NEA/WPEC–14

International Evaluation Co-operation

VOLUME 14
PROCESSING AND VALIDATION OF
INTERMEDIATE ENERGY EVALUATED DATA FILES

A report by the Working Partyon International Evaluation Co-operationof the NEA Nuclear Science Committee

CO-ORDINATOR/MONITOR
A.J. Koning
Nuclear Research andConsultancy Group (NRG)
THE NETHERLANDSNUCLEAR ENERGY AGENCY
ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENTORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT
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FOREWORD

A Working Party on International Evaluation Co-operation was establishedunder the sponsorship of the OECD/NEA Nuclear Science Committee (NSC)
to promote the exchange of information on nuclear data evaluations, validation,and related topics. Its aim is also to provide a framework for co-operative
activities between members of the major nuclear data evaluation projects.
This includes the possible exchange of scientists in order to encourage
co-operation. Requirements for experimental data resulting from this activity arecompiled. The working party determines common criteria for evaluated nuclear
data files with a view to assessing and improving the quality and completenessof evaluated data.
The parties to the project are: ENDF (United States), JEF/EFF (NEA Data
Bank Member countries), and JENDL (Japan). Co-operation with evaluation
projects of non-OECD countries, specifically the Russian BROND and Chinese
CENDL projects, are organised through the Nuclear Data Section of theInternational Atomic Energy Agency (IAEA).
Subgroup 14 of the working party was set up with the objective of assessing
the quality and practical use of intermediate energy evaluated data files.
The current collection of intermediate energy data files was established, with thecriterion being the processability of the data files for current transport codes.
The quality of the pointwise data for neutrons and protons on several isotopes up
to 150 MeV was reviewed. This was done by means of the data files themselves,
associated cross-section plots and outputs of checking codes. In the process, theLA150 library was recommended for inclusion in ENDF/B-VI. An integral
transport calculation with MCNPX was performed to validate the files against aneutron transmission experiment.
The opinions expressed in this report are those of the authors only and do
not necessarily represent the position of any Member country or internationalorganisation. This report is published on the responsibility of the Secretary-Generalof the OECD.

3TABLE OF CONTENTS

SUMMARY ...................................................................................................

7

1.

Data files above 20 MeV........................................................................

9

2.

Review of the basic data........................................................................

10

2.1 LA150 library ..................................................................................

10

2.1.1 Cross-section plots ................................................................

11

2.1.2 BNL checking codes ..............................................................

12

2.2 NRG/CEA library............................................................................

12

2.3 JENDL HE library..........................................................................

12

2.4 Processing .......................................................................................

13

3.

Validation on an integral experiment with MCNPX..........................

13

4.

Conclusions ............................................................................................

15

REFERENCES ..............................................................................................

17

TABLES .........................................................................................................

19

FIGURES .......................................................................................................

25

5

SUMMARY

Current accelerator-driven and other intermediate energy technologies
require accurate nuclear data to model the performance of the target/blanket
assembly, neutron production, activation, heating and damage. In a previous
WPEC subgroup, SG13 on intermediate energy nuclear data, various aspects ofintermediate energy data, such as nuclear data needs, experiments, model
calculations and file formatting issues were investigated and categorised tocome to a joint evaluation effort. The successor of SG13, SG14 on the processing
and validation of intermediate energy evaluated data files, goes one step further.
The nuclear data files that have been created with the aforementioned informationneed to be processed and validated in order to be applicable in realistic
intermediate energy simulations. We emphasise that the work of SG14 excludes
the 0-20 MeV data part of the neutron evaluations, which is supposed to becovered elsewhere. This final report contains the following sections:•

Section 2: A survey of the data files above 20 MeV that have been
considered for validation in SG14.

•

Section 3: A summary of the review of the 150 MeV intermediate
energy data files for ENDF/B-VI and, more briefly, the other libraries.

•

Section 4: Validation of the data library against an integral experimentwith MCNPX.

•

Section 5: Conclusions.

7PROCESSING AND VALIDATION OF
INTERMEDIATE ENERGY EVALUATED DATA FILES

1.

