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LA-6260-MSInformal Report
C3b
I
ClC-l 4 REPORT COLLECTION
REPRODUCTIONCOPY
UC-34C and UC-80
Reporting Date: February 1976
Issued: March 1976
LIB-IV, A Library of Group Constants for
Nuclear Reactor Calculations
by
R. B. Kidman
R. E. MacFarlane
(i?:10s alamosscientific laboratory
of the University of CaliforniaLOS ALAMOS, NEW MEXICO 87545
l\
An Affirmative Action /Equol Opportunity Employer
UNITED STATES
ENERGY REsEARCH AND DEVELOPMENT ADMINISTRATION
CONTRACT W-740 S-ENG. 36
In the interest of prompt distribution, this report was not edited bythe Technical Information staff.
‘Ilk work was supported by the US Energy Research and DevelopmentAdministration, Division of Reactor Development and Demonstration.
PrintedintheUnitedStatenofAmerica.AvailablefromNationafTechnicafInfonnatianService
U S DepartmentofCommerce528SPortRoyalRaadSpringfield,VA 22151
Price:PrintedCOPY$4.MMicrofiche$2.25
This rqwrt was pm .rrd .s . . ●mount of work sponsoredb, the United States L vmntnettl. Neither the United St.tesnor the United 9tmt” Emmy Ike.rch and Drvelqnnent Ad.ministration. nor ●ny d their .IIVI1.ayr.u. nor any of their con-tr.clors, s.bco.tr.ctors, or Ihelr ●mplqees. m.k” .myw.rm.~v, expr”. or implied, or .. SUIIWSany legal liability orrnmn~t~lily for the •car~c~. completeness, or usefulness of●m. information. .pII.r.Iuc. prcd. et. o, process dhcl.scd. orrrprc.rnb tlut its use would not intringe privately ownedrichb.
CONTENTS
I. INTRODUCTION ................................ 1
II. MATERIALS AND SPECIFICATIONS ................ 1
III . LIBRARY FORMAT .............................. 4
IV. PROCESSING METHOIKS.......................... 5
v. CRITICAL ASSEMBLY CALCULATIONS .............. 7
APPENDIX A: SAMTLEDALA. ............ .............. 9ISOTXS ...................................... 9BRKOXS ...................................... 16DLAYXS ...................................... 20
APPENDIX B: OPERATING INSTRUCTIONS FOR THEUTILITY CODES LINX, BINX, AND JINX .......... 22
REFERENCES ........................................ 23
?’”’k ----
—
1
iii
LIB-IV
A LIBRARYOF GROUPCONSTANTSFOR NUCLEARRSACTORCALCULATIONS
by
R. B. Kidman and R. E. MacFarlane
ABSTRACT
A 50-group, I@L-isotope library of multigroup constants fornuclear reactor design is described. Nuclear cross sections, self-shielding factors, transfer matrices, and delayed neutron data weregenerated with MINX and NJOY using evaluated data from ENDF/B-lV.The output is in the CCCC-111 interface format. Test results arepresented for six CSEWG benchmark critical assemblies.
I. INTRODUCTION
The purpose of this report is to docu-
ment LIB-IV, a rather complete and tested
multigroup library based on the latest ver-
sion of the Evaluated Nuclear Data Files 1
(ENllF/B-IV)and generated using the MINX2
nuclear cross–section processing code. This
library is being issued in the CCCC-111 in-
terface format3’4 and is intended for use
by the nuclear community for fast–reactor
design calculations.
The ENDF/B-IV data files are the latest
result of a continuing major effort to com-
pile, evaluate, test, and update a computer-
readable repository of basic nuclear data.
Because of the scope of this effort and the
intensive testing of the data, these files
are rapidly becoming the authoritative
source of data for the preparation of multi-
group constants. The MINX (E<igroup ~n-
terpretation of Nuclear Cross Sections)
code is a new advanced computer program for
processing ENDF/B data. It is a designer-
oriented code producing pseudo-composition-
independent libraries of group cross sec-
tions, self-shielding factors, and group-
to-group transfer matrices in the CCCC in-
terface format. The Committee for Computer
Code Coordination (CCCC) interface system
is part. of an ambitious attempt by the Di-
vision of Reactor Research and Development
(DRRD) of the United States Energy Research
and Development Administration (ERDA) to fa-
cilitate the exchange of codes and data for
reactor design among the laboratories and
companies involved in the DRRD program.
