input files of the following

NJOY modules.
• MODER, RECONR, BROADR, GASPR, PURR, UNRESR,

THERMR, ACER, GROUPR, and MATXSR.

• Though THERMR input data of NJOY2012 andNJOY2016 are different from those of NJOY99,
FRENDY can treat both input data.
• FRENDY skips new input option “iform” in THEMR of NJOY2016.
• FRENDY uses “iform=0: MF6 special”.

• Fast, thermal, and dosimetry (iopt=1~3) are only

available for ACER module.
• FRENDY considers that this input file if PURR module
even if user sets input file of UNRESR module.

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Notes on UNRESR and PURR modules• Both modules treat self-shielding effect in the unresolved

resonance region.
• PURR is only available for continuous energy Monte Carlo codes.
• PURR and UNRESR are available for multi-group calculation

codes.
• Processing time of UNRESR is much shorter than that of PURR.

• NJOY developers do not recommend to use UNRESR.
• “For most purposes, UNRESR has been superseded by PURR.”*)• “The PURR results may be more reliable at low σ0 values than
UNRESR results.”*)• FRENDY doesn’t have equivalent function of UNRESR.
• FRENDY uses equivalent function to PURR module even if user
uses input of UNRESR module.
*) R. E. MacFarlane and A. C. Kahler, “Methods for Processing ENDF/B-VII
with NJOY,” Nucl. Data Sheets, 111, pp.2739-2890 (2010).

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Multi-group XS file generation
with FRENDY/MG

Evaluatednuclear data lib.
Linearization• FRENDY will generate multi-…

group XS file using ACE file.
• FRENDY will treat input file of
GROUPR module.

Probability-tablecalculation• Procedure of multi-group XS
ACE file generation

file generation is different.
Free gas scattering law
processing

NJOY/GROUPR’s
process

Multi-group XS file
generation

Multi-group XS fileMulti-group XS file
generation(Including free gas
scattering law
processing)
FRENDY’s
process

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NJOY compatible input file generation
using FRENDY• FRENDY generates NJOY compatible input fileusing FRENDY input file.
• Adding ”_make_inp” at the end of processing mode
• ace_fast_mode_make_inp, ace_tsl_mode_make_inp,
ace_dosi_mode_make_inp• NJOY input file name is “FRENDY input file name”.njoy_input.dat.

• We strongly recommend to check generated input

file.
• Major nuclides and materials in JENDL-4.0, ENDF/B-

VIII.0, JEFF-3.3 have already checked.
• Other materials, e.g., UO2, SiO2, …, may be incorrect.
• MAT number of TSL data depends on the evaluated nuclear datalibrary.
• FRENDY cannot distinguish material data from MAT number.

36

Input check function of FRENDY• Several input parameters largely affectprocessing results.
• FRENDY verifies processing results in eachprocessing step.
• E.g., linearization and processing of thermal scattering

law data• This function is available for FRENDY input and NJOY
compatible input.
• This function will be helpful to make the correct input file.

37

Example of input check function (1/3)• ENDF-6 format allows two types of particle production

reaction (p, d, t, He-3, α).
• Total (MT=103-107) / each excited state (MT=600-849)• Total particle production cross section of some nuclides is not

identical to sum of each excited state production cross section.

• FRENDY compares total and sum of each excited state

XS• Output warning
Cross section [barn]

Comparison of MT=103 and MT=600-649

MT=103600-649
Rela. Dif.

(n,ptot) XS of Co-58
from ENDF/B-VIII.0

Relative Dif. [%]message if
total XS isdifferent to sumof each excited
XS.

38
100

• natom of THEMR and nmix of ACER

affect incoh-inela scattering XS.

Incoh-Inela XS of H in CH2

nmix=2
nmix=1

XS [barn]

Example of input check
function (2/3)

10
1.E-05×1/2
1.E-03• natom：number of principal atoms

1.E-01

Energy [eV]

• nmix：number of atom types in mixed moderator• These parameter modifies incoh-inela scattering XS.