Data files above 20 MeV

The various intermediate energy files that have been created have several
things in common:•

They are usually created for both incident neutrons and protons.

•

They are stored in the ENDF-6 format.

•

The usual upper energy limit is 150 MeV, though some files up to
50 MeV (for fusion) exist.

•

The part below 20 MeV is usually left untouched, whereas the part
above 20 MeV is primarily based on new model calculations, which are
guided by the few existing experimental data sets.

Table 1 gives the entire collection of intermediate energy data files that ispresently known to SG14. The criterion of being included in this table is that thedata file has been, or will be in the near future, successfully used in a transport
code (in practice, at the moment this means either MCNP-4A/B/C or MCNPX).
The following (partial) libraries were considered:•Los Alamos LA150 [1]. This is a neutron and proton library up to
150 MeV for a suite of isotopes. The library has been tested against both
microscopic and integral experiments. The LA150 library was producedin collaboration with JAERI, Japan and NRG, Petten.

•

NRG/CEA [2]. This presently consists of 150 MeV neutron and proton
files for the main iron and nickel isotopes. The library is the result of acollaboration between NRG, Petten and CEA, Bruyères-le-Châtel.

•JENDL/HE [3]. This is a 50 MeV neutron data library for isotopes
relevant for fusion. The library is produced at JAERI.

9

2.

•

IPPE/FZK [4]. This is also a 50 MeV neutron data library for isotopes
relevant for fusion. The library was produced by IPPE Obninsk and FZK
Karlsruhe.

•

IPPE/KTH [5]. This consists of 150 MeV neutron and proton files forthe main thorium and uranium isotopes. This library was produced by
IPPE Obninsk and KTH Stockholm for the IABAT project of the EU.

Review of the basic data

As argued in several papers [1,2,6], below 150 MeV the predictive powerof several pre-equilibrium/statistical model codes is superior to intranuclear
cascade codes for continuum reactions. Also, individual reaction mechanisms(giant resonances, direct collective reactions, etc.) constitute a relatively larger
fraction of the reaction spectrum and require an individual, more sophisticatedtreatment. When results from such detailed reaction mechanisms are collected
and included in a data file, they form a data source that in quality can never bematched by one single computer code. All the physical models that are utilisedin the LA150 and NRG/BRC libraries are described in [1] and [2] respectively.
Most of the data have been generated with the GNASH and ECIS codes.
Refs. [1,2] contain a large collection of comparisons of the calculated data(which are stored in the file) and the existing experiments. The comparisons
include total and reaction cross-sections, elastic scattering angular distributions,double differential data and residual production cross-section above 20 MeV.
The agreement with experimental data ranges from excellent to very reasonable,
as can be seen from the figures in the aforementioned references.
2.1 LA150 library
Subgroup 14 has been asked to review the LA150 library, and to makerecommendations concerning inclusion of LA150 in ENDF/B-VI. In themeantime, the adoption of LA150 into ENDF/B-VI has taken place. The CSWEG
request came from the Evaluation Committee of ENDF/B-VI, which only
concerns itself with “Phase 1” reviews. This means that the present review does
not involve integral data testing, but rather is concerned with:•

The correct format of the evaluations.

•

Errorless passing of the checking codes.

10•Continuous data varying smoothly with energy, angle, etc.

•

Agreement with existing measurements.

The two principal authors of the LA150 library, M.B. Chadwick and
P.G. Young, have provided Subgroup 14 with the following information:••

Documentation:–

A recent publication in Nuclear Science and Engineering [1],containing extensive comparisons of the model-based data withmeasurements.

–

A collection of summary file-1 documentation and benchmark
figures (some of them three-dimensional) depicting the data in thelibraries [7].

Data in electronic form:–

All the evaluated files of LA150.n and LA150.p.

–

Outputs of the BNL checking codes CHECKR, FIZCON, PSYCHEand STANEF.

–

Various postscript plots depicting the data.

–

Summary files of cross-sections.

