Development and Testing of HENDL-ADS/MG Cross Section Library for Neutron Energy up
to 150 MeV
Development and Testing of HENDL-ADS/MG Cross Section Library for
Neutron Energy up to 150 MeV
Jun ZOU, Mengping SUN, Fang WANG, Liqin HU*, Yican WU, FDS Team
Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei,
Anhui, 230031, China
* Corresponding author: Liqin HU, Institute of Nuclear Energy Safety Technology,
Chinese Academy of Sciences, Hefei, Anhui, China, 230031.
Tel: +86 551 65591087; Fax: +86 551 6559 3686
Email address: liqin.hu@fds.org.cn,
Development and Testing of HENDL-ADS/MG Cross Section Library for Neutron Energy up to 150 MeV
Development and Testing of HENDL-ADS/MG Cross Section Library
for Neutron Energy up to 150 MeV
Jun ZOU, Mengping SUN, Fang WANG, Liqin HU, Yican WU, FDS Team
Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, 230031, China
Abstract:
To improve the accuracy of the neutronics analyses for the accelerator driven subcritical system (ADS) with
complex energy spectrum structures and strong physical effects, a coupled neutron and photon (366 n + 42γ)
multi-group cross section library HENDL-ADS/MG (Hybrid Evaluated Nuclear Data Library) for neutron
energy up to 150MeV based on FENDL3, JENDL-He and TENDL-2009 was produced by FDS team. To
validate and qualify the reliability of the high-energy cross section in HENDL-ADS/MG library, the shielding,
critical safety and JAEA 800MW ADS benchmarks, have been performed for HENDL-ADS/MG. These testing
results indicate that HENDL-ADS/MG has accuracy and reliability.
KEYWORDS: Accelerator Driven Subcritical System, Nuclear Data Library, Bendarenko, neutron integrated
benchmark

Corresponding author at: Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei, Anhui, China,
230031.
Tel.: +86 551 65591087; fax: +86 551 6559 3686. E-mail address: liqin.hu@fds.org.cn
Development and Testing of HENDL-ADS/MG Cross Section Library for Neutron Energy up to 150 MeV
1. Introduction
Accelerator Driven subcritical System (ADS) is recognized as an efficient nuclear waste transmutation
device. Recently, Chinese Academy of Sciences has made a plan to research and develop ADS. The concept of
China Lead-based Reactor (CLEAR)[1-3] is proposed and developed by FDS Team[4-10]. Neutronics
calculations and analysis are necessarily involved in designs of ADS, and nuclear data libraries are the basis of
nuclear analysis. At present, the nuclear data libraries during the world can’t fully meet the needs of nuclear
analysis in ADS system with complex energy spectrum structures and strong physical effects.
In this study complex physical effects and great energy spans accelerator driven subcritical system have
been analyzed and studied. The great energy spans were solved by extending energy group and iteration
methods, and physical effects were corrected by Bendarenko[11] and flux calculator methods[12] in the design
of nuclear data libraries of ADS system. On the basis of the analysis and studies, a coupled neutron and photon
(366 n + 42γ) cross section library HENDL-ADS/MG (Hybrid Evaluated Nuclear Data Library) based on
FENDL3[13], JENDL-He[14] and TENDL-2009[15] has been produced by FDS Team. The neutron cross
section of HENDL-ADS/MG has energy range from 10-5eV to 150 MeV. For HENDL-ADS/MG data library, in
the range of unresolved resonance region (100 eV~10 keV) have been treated with Bondarenko method, but in
the range of resolved resonance region (4 eV~100 eV), should be treated with flux calculator method.
In order to test the availability and reliability of the HENDL-ADS/MG data library, shielding and critical
safety benchmarks were performed in this paper using VisualBUS[16-22] code. The discrepancy between
calculation and experimental values of nuclear parameters falls into a reasonable range. To validate and qualify
the reliability of the high-energy cross section for HENDL-ADS/MG library, the shielding, critical safety and
JAEA 800MW ADS benchmarks, have been performed for HENDL-ADS/MG. These benchmark results
indicated that HENDL-ADS/MG had accuracy and reliability.