• Users have to check XS to verify these parameters.
• FRENDY automatically checks XS.
• Incoh-inela scattering XS is nearly equal to elastic
scattering XS at the upper limit of incident energy.
• FRENDY compares these XSs at the upper energy.
• Output warning message if the relative difference is larger than 10%.

1.E+01

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Example of input check function (3/3)• ACER requires elastic scattering type.
• ielas of ACER : 0=coherent, 1=incoherent• This parameter has large impact on processing results.
• FRENDY checks elastic scattering type using PENDF file.
• LCT value of MF=6
1.E+02• Output warning message if ielas

of ACER is different to PENDF
data.

• These input check functions

will be helpful to make thecorrect input file.

XS [barn]• LCT=7: coherent, LCT=6: incoherent

1.E-01

1.E-04

ielas=1
ielas=0

1.E-07
1.E-10
1.E-05

1.E-03

1.E-01

Energy [eV]

1.E+01

40

Concluding and remarks• FRENDY treats two types of the input format.
• FRENDY input format• First line must be set processing mode.
• ace_fast_mode, ace_tsl_mode, ace_dosi_mode• Other lines are free format.
• Setting “input data name” and “input data”• Bracket is used to describe array data.
• Text data is surrounded by single or double quotation mark.
• Comment line is similar to C/C++.

• NJOY compatible input format• FRENDY version 1 handles input files of the following NJOY modules.
• RECONR, BROADR, GASPR, PURR, UNRESR, THERMR, ACER, MODER.

• Each module is independent• Input for each module is required• Order of module has impact on processing result.
• Comment line is after slash• The input parameters written in Card N must be set in one line.
• If user sets slash, other input data are default values• Input checker function of FRENDY• FRENDY verifies processing results in each processing step.

41[Appendix]
Explanation of NJOY input format

42

Input description: RECONR• Card 1：nendf npend• ENDF (input) file name and PENDF (output) file name (20~99)• Card 2：tlabel• Label (one line comment) of PENDF• Card 3：mat ncards ngrid• MAT number, Number of comment lines of PENDF file, Number of
additional energy grids• Card 4：err tempr errmax errint• Allowable error of linearization, temperature [K], Maximum error of
linearization, Allowable error of linearization (integral value)• Card 5：cards• Comment line of PEND file (Line number = ncards)• ncards=0: Skip this card
• Card 6:enode
Gray parameters:• Additional energy grid (Grid number = ngrid)
Recommended to• grid=0: Skip this card
use the default value.

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Important point: RECONR• nendf/npendf (card 1)• nendf and npendf are only available from 20 to 99.
• File name of ENDF or PENDF is tapeXX (tape20~tape99).
• ENDF file name is tape20 if nendf=20.

• Original ENDF file name: nendf, Output PENDF file name: npendf• err/errmax/errint (card 4)• We recommend to use err＝1.0E-3 (0.1%).
• Default values should be used for errmax and errint.
• tempr (card 4)• tempr must be set 0 K.
• Single-Level Breit-Wigner resonance formula can directly calculate
Doppler broadened XS using psi-chi approximation method.
• The difference at top and bottom of resonance XS will become larger

when psi-chi method is used.
• Doppler broadened XS must be calculated in BROADR module.

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Example: RECONR
reconr/ command
20 21/ input(tape20), output(tape21)'pendf tape for JENDL-4 U235' / identifier for PENDF
9228
/ mat
ncards and ngrid
1.00e-03/ err
are default value.
0/(ncards/ngrid=0)
Last data is mat=0.
(Card 3 of 2nd nuclide)tempr, errmax, anderrint are default value.

• NJOY considers that data of many nuclides are written in one

file.
• NJOY processes data of several nuclides with one input file if user

repeats Card 3~Card 6.
• mat=0 in Card 3 means the end of RECONR module.