The review has been performed by two parties, JAERI (T. Fukahori) and
NRG Petten (A. Koning). Both concluded that LA150 passed the several tests of
the “Phase 1” review and that, with some minor modifications, it could be
adopted. A few of the findings follow below.
2.1.1 Cross-section plots
An extensive collection of figures of total, differential and double
differential data for the LA150 library has been provided in [7]. These figures
clearly reveal the overall smooth behaviour of the data as a function of mass,energy and angle. In general, for incident energies between 20 and 50 MeV, theevaporation peak seems to be very pronounced for some (n,xd) data. In particular,
there are some, maybe anomalous, spikes in the (n,xd) spectra for 30Si, 31P, Ca,
60,62,64Ni, 63Cu (but not in 65Cu) and 93Nb. It is not immediately clear why these11

peaks appear for these nuclei and this particular channel, whereas they are notpresent in the (n,xt) and (n,xα) cross-sections. Similar spikes appear in 28Si(p,xt)
and 29Si(p,xγ). The fact that the magnitude of these cross-sections is relatively
small and that this appears only in a very small energy region means that this iscertainly no reason to reject the data files. Of course, the effect may actually bephysical. Consult [7] for further details.
2.1.2 BNL checking codes
The output files of the checking codes CHECKR, FIZCON and PSYCHE
report several warnings. However these apply almost all at the part below
20 MeV. The only high-energy warning concerns a new feature of the ENDF-6
format, namely the switch from Legendre coefficients to tabular distributions
at 20 MeV. The CHECKR code wants this point to be at exactly 20 MeV.
The LA150 library gives 20.00001 as the first energy point with tabulated data
(and thereby avoids a double point, which seems to be better). Perhaps CHECKR
requires a little change for this. This warning seems to be a minor detail.
Table 1 shows the data files which are known to have been checked this way.
2.2 NRG/CEA library
For this library essentially the same working methods were used as for
LA150. The main difference lies in the use of new optical models throughout
the calculation. The checking procedure described for LA150 is also applied
here. As an example of the contents of the file Figure 1 shows double
differential data for protons on 58Ni.
2.3 JENDL HE library
A comparison of the JENDL HE library with the LA150 and NRG/CEA
libraries has been provided by Lee and Fukahori [10]. The conclusions werethat JENDL HE generally describes the data well up to 50 MeV, but that
improvements in optical models are required for the most basic cross-sections.
Also for some materials (notably iron) the double differential cross-sections of
LA150 and NRG/CEA seem to do somewhat better than the JENDL HE results.
A lot of added value in the JENDL HE library is provided by covering materials
that were not (yet) considered in the 150 MeV libraries.

122.4 Processing
Table 1 shows that most data files have proven to be processable by NJOY
into an MCNP library. In another WPEC document [8], a set of special rules
and recommendations for an evaluated nuclear data file are given, such that theabove processing conditions are obeyed. Recommendations resulting from thatwork are:•Use double-points in the MF3 section of the evaluation for thetransition of the low-energy range (En < 20 MeV) to the high-energy
range (En > 20 MeV).

•

Double-points should not be used in the MF6 section of the evaluation.

•

Use a representation with MT2 (elastic cross-section), MT5 ((n,x)
cross-section), MT18 (fission cross-section) and possibly MT101(neutron disappearance cross-section) in the high-energy region.

•

Use the redundant production cross-sections MT201 to MT207 for theease of the user: It enables the calculation of production rates in MCNP.

•

Specify distributions of reaction products in the MF6 section of theevaluation for MT5.

•

If MT18 is used, the MT456 section in MF1 is required.

If these recommendations are applied, high-energy neutron evaluated nuclear
data files can be produced which can be used without problems in MCNP(X).
3.