Development and Testing of HENDL-ADS/MG Cross Section Library for Neutron Energy up to 150 MeV
2. Design of HENDL-ADS/MG
The neutron energy span is large, for the accelerator driven subcritical system, its neutron energy had a
range from 10-5eV to 150MeV. The group structure was 366 neutron groups, 42 gamma groups. And the
complex physical effects including resonance self-shielding, thermal neutron up-scattering effect also should be
considered in the design of HENDL-ADS/MG. In the range of unresolved resonance region (100 eV~10 keV),
self-shielding effect can be treated with Bendarenko method. But in the range of resolved resonance region
(4~100 eV), it should be treated with flux calculator. And then, the neutron energy structure, weight function
and complex physical effects were introduced.
2.1. Selection of Evaluated Nuclear Data Files
The HENDL-ADS/MG consisting of 408 nuclide cross-section files, which include moderators, structural
materials, fission products and actinides were developed. The neutron evaluated nuclear data files were
FENDL3 , JENDL/He-2007 and TENDL-2009, the photo-atomic data was ENDF/B-VI[23].
2.2.Design of Energy Structure and Weight Function
Development and Testing of HENDL-ADS/MG Cross Section Library for Neutron Energy up to 150 MeV
2.2.1. Energy Structure
For HENDL-ADS/MG data library, the neutron energy was from 10-5eV to 150MeV. The neutron structure
up 20MeV was 51 groups. The selection of neutron energy boundary from 20MeV to 150 MeV accorded as
cross section threshold and lethargy. The lethargy width is 0.05. The portion below 4.0eV of the neutron group
structure of HENDL-ADS/MG was a detailed thermal structure, which was finer than the WIMSD-69[24]
structure. And the group in the epithermal range was finer than 175-group. The other group structure was
similar to that of Vitamin-J[12]. The gamma structure from 1keV to 50 MeV was 42 groups. The energy
structure of HENDL-ADS/MG can meet the need of nuclear design for ADS system.
2.2.2. Weight Function
The accelerator driven subcritical system is driven by spallation neutron source, which has neutron spectrum
mixed with spallation and fission. The neutron weight function of HENDL-ADS/MG had the following
segments: a 0.0253-eV thermal Maxwellian below 4 eV, a l/E law from 4 eV to 2.12 MeV, a 1.415-MeV fission
spectrum from 2.12 to10 MeV, another l/E section from 10 to 12.52 MeV, a fusion peak between 12.52 and
15.68 MeV, a final l/E section from 15.5 to 19.64 MeV, and an adopted 1/E spectrum from 19.64 to 150 MeV
according to optimization analysis. The gamma weight function was 1/E + roll-offs between 1keV and 50 MeV.
The thinning tolerance in BROADR was 0.1% and the number of probability bins in PURR was 20. Legendre
order was P-6 for transport correction to P-5.
2.3. Correction for Physical Effects
2.3.1. Resonance Self-Shielding Effect
The correction of resonance self-shielding effect was implemented by making multi-group cross section data
library with different reference background cross sections. The precision of correction self-shielding effect was
determined by the selection for background cross sections[25-27] in the design of HENDL-ADS/MG. There
Development and Testing of HENDL-ADS/MG Cross Section Library for Neutron Energy up to 150 MeV
were 10 reference background cross sections for the nuclides in HENDL-ADS/MG. And the reference
background cross sections were chosen according to the compositions which the nuclides were likely to be used.
In this study, the typical design for ADS subcritical system also should be considered in the selection for
background cross sections. The following was the reference background cross-sections (barns) for Pu239:
1010 ,104 ,103 102 ,50, 10, 1 ,0.5 , 0.3, 0.1.
2.3.2. Thermal Upscattering Effect
The thermal scatter cross section was made in HENDL-ADS/MG to solve the thermal upscattering effect in the
nuclear analysis for sub-critical system. The following was the main parameters for thermal scatter cross section
：
1）Tolerance: 0.1% ; Maximum energy: 4 eV
2）Scattering laws:
a) H-1:S(α,β) for hydrogen bound in water
b) H-2:S(α,β) for deuterium bound in heavy water
c) C:S(α,β) for carbon in graphite
d) Be9: S(α,β) for carbon in Beryllium
e) Free gas model for all materials
3. Benchmark Calculation
To test the accuracy and reliability of HENDL-ADS/MG, shielding and critical safety benchmarks were
performed in this paper using VisualBUS code. In order to test the reliability of cross section with high neutron
energy, the transport calculations for high neutronics integral experiments in TIARA were accomplished by the
use of HENDL-ADS/MG library.