45

Input description: BROADR• Card 1：nendf nin nout
• ENDF file name, PENDF file name before BROADR (input
PENDF), PENDF file name after BROADR (output PENDF)• Card 2：mat1 ntemp2 istart istrap temp1• MAT number, number of temperatures, whether temp1 data is
copy to nout or not, whether all temperature data is calculate
from tmep1 or not, temperature of nin (normally 0 K)
• Card 3：errthn thnmax errmax errint• Allowable error of linearization, Maximum energy of Doppler
broadening, Maximum error of linearization, Allowable error of
linearization (integral value)• errthn, errmax, and erring of BROADR is identical to err, errmax, anderrint of RECONR• Card 4：temp2• Doppler broadened temperature (temperature number=ntemp2)

46

Important point: BROADR• thnmax (card 3)• NJOY considers that thnmax is the lowest of input value,
upper boundary of resolved resonance regions, and 1 MeV.
• Old version of NJOY, e.g., NJOY99 and NJOY2012, uses
threshold energy as the thnmax.
• U-235 in JENDL-4.0 cannot be correctly processed since thresholdenergies of several reactions are very small.
• Minus thnmax value must be used to avoid this problem.
• Input value is forcibly set when user sets minus thnmax value.

• FRENDY and the current version of NJOY2016 do notcheck threshold energy.

47

Threshold reaction and Doppler broadening• Doppler broadening considers nucleus vibration.
• Threshold energy will also be moved by nucleus

vibration.
• Current nuclear data processing codes do not consider

the moving of threshold energy.
XS [b][Reaction of incident particle
and nucleus][Equation of Doppler broadening]2−𝛽 𝑣−𝑣𝑟
ቂ𝑒
1 𝛽 ∞න 𝑑𝑣𝑟 𝑣𝑟 2 𝜎 𝑣𝑟
𝜎 𝑣, 𝑇 = 22𝑣 𝜋 0−𝑒 −𝛽 𝑣+𝑣𝑟 ൧

𝑇: Temperature,
𝑣：velocity of incident particle, 𝑣𝑟 ：relative velocity

ThresholdmovingE [eV]

48

Example: BROADR
broadr/ command
20 21 22
/ endf, pendf(in), pendf(out)9228 1/ mat, temp no1.00e-03 -5.0E+2/ err, thnmax
istart, istrap, and
296.0
temp1 are default
Maximum energy is / temp
values.
forced to 500 eV. /0
Last data is mat=0.
(Card 2 of 2nd nuclide)errmax and errint
are default values.

49

Input description: GASPR• Card 1： nendf nin nout
• ENDF file name, PENDF file name before GASPR(input PENDF), PENDF file name after GASPR (output
PENDF)• GASPR requires only ENDF/PENDF file names.
• GASPR can be skipped if user does not need gas
production XS (MT=203～207).
[Example of GASPR]

gaspr
20 22 23/ command/ endf, pendf(in), pendf(out)50

Input description: PURR
• Card 1：nendf nin nout
• ENDF file name, PENDF file name before PURR (input
PENDF), PENDF file name after PURR (output PENDF)• Card 2：matd ntemp nsigz nbin nladr iprint nunx
• MAT number, number of temperatures, number of background XS, number of probability bins, number of ladders,
output option, number of energy grids (0: all)• Card 3：temp• temperature (temperature number = ntemp)• Card 4：sigz• Bagk-ground XS σ0 (sigz number = nsigz)

51

Important point: PURR
• nbin/nladr (card 2)• nbin must be larger than or equal to 15.
• Recommended nladr is larger than or equal to 100.
• iprint (card 2)• Probability table information is output in output file if iprint = 1.
• nunx (card 2)• Recommended nunx is 0, i.e., processing all energy grids.
• Considering to current computing performance, theprocessing time is not so long.
• sigz (card 4)• Back-ground XS data must be descending order.
• The first back-ground XS data must set large value, e.g.,
1.0E+10.
• NJOY considers that the first back-ground XS is infinite.
• FRENDY sorts back-ground XS data.
• FRENDY considers that the maximum back-ground XS is infinite.

52

Example: PURR
purr
/ command
20 23 24
/ endf, pendf(in), pendf(out)9228 1 10 20 100 0/ mat, temp no, sig no, bin no, lad no296.0/ temp
1E10 1E4 1E3 300 100 30 10 1 0.1 1.0E-5 / sig zero0/This value is considered
as inifinite.
Last data is mat=0.
(Card 2 of 2nd nuclide)nunx is default
value.