Validation on an integral experiment with MCNPX

A number of neutron transmission experiments have been performed [11-13]
at the Azimuthally Varying Field Cyclotron facility (TIARA) at the JAERITakashi site. Incident 43- or 68-MeV protons impinged on converters consistingof 99.9% enriched 7Li. The 7Li(p,n) reaction produced nearly monoenergetic
neutrons, which were then collimated and allowed to strike iron or concretetargets of various thickness. The neutron transmission was measured at several
positions relative to the transmission target. Although the neutrons were initiallyalmost monoenergetic in all cases, their actual spectra were measured in order
to allow for a more realistic comparison with neutron transport calculations.
Details about the experimental arrangement and the geometry can be found in
the aforementioned references.

13

This experiment forms an ideal case to validate some of the intermediate
energy libraries. The iron isotopes of the Los Alamos 150 MeV library havealready been used in an analysis [1] of the 68 MeV experiment. Within SG14,
this analysis has been repeated, as an independent check, and extended to othercases. We confirm the overall excellent agreement between the measurements
and the data (see Figures 2-4) that was already reported in [1]. The alternative
libraries from NRG/BRC (Figures 5-7) give an equally good agreement.
It is obvious from Figures 8-10 that the predictions by LAHET do not havethe quality of those using the data libraries. One reason for the deviation fromthe data is the quality of the elastic scattering model used in LAHET.
This is currently under development.
The main reason that we include this comparison with experiment is that
we use MCNPX, with the geometrical set-up of this experiment, to see whether
the other isotopes of the LA150 library show any undesired irregularities.
This does give a valuable indication of the presence of problems in theevaluations. In Figures 11-14 the neutron flux at centreline behind a 40 cm slabof pure material is shown. The atomic density at room temperature for all theelements are used. The figures demonstrate that, for this simple experiment, thedata files do not exhibit any misbehaviour.
An analysis similar to the one described here has been performed by
Konno, et al. [14-16]. In addition, these authors have performed multi-group
analyses with the LA150 library (see Table 1) using the DORT code and P9
expanded multi-group libraries. The authors claim that LA150 may have someproblems since their MCNP calculations tend to overestimate the neutron flux
above 10 MeV with an increasing thickness of the assembly. This is an important
point for future research. For completeness, we mention that this experiment has
also been used to test some of the other libraries [17,18].
As an alternative manifestation of the impact of the 150 MeV data
evaluations, we present a calculated result from the TIERCE code system [19],which comprises among others HETC and MCNP-4A, with the 150 MeV filefor 58Ni from NRG/CEA. Figure 15 displays the neutron flux resulting from a
200 MeV proton beam incident on a 50 cm long 58Ni-cylinder. Two calculations
were performed: One with HETC and MCNP + 20 MeV data file and one with
MCNP + 150 MeV data file. Besides the expected discontinuity at 20 MeV for
the case with the conventional 20 MeV cut-off, one can observe an overall
difference of up to 40% in the high-energy region.

14

4.

Conclusions

In line with the “Phase 1” review of ENDF/B-VI, we have checked that theLA150 data show a smooth behaviour, where this is expected, by means ofcross-section plots. The comparison of the contents of the data files withexperimental data reveals that the data files seem to be superior to anything else
existing at the moment (e.g. the intranuclear cascade codes), at least consistently
over such a large range of mass, energy and reaction channels. The checking
codes do not complain about the contents of the files above 20 MeV, and thefiles can be processed by NJOY into MCNP libraries.
The quality of several of the libraries is tightly connected with the qualityof the nuclear model codes GNASH and ALICE, which are known to performbetter or at least as good as its competitors [6]. In other words, they are relatively
safe tools when so little experimental data is available as in the intermediate
energy region. It should however be mentioned, and the authors of the various
libraries are aware of that, that a lot can still be gained by improving nuclear
models, of which the optical model, level density and pre-equilibrium models
seem to be the most crucial. To this end, a new WPEC subgroup on nuclear
model codes will be formed. Hence, the present intermediate energy libraries
represent a challenge to other methods that claim to do even better in the future.
Within SG14, the LA150 and NRG/BRC data files have been tested, withthe transport code MCNPX, against an iron benchmark experiment. A similarvalidation has been simultaneously performed by others. For nuclear applications
with nucleon energies below 150 MeV, the calculations with neutron data files
suggest a drastic improvement of the description of macroscopic experiments,
when compared with the intranuclear cascade code LAHET. This confirms thefindings that were reported in [1]. For this simple benchmark experiment, there
seems to be no clear quality argument in favour of either the LA150 or the
NRG/BRC neutron data files for iron. Some discontinuities can still be observedat energies around 20 MeV, although they are no longer as large as in the
LAHET + 20 MeV data file calculations. This suggests that for a continuous
description the data below and above 20 MeV should preferably be re-evaluatedin one and the same working process. Also, the findings by Konno, et al.
mentioned in the previous section need to be taken into account. Finally, we
have checked that the other materials present in the LA150 data library show no
strange irregularities that result from the extension to 150 MeV. For several ofthe data files of Table 1 this still needs to be done. The conclusion of SG14 is,however, that there should in principle be no problem to achieve this, provided
the format procedures of the LA150 and NRG/BRC libraries are followed.