Development and Testing of HENDL-ADS/MG Cross Section Library for Neutron Energy up to 150 MeV
3.1 Critical Safety Benchmark
The critical spheres were derived from International Criticality Safety Benchmark Evaluation Project[28].
The calculation code was VisualBUS. Based on criticality calculations using VisualBUS and the
HENDL-ADS/MG library, the agreement between experimentally measured and computed values of Keff was
very good. As shown in Table 1, the relative error of computed Keff for all experiments was within almost 0.5%.
Table 1 computational and experimental Keff of spherical shells
VisualBUS
HENDL-ADS/MG
0.99649
0.99732
1.00400
1.00211
1.00492
0.99951
1.00033
1.00432
1.00481
1.00258
0.99629
Critical spheres
U233-MET-FAST-001
U233-MET-FAST-002
HEU-MET-FAST-001
HEU-MET-FAST-027
PU-MET-FAST-001
PU-MET-FAST-005
PU-MET-FAST-035
SPEC-MET-FAST-008
SPEC-MET-FAST-001
U233-SOL-THERM-001
PU-SOL-THERM-002
VisualBUS
ENDF-B/VII
0.9931
0.9954
0.9972
1.0090
0.9969
1.0080
1.0035
1.0073
1.0074
1.0020
1.0004
Experiment Values
1.0000
1.0000
1.0000
1.0000
1.0000
1.0000
1.0000
1.0026
1.0000
1.0005
1.0000
3.2 Shielding Benchmark
These benchmark experiments were based on sphere shell geometry with 14MeV D-T fusion neutron
source at the center of the inner void sphere. The detailed description of these experiments can be found in
Refs[29-30]. The simulation results of C/E (calculated/experimental) values of integral neutron leakage rate
using VisualBUS& HENDL-ADS/MG and ENDF/B-VII, and the corresponding experimental measured values
were all listed in Table 2.
Table 2 results of neutron leakage rate
Sphere
Shell
Be
Al
Energy ranger
(MeV)
0.003~1.0
1.0~5.0
5.0~10.0
10.0~20.0
>0.003
0.1~1.0
1.0~5.0
5.0~10.0
Experiment
values
(1/sn)
.469
.315
.143
.324
1.26
.069
.148
.050
Integrated neutron leakage rate C/E
VisualBUS
VisualBUS
HENDL-ADS/MG
(ENDF-B/VII)
1.03
0.99
0.85
0.84
0.94
0.90
1.35
1.20
1.06
0.99
0.72
0.62
0.78
0.76
0.77
0.79
Development and Testing of HENDL-ADS/MG Cross Section Library for Neutron Energy up to 150 MeV
Ti
V
Cr
Fe
Cu
Zr
W
Pb
10.0~20.0
>0.1
0.1~1.0
1.0~5.0
5.0~10.0
10.0~20.0
>0.1
0.1~1.0
1.0~5.0
5.0~10.0
10.0~20.0
>0.1
0.1~1.0
1.0~5.0
5.0~10.0
10.0~20.0
>0.1
0.05~1.0
1.0~5.0
5.0~10.