53

Input description: THERMR• Card 1：nendf nin nout
• ENDF file name of TSL data, PENDF file name before THERMR (input
PENDF), PENDF file name after THERMR (output PENDF)• Card 2：matde matdp nbin ntemp iin icoh iform natom

mtref iprint• MAT number of TSL data, MAT number of nuclide, number of equi-probable angular bins, number of temperatures, inelastic scattering
option, elastic scattering option, output format option, number ofprincipal atoms, MT number of inelastic scattering (221~225 only),
output option

Green parameters:• Card 3：temp
User have to read TSL• Temperature (temperature number = ntemp)
data to set theseparameters.
• Card 4：tol emax

• Allowable error of linearization, maximum energy to consider thermal

scattering• tol is identical to err in RECONR.

54

Important point: THERMR (1/3)• nendf/nin (card 1) & matde/matdp (card 2)• nendf and matde are obtained from TSL data.
• For example, TSL data file name of HinH2O and MAT number• nendf and matde are 0 for free gas scattering law processing.

• nin and matdp are obtained from nuclide data.
• For example, H-001 for HinH2O.

• iform (card 2)• Data format of angular and energy distribution can be changed
using this option.
• This option is added in NJOY2012.
• NJOY2012/2016 input is incompatible to NJOY99 input.
• Users have to check whether this input file has iform or not.
• FRENDY can treat both input format.

• mtref (card 2)• MT number of elastic scattering is mtref+1.

55

Important point: THERMR (2/3)• natom (card 2)• Number of target nuclides in a molecule.
• For example, HinH2O: natom=2, OinH2O: natom=1• ｔemp (card 3)• Temperature is only available for given temperaturesin TSL data.
• PENDF file of target nuclide must be broadened in thistemperature.
• emax (card 4)• Recommended value is the maximum energy of TSL or
higher energy, e.g., 10 eV.
• Short Collision Time (SCT) approximation is used if theenergy is higher than the given energy range in TSL data.

56

Important point: THERMR (3/3)• iin (card 2)• Meaning of iin value of NJOY2012/2016 is different to NJOY99.
• User has to check whether TSL data has inelastic scattering
data in MF=7/MT=4 or not.
• icof (card 2)• User has to check whether TSL data has elastic scattering data
in MF=7/MT=2 or not.
• Elastic scattering XS of graphite is added in output PENDF file
if user sets icof=2 and TSL data does not have elastic
scattering data.
• icof=2: compute elastic scattering XS using TSL data or elastic

scattering XS of graphite• iform (card 2)• This option is added in NJOY2012.
• NJOY2012/2016 input is incompatible to NJOY99 input.
• User have to check whether this input file has iform or not.

57

iin/icof options of NJOY99 and NJOY2016
NJOY2016

NJOY99
iinc
0
1
2
3
4

icoh

inelastic options
none
compute as free gas
reserved
reserved
read s(a,b) and compute matrix

iin inelastic options
0 none1 compute as free gas
2 read s(a,b) and compute matrix

icoh elastic options

elastic options

0 none1 compute using ENDF6 input tapedata--------or for pre-ENDF6 input set icoh =1 graphite
2 beryllium
3 beryllium oxide
11 polyethylene
Option number is
12 h(zrh)
identical!!
13 zr(zrh)

0 none1 compute using ENDF6 format data--------or for earlier formats
1 graphite
2 beryllium
3 beryllium oxide
11 polyethylene
12 h(zrh)
13 zr(zrh)58

Example: THERMR
TSL data of HinH2O does nothave elastic scattering data.
(icoh = 0)

thermr
26 23 27
1 125 60 1 2 0 0 2 221
iform natom mtref
293.6
1.0e-03 1.00001e+01/command/nendf nin nout
/matde matdp nbin ntemp iin icoh
/tempr/tol emax
Since there is iform option, thisis NJOY2012/2016 input data.