15

REFERENCES[1]

M.B. Chadwick, P.G. Young, S. Chiba, S.C. Frankle, G.M. Hale,G. Hughes, A.J. Koning, R.C. Little, R.E. MacFarlane, R.E. Prael and
L.S. Waters, “Cross-Section Evaluations to 150 MeV for AcceleratorDriven Systems and Implementation in MCNPX”, Nucl. Sci. Eng. 131(1999), 293.

[2]

A.J. Koning, J.-P. Delaroche and O. Bersillon, “Nuclear Data for
Accelerator-Driven Systems: Nuclear Models, Experiments and Data
Libraries”, Nucl. Instr. and Methods, A414, 49 (1998).

[3]

T. Fukahori, “Status of JENDL High-Energy File for IFMIF”, JAERI-Conf
96-008, p. 56 (1996).

[4]

U. Fischer,“High-Energy Neutron Cross-Section Data for the IFMIF
Neutron Source”, NEA Data Bank JEFF/DOC (1997), unpublished.

[5]

W. Gudowski, et al., “Impact of Accelerator Based Technologies on
Nuclear Fission Safety: IABAT Project”, EU final report, to be published(2000).

[6]

Proceedings of the NEA Specialists Meeting on Intermediate Energy
Nuclear Data: Models and Codes, 30 May-1 June 1994, Nuclear Energy
Agency, Issy-les-Moulineaux, France.

[7]

M.B. Chadwick, P.G. Young and P. Moller, “LA150 Library ENDF
Neutron Cross-Section Benchmarks”, and “LA150 Library ENDF Proton
Cross-Section Benchmarks”, Los Alamos National Laboratory, unpublished(1998).

[8]

A.J. Koning and A. Hogenbirk, “High-Energy Nuclear Data Files: From
ENDF-6 to NJOY to MCNP”, Nuclear Energy Agency Data Bank Report
NEA/NSC/DOC(97)8.

[9]

S.V. Fortsch, et al., Phys. Rev., C43 (1991), 691.

17

[10] Y.-O.Lee and T. Fukahori, “Intercomparison of High-Energy Files(Neutron Induced from 20 to 150 MeV)”, JAERI-Conf 98-016, p. 97(1998).
[11] Y. Nakashima, et al., Nuc. Sci. Eng. 124, 243 (1996).
[12] Y. Nakane, et al., “Neutron Transmission Benchmark Problems for Iron
and Concrete Shields in Low, Intermediate and High-Energy Proton
Accelerator Facilities”, JAERI report JAERI-Data/Code 96-029 (1996).
[13] Y. Nakane, et al., “Intercomparison of Neutron Transmission Benchmark
Analyses for Iron and Concrete Shields in Low, Intermediate andHigh-Energy Proton Accelerator Facilities”, Proc. of the Workshop on
Shielding Aspects of Accelerators, Targets and Irradiation Facilities(SATIF-3), NEA Data Bank (1996).
[14] C. Konno, et al.,“Analyses of the TIARA Experiments Using the LA150
Cross-Section Data Library”, JEF/DOC-808 (1999).
[15] C. Konno, et al. ,“DORT Analysis of Iron and Concrete Shielding
Experiments at JAERI/TIARA”, JAERI conference, JAERI-99-002,
p. 164 (1999).
[16] C. Konno, et al. ,“Analysis of Iron and Concrete Shielding Experiments
for 43 and 68 MeV p-Li7 neutrons with LA150”, ICRS-9 proceedings(1999).
[17] U. Fischer, “First Results of Benchmark Calculations for Intermediate
Energy 56Fe Cross-Section Data”, NEA Data Bank JEF/DOC-721 (1997),
unpublished.
[18] F. Maekawa and M. Wada, “Results of Benchmark Test with MCNP
Code”, JAERI-Conf 98-016, p. 66 (1998).
[19] O. Bersillon, et al., “TIERCE: A Code System for Particles and Radiation
Transport in Thick Targets”, Proceedings of International Conference on
Nuclear Data for Science and Technology, 19-24 May 1997, Trieste, Italy(1997), 257.