10.0~20.0
>0.1
0.1~1.0
1.0~5.0
5.0~10.0
10.0~20.0
>0.1
0.1~1.0
1.0~5.0
5.0~10.0
10.0~20.0
>0.1
0.1~1.0
1.0~5.0
5.0~10.0
10.0~20.0
>0.1
0.4~0.8
0.8~1.4
1.4~2.5
2.5~4.0
4.0~6.5
6.5~10.5
10.5~20.0
>0.4
.675
.942
.086
.152
.038
.598
.874
.391
.301
.0377
.381
1.11
.211
.221
.041
.549
1.02
.099
.140
.032
.740
1.01
.660
.145
.013
.079
.898
.442
.307
.033
.317
1.10
.360
.241
.040
.710
1.35
.173
.212
.231
.100
.035
.038
.489
1.28
1.12
1.02
1.16
0.93
0.84
1.27
1.20
1.10
1.11
1.02
0.89
1.03
1.04
1.04
0.97
1.01
1.02
1.24
1.10
0.99
0.98
1.01
1.05
1.02
1.20
1.07
1.01
1.20
1.04
0.97
1.31
1.17
1.13
0.74
0.43
0.94
0.94
1.17
1.08
1.15
1.13
0.88
0.62
1.00
1.04
1.10
1.03
1.31
0.93
0.84
1.27
1.20
1.21
1.05
1.22
0.88
1.06
1.07
1.13
1.14
0.97
1.04
1.30
1.22
1.02
0.96
1.03
0.99
1.17
1.26
0.93
1.01
1.20
1.00
0.95
1.36
1.18
1.11
0.79
0.44
0.93
0.94
1.00
1.04
1.05
1.00
0.88
0.71
1.07
1.02
The neutron leakage spectra results showed that a good agreement between HENDL-ADS/MG and the
experiment results in the Be, Fe, Ti, V, Cr, Cu, and Zr spherical shell. For the spherical shell of Al, W, the
difference of neutron leakage spectra was more than 30% between VisualBUS with HENDL-ADS/MG and
experiment. But the calculations with HENDL-ADS/MG were almost the same as ENDF-B/VII (point-wise)
calculations for these models. The difference between experiment and calculation may be caused by the error of
measurement.
Development and Testing of HENDL-ADS/MG Cross Section Library for Neutron Energy up to 150 MeV
3.3 ANALYSIS OF NEUTRON SHIELDING EXPERIMENT AT JAERI/TIARA
In order to validate and qualify the reliability of the high-energy cross section for HENDL-ADS/MG
library, the high neutronics integral experiments[31]—TIARA (JAERI) have been performed by VisualBUS&
HENDL-ADS/MG. The test shield of Iron, Lead, Graphite and Cement from 10cm to 60cm in thickness was
located at the end of the collimator with or without an additional sample shield. Neutron spectra were measured
with NE213 detectors on the beam axis and at 5~7cm off the beam axis behind the test shield. The energy of
incident proton was 65MeV. The comparison between the calculations and measurements for neutron spectra
above 10MeV on the beam axis is carried out in this paper. The analysis with VisualBUS and
HENDL-ADS/MG were carried out. At the same time, Monte Carlo calculations with MCNPX[32] code and
LA150[33] data library were also carried out for the benchmark analyses in order to make a comparison with
those of HENDL-ADS/MG. The results are shown in Fig1~Fig4.
EXP-20
EXP-40
LA150-20
LA150-40
HENDL-ADS-20
HENDL-ADS-40
Neution Flux((n/Sr/MeV/proton)
Neution Flux((n/Sr/MeV/proton)
1E-11
1E-12
1E-13
1E-14
EXP-10
EXP-20
EXP-30
LA150-10
LA150-20
LA150-30
HENDL-ADS-10
HENDL-ADS-20
HENDL-ADS-30
1E-10
1E-11
1E-12
1E-13
1E-15
0
10
20
30
40
50
60
70
0
10
20
Neutron Energy(MeV)
Fig1 Iron Shield Experiment Benchmark
1E-10
1E-11
1E-12
1E-13
1E-14
1E-15
1E-16
10
20
30
40
50
50
60
70
60
Neutron Energy(MeV)
Fig3 Graphite Shield Experiment Benchmark
EXP-20
EXP-50
LA150-20
LA150-50
HENDL-ADS-20
HENDL-ADS-50
1E-10
Neution Flux((n/Sr/MeV/proton)
Neution Flux((n/Sr/MeV/proton)
1E-9
40
Fig2 Lead Shield Experiment Benchmark
EXP-30
EXP-60
LA150-30
LA150-60
HENDL-ADS-30
HENDL-ADS-60
1E-8
30
Neutron Energy(MeV)
1E-11
1E-12
1E-13
1E-14
0
10
20
30
40
50
60
70
Neutron Energy(MeV)
Fig4 Concrete Shield Experiment Benchmark
For the Fe, Pb benchmark experiment, the difference of neutron flux was more than 20% between
Development and Testing of HENDL-ADS/MG Cross Section Library for Neutron Energy up to 150 MeV
VisualBUS with HENDL-ADS/MG and experiment. But the calculations with HENDL-ADS/MG were almost
the same as MCNPX&LA150 calculations for these models, the difference was about 5% between
HENDL-ADS/MG with LA150 data library. For graphite, concrete benchmark experiment, the agreement
between experimentally measured and calculated values of neutron flux was very good. And the neutron flux
calculated with HENDL-ADS/MG agree with the measured ones than those with LA150.