59

Input description: ACER (common)• Card 1：nendf npend ngend nace ndir
• ENDF file name, PENDF file name before ACER (input
PENDF), multi-group photon data, ACE file name, XSDIR filename
• Card 2：iopt iprint itype suff nxtra• Processing mode, output option, ACE file mode (1=ASCII,
2=binary), suffix ID, number of IZ/AW data
• FRENDY can not handle itype=2.
• iopt=1: neutron/proton induced, iopt=2: TSL, iopt=3: dosimetry,

iopt: 4: photo-atomic, iopt=5: photo-nuclear• Card 3：hk
• Label (one line comment) of ACE (Maximum: 70 characters)• Card 4：iz, aw• IZ/AW pair data (number of iz, aw = nxtra)• nxtra=0: Skip this card

60

Input description: ACER (iopt=1)• Card 5：matd tempd• MAT number, temperature• Card 6：newfor iopp
• Whether new angular distribution format (LAW=61) isused or not, whether detailed photon data is used or not• Default newfor option is 1 (use LAW=61).
• MCNP4C and later version of MCNP can handle LAW=61.

• Card 7：thin(1) thin(2) thin(3)• Data reduction option• User should not enter this option and should skip this card usingslash “/”.

61

Input description: ACER (iopt=2)• Card 8：matd tempd tname• MAT number of nuclide, temperature, S(α, β) identifier of
MCNP, e.g., lwtr (Maximum: 6 characters)• Card 8a：iza01 iza02 iza03• ZA value of target nuclide• Card 9：mti nbint mte ielas nmix emax iwt• MT number of inelastic scattering, number of energy bins of
2nd particle, MT number of elastic, whether coherent elastic(ielas=0) or incoherent elastic (ielas=1), number of atom
types in mixed moderator, maximum energy to consider
thermal scattering, output format of energy of 2nd particle• mti is 0 or mtref of THERMR, mte is 0 or mtref+1 of THERMR• Emax is emax of THERMR• iwt=0: skewed, iwt=1:discrete, iwt=2:continuous• MCNP6.1 or later version can handle iwt=2.

62

Important point: ACER (iopt=2)• tname (card 8)• This name is also used in MCNP input file.
• iza01 iza02 iza03 (card 8a)• iza02 and iza03 are normally 0.
• Target nuclide have several isotopes, e.g., Zr in ZrH, user has to set
iza02 and iza03.
• ielas (card 9)• User has to check TSL data (MF=7/MT=2) and including data type.
• nmix (card 9)• Mainly, Benzene, BeO, and SiO2 are nmix=2 and others are nmix=1• Though BeO from JENDL-4.0 is nmix=2, BeO from ENDF/B-VIII.0 is nmix=1.
• Please carefully check TSL data to process Benzene, BeO, and SiO2.

• iwt (card 9)• MCNP6.1 or later version of MCNP can handle iwt=2.
• Recommended iwt value is iwt=0 if user uses PHITS code orprevious version of MCNP.
• The nuclear calculation results using iwt=1 may no be incorrect.

63

Example: ACER (iopt=1)
If user does not use photon
data, ngend is 0.

acer/ command
20 24 0 30 31/ nendf, npend, ngend, nace, ndir
1 1 1 0.00
/ iopt(fast), iprint(max), itype, suffix'ACE file for JENDL-4 U235' / descriptive character
9228 296.0/ mat, temp
1
/ newfor(yes)/ thin(1), thin(2), thin(3)stop/
Skip Card 7 (thin(1)~thin(3)).

64

Example: ACER (iopt=2)
acer/command26 27 0 30 31/nendf npend ngend nace ndir
2 1 1 0.0 0/iopt iprint itype suff nxtra‘ACE file for HinH2O from JENDL-4.0' /hk
125 2.93600e+02 'lwtr'/matd tempd tname
1001
/iza
221 60 0 0 1 1.00001e+01 0 /mti nbint mte ielas nmix emax iwt

User considers that ‘lwtr’ means HinH2O.
(User has to use ‘lwtr’ in MCNP input file.)