18

TABLES

19

Table 1. Intermediate energy data files, May 2000
Nuclide Library1
H
ENDF/B-VI
JENDL HE2
H
ENDF/B-VIC
ENDF/B-VI
12C
JENDL HE14
N ENDF/B-VI
16
O ENDF/B-VI
23

Na

24

Mg
25
Mg
26
Mg
27
Al
28

Si

29

Si

30

Si

31

P
Cl
37
Cl
39
K
35

41

K
Ca
40
Ca
42
Ca
43
Ca
44
Ca
46
Ca
48
Ca
46
Ti
47
Ti
48
Ti
49
Ti
50
Ti

JENDL HEJENDL HEJENDL HEJENDL HE
ENDF/B-VI
JENDL HE
ENDF/B-VI
JENDL HE
ENDF/B-VI
JENDL HE
ENDF/B-VI
JENDL HE
ENDF/B-VI
JENDL HEJENDL HEJENDL HEJENDL HE
ENDF/B-VI
JENDL HEJENDL HEJENDL HEJENDL HEJENDL HEJENDL HEJENDL HEJENDL HEJENDL HEJENDL HEJENDL HE

Origin
LANL
JAERI
LANL
LANL
IPPE/FZK
JAERI
LANL
LANL
IPPE/FZKIPPE/FZK
JAERI
JAERI
JAERI
JAERI
LANL
JAERI
LANL
IPPE/FZK
JAERI
LANL
JAERI
LANL
JAERI
LANL
JAERI
JAERI
IPPE/FZK
JAERI
JAERI
LANL
JAERI
JAERI
JAERI
JAERI
JAERI
JAERI
JAERI
JAERI
JAERI
JAERI
JAERI

Particle Energy Checked MCNP Multi-groupp,n
150 MeV
yes
yes
yes
n
050 MeVp,n
150 MeVyes
yesp,n
150 MeVyes
yesn050 MeVyesn050 MeVp,n
150 MeVyes
yesp,n
150 MeV
yes
yes
yes
n
050 MeVyesn050 MeVyesn050 MeVn050 MeVyesn050 MeVyesn050 MeVyesp,n
150 MeV
yes
yes
yes
n
050 MeVyesp,n
150 MeV
yes
yes
yes
n
050 MeVyesn050 MeVyesp,n
150 MeV
yes
yes
yes
n
050 MeVyesp,n
150 MeV
yes
yes
yes
n
050 MeVyesp,n
150 MeVyes
yesn050 MeVn050 MeVn050 MeVyesn050 MeVyesn050 MeVyesp,n
150 MeV
yes
yes
yes
n
050 MeVyesn050 MeVyesn050 MeVyesn050 MeVyesn050 MeVyesn050 MeVyesn050 MeVyesn050 MeVyesn050 MeVyesn050 MeVyesn050 MeVyes

Yes. The action has been successfully performed.
No. The action has not been successfully performed.
Blank. It is not known whether the action has taken place.