3.4 JAEA 800MW ADS Benchmark
In order to test the reliability of HENDL-ADS/MG library applied in the neutronics analysis for ADS, the
JAEA 800MW ADS[34] benchmark have been performed by VisualBUS& HENDL -ADS/MG. The JAEA
800MW ADS benchmark problem was proposed as one of the problems discussed in the International Atomic
Energy Agency (IAEA) Coordinated Research Project (CRP) on “Analytical and experimental benchmark
analyses of accelerator driven systems [35]”. The purpose of this benchmark problem was to obtain
fundamental knowledge of calculation accuracy for a commercial grade ADS. Figure 5 shows the RZ
calculation model and the initial homogeneous number densities of each fuel region.
Fig5 RZ calculation model and Fuel composition
In this paper, the Keff value at beginning of cycle (BoC) for JAEA 800MW ADS model were calculated by
HENDL-ADS/MG. At the same time, Monte Carlo calculations with VisualBUS code and point-wise nuclear
data libraries HENDL-ADS/MC [36] (same evaluated source with HENDL-ADS /MG), JENDL-4.0,
ENDF/B-VII.1 and JEFF-3.1 were also carried out for the benchmark analyses in order to make a comparison
Development and Testing of HENDL-ADS/MG Cross Section Library for Neutron Energy up to 150 MeV
with those of HENDL-ADS/MG. The calculated results were all listed in Table 3.
Table3 Keff by different data library
Nuclear data
Keff
HENDL-ADS/MG
0.9843
HENDL-ADS/MC
0.9834
JENDL-4.0
0.9776
ENDF/B-VII.1
0.9820
JEFF-3.1
0.9923
Mean
0.9839
*Relative Deviation from the mean=(Keff value-Mean)/Mean×100
Rel. Dev (%)*
0.049%
-0.043%
-0.632%
-0.185%
0.862%
0
The agreement between HENDL-ADS/MG and mean value of Keff was good. As shown in Table 7, for
HENDL-ADS/MG, the relative deviation from the mean was about 0.049%. The calculations with
HENDL-ADS/MG were almost the same as that with HENDL-ADS/MC. This result showed that the design of
energy structure and weight function for HENDL-ADS/MG was rational and accurate. This benchmark result of
JAEA 800MW ADS preliminary confirmed the reliability of HENDL-ADS/MG library applied in the
neutronics analysis for ADS.
4 Conclusions
In this study, a coupled neutron and photon (366 n + 42γ) multi-group cross section library
HENDL-ADS/MG for neutron energy up to 150 MeV based on FENDL3, JENDL-He and TENDL-2009, has
been developed, which considered complex physical effects including resonance self-shielding in the nuclear
analysis for ADS subcritical system.
The shielding and critical safety benchmarks were performed in this paper. The discrepancy between
calculation and experimental values of nuclear parameters falls into a reasonable range. To validate and qualify
the reliability of the high-energy cross section for HENDL-ADS/MG library, the transport calculations for
neutronics integral experiments in the high-energy range have been performed. In order to test the reliability of
this library applied in the neutronics analysis for ADS, the JAEA 800MW ADS benchmark have been
performed by HENDL-ADS/MG. These testing results indicated that HENDL-ADS/MG has accuracy and
Development and Testing of HENDL-ADS/MG Cross Section Library for Neutron Energy up to 150 MeV
reliability.
Acknowledgements
This work was supported by the “Strategic Priority Research Program” of the Chinese Academy of Sciences
under grant No. XDA03040000 , the National Natural Science Foundation of China (No. 91026004 and
11305205), the National Special Program for ITER (No. 2014GB1120001), the Informatizational Special
Projects of Chinese Academy of Sciences(No. XXH12504-1-09), and the Natural Science Foundation of China
under grant No.51076166. We thank our colleagues Jieqiong Jiang, Zhong Chen, Yan Chen, Jing Song for their
help. The authors would also like to thank all the reviewers for their valuable comments and suggestions which
have definitely improved the quality of this paper.
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