21

Table 1. Intermediate energy data files, May 2000 (cont.)
Nuclide Library
OriginParticle Energy Checked MCNP Multi-group
50
V
JENDL HEJAERIn050 MeVyes
51
V
IPPE/FZKn050 MeVyes
JENDL HEJAERIn050 MeVyes
50
Cr ENDF/B-VI LANL/JAERI p,n
150 MeVyes
yes
JENDL HEJAERIn050 MeVyes
52
Cr ENDF/B-VI LANL/JAERI p,n
150 MeVyes
yes
IPPE/FZKn050 MeVyes
JENDL HEJAERIn050 MeV53
Cr ENDF/B-VI LANL/JAERI p,n
150 MeVyes
yes
JENDL HEJAERIn050 MeV54
Cr ENDF/B-VI LANL/JAERI p,n
150 MeVyes
yes
JENDL HEJAERIn050 MeV55
Mn JENDL HE
JAERIn050 MeV54
Fe ENDF/B-VI LANL/NRG
p,n150 MeVyes
yesyes
NRG/CEA
p,n
150 MeVyes
yes
JENDL HEJAERIn050 MeVyes
56
Fe ENDF/B-VI LANL/NRG
p,n150 MeVyes
yesyes
NRG/CEA
p,n
150 MeVyes
yes
IPPE/FZKn050 MeVyes
JENDL HEJAERIn050 MeVyes
57
Fe ENDF/B-VI LANL/NRG
p,n150 MeVyes
yes
yes
JENDL HEJAERIn050 MeVyes
58
Fe ENDF/B-VI LANL/NRG
p,n150 MeVyes
yes
yes
JENDL HEJAERIn050 MeVyes
58
Ni ENDF/B-VI LANL/JAERI p,n
150 MeVyes
yes
NRG/CEA
p,n
150 MeVyes
yes
JENDL HEJAERIn050 MeVyes
60
Ni ENDF/B-VI LANL/JAERI p,n
150 MeVyes
yes
NRG/CEA
p,n
150 MeVyes
yes
JENDL HEJAERIn050 MeVyes
61
Ni ENDF/B-VI LANL/JAERI p,n
150 MeVyes
yes
JENDL HEJAERIn050 MeVyes
62
Ni ENDF/B-VI LANL/JAERI p,n
150 MeVyes
yes
JENDL HEJAERIn050 MeVyes
64
Ni ENDF/B-VI LANL/JAERI p,n
150 MeVyes
yes
JENDL HEJAERIn050 MeVyes
63
Cu ENDF/B-VI LANL/NRG
p,n150 MeVyes
yes
JENDL HEJAERIn050 MeVyes
65
Cu ENDF/B-VI LANL/NRG
p,n150 MeVyes
yes
JENDL HEJAERIn050 MeVyes
89
Y
JENDL HEJAERIn050 MeVYes. The action has been successfully performed.
No. The action has not been successfully performed.
Blank. It is not known whether the action has taken place.

22

Table 1. Intermediate energy data files, May 2000 (cont.)
Nuclide Library
OriginParticle Energy Checked MCNP Multi-group
90
Zr JENDL HE
JAERIn050 MeV91
Zr JENDL HE
JAERIn050 MeV92
Zr JENDL HE
JAERIn050 MeV94
Zr JENDL HE
JAERIn050 MeV96
Zr JENDL HE
JAERIn050 MeV93
Nb ENDF/B-VI
LANLp,n
150 MeVyes
yes
JENDL HEJAERIn050 MeV92
Mo JENDL HE
JAERIn050 MeV94
Mo JENDL HE
JAERIn050 MeV95
Mo JENDL HE
JAERIn050 MeV96
Mo JENDL HE
JAERIn050 MeV97
Mo JENDL HE
JAERIn050 MeV98
Mo JENDL HE
JAERIn050 MeV100
Mo JENDL HE
JAERIn050 MeV180
W JENDL HE
JAERIn050 MeV182
W ENDF/B-VI
LANLp,n
150 MeVyes
yes
JENDL HEJAERIn050 MeV183
W ENDF/B-VI
LANLp,n
150 MeVyes
yes
JENDL HEJAERIn050 MeV184
W ENDF/B-VI
LANLp,n
150 MeVyes
yes
JENDL HEJAERIn050 MeV186
W ENDF/B-VI
LANLp,n
150 MeVyes
yes
JENDL HEJAERIn050 MeV196
Hg ENDF/B-VI LANL/JAERI p,n
150 MeVyes
yes
198
Hg ENDF/B-VI LANL/JAERI p,n
150 MeVyes
yes200
Hg ENDF/B-VI LANL/JAERI p,n
150 MeVyes
yes201
Hg ENDF/B-VI LANL/JAERI p,n
150 MeVyes
yes202
Hg ENDF/B-VI LANL/JAERI p,n
150 MeVyes
yes204
Hg ENDF/B-VI LANL/JAERI p,n
150 MeVyes
yes206
Pb ENDF/B-VI LANL/NRG
p,n150 MeVyes
yes207
Pb ENDF/B-VI LANL/NRG
p,n150 MeVyes
yes
208
Pb ENDF/B-VI LANL/NRG
p,n150 MeVyes
yes
209
Bi ENDF/B-VI
LANLp,n
150 MeV
232
Th
IPPE
p,n
150 MeV
no
yes
238
U
IPPE
p,n
150 MeVyes
Yes. The action has been successfully performed.
No. The action has not been successfully performed.
Blank. It is not known whether the action has taken place.

23

FIGURES

25

Figure 1. (p,xp) on 58Ni: Comparison between NRG/CEA data fileand experimental data [9] for incident energies of (a) 150 MeV(b) 120 MeV, (c) 100 MeV at several outgoing energies

27

Figure 2. 68 MeV neutrons on 40 cm of iron, detector at centreline
Comparison between experimental data and MCNPX + LA150 data libraries

Figure 3. 68 MeV neutrons on 40 cm of iron, detector at 20 cm
Comparison between experimental data and MCNPX + LA150 data libraries

28

Figure 4. 68 MeV neutrons on 40 cm of iron, detector at 40 cm
Comparison between experimental data and MCNPX + LA150 data libraries

Figure 5. 68 MeV neutrons on 40 cm of iron, detector at centreline
Comparison between experimental data and MCNPX + ECN/BRC data libraries

29

Figure 6. 68 MeV neutrons on 40 cm of iron, detector at 20 cm
Comparison between experimental data and MCNPX + ECN/BRC data libraries

Figure 7. 68 MeV neutrons on 40 cm of iron, detector at 40 cm
Comparison between experimental data and MCNPX + ECN/BRC data libraries

30

Figure 8. 68 MeV neutrons on 40 cm of iron, detector at centreline
Comparison between experimental data and MCNPX + LAHET above 20 MeV

Figure 9. 68 MeV neutrons on 40 cm of iron, detector at 20 cm
Comparison between experimental data and MCNPX + LAHET above 20 MeV

31

Figure 10. 68 MeV neutrons on 40 cm of iron, detector at 40 cm
Comparison between experimental data and MCNPX + LAHET above 20 MeV

Figure 11. 68 MeV neutrons on 40 cm of carbon,
nitrogen and oxygen, detector at centreline
Calculated result of MCNPX + LA150 data libraries

32

Figure 12. 68 MeV neutrons on 40 cm ofaluminium, silicon and calcium, detector at centreline
Calculated result of MCNPX + LA150 data libraries

Figure 13. 68 MeV neutrons on 40 cm ofchromium, iron and nickel, detector at centreline
Calculated result of MCNPX + LA150 data libraries

33

Figure 14. 68 MeV neutrons on 40 cm oftungsten and lead, detector at centreline
Calculated result of MCNPX + LA150 data libraries

Figure 15. HETC-MCNP4A calculation for 200 MeV protons incident
on a 58Ni cylinder with the neutron data file cut-off at 20 vs. 150 MeV
The cylinder is 50 cm long and has a radius of 20 cm.
The mean neutron flux is calculated between 10 and 20 cm.

34