LIB-IV contains three CCCC-111 files: ISOTXS
(isotope constants, cross sections, and ma-
trices), BRKOXS (self-shielding factors),
and DLAYXS (delayed neutron yields and spec-*
tra by time group).
The detailed specifications for the li-
brary, the processing methods, and the test-
ing performed will be discussed in the fol-
lowing sections.
11. MATERIALS AND SPECIFICATIONS
Table I shows the 101 materials compris-
ing LIB-IV. Also shown are the ENDF/B-IV
material source numbers, MINX CDC-7600 tim-
ing, and the o0
table values. All materials
*Delayed neutron constants were generatedfrom ENDF/B-IV using NJOY.5
1
TABLE I
LIB-IV MATERIALS
123
:6789
10It1?131415!61718192142122’2324252b2728293031323334353b373839U@41424344454(14748lJ95ti515?5354555b5758596P61b?6364
14AT ERIAI
1+- 1H-2H-3HE-3HE-4LI-6LI-7BF-9B-lm8-11c-t2N-1o0-16FNA-23MGAL-27STc1KCA11vCRtlN-55FEcn-5QN ICuC[J-63CU-65KR-78KR-flklKR-R2KQ-8ZKf?-f34KU-86ZTUC-i!hil-Q3M(lTC-99l?H-lti3AC-IM7AG-l&?19CDCO-113XE-1?4XE- 126xE-li?7XE-l?I?XF-130XF-131XE-132XE-13UXE-1 \SXE-136CS-133SM-149Eu-l\lLU-1’52EU-153EU-15dSDII Y-16U
ENDFIBMATNO.
1269112011691146ll?7~1271127212t591273lleo12741275127612771!5612Rk71193119U114911501195I?fib11961191119711921!9Q11901295lfi85lP&611811181?1183llUU118511861284llIIQ1?87113711251158115912811282l17Gl11711172117311741175117611771?9U1178llU1lf127l?9~129212911293133GIln31
MINXTIMING(SEC)
13395
\ h510?1181571595164281821’3659359m38466758Q6S15464383685422183UU
16417t45
1075910
12517L17U51365162j 7fl
17619?
217163
12732975
532325
.211E3698793f159
6ti5177146367
llh5?9n751.?1’314315(1128
1472a(>49b’lm7137ti5585378?13
1
656tI6768697(37172737475Th
7778798fi818283flu85Rhf1788899Fl91Q?939495969798~9
1001( ’31
MAicPIAL
LU-175LU-1761A-181IA-t82II-18.?N-183N-180bu-lf36RF-185RF-187AU-197P13iH-?32PA-233U-233U-234U-235U-236U-238NP-237PiJ-238plJ-~3QPU-I?4UPU-.241Pu-24i?~tA-24j11~-243CIA-24LJFP~33NFpt?33SF~’?33RFP235NFP231jsFP23’52FF239NFP239S~p23qR
TABLE I (cent)
were run for 3 temperatures, 300, 900,
!41!NJATit-iING(>Ec)
354389
1 09.?252
~lA231353135?1(IR9ti7BUIR168564138’i’a/162‘i31672
ZR32lllm
bu!ju2tA85\@4335U5bl!;
5UU664
54P
?31~f457
839893849395859491
79/J55
and
2100° K. 63CU, 65Cu, and the 9 lumped fis-
sion–product isotopes were obtained from
ENDF/B-111 in order to provide a library
complete enough to allow full Cross Sec-
tion Evaluation Working Group (CSEWG) bench-
mark testing and reactor burnup calculations
The names of the 9 lumped fission pro-
ducts can be interpreted in the following
manner: FP233N refers to the lumped, non-
saturating,233
U fission products; “s”
would stand for slowly saturating; and “R”
would stand for rapidly saturating.
Delayed neutron yields and spectra for
6 time groups are inc~ded for ~~ following
7 isotopes: 232Th, U, 235U, U, 23%>
240Pu, and 241PU . These are all of the
ENDF/B-IV materials that have delayed neu-
tron data.
Table II shows the 50-group energy
structure used in LIB-IV. This structure
is a subset of the 240-group structure,6
and the widely used 26-group half-lethargy
structure is a subset of the LIB-IV struc-
ture.
The library was generated using a
“thermal + l/E + fission” weight function.
The thermal portion is Maxwellian with a
temperature of 0.025 eV which joins l/E at
0.10 eV. The fission spectrum joins l/E at
820.8 keV (lower boundary of group 6) and
has a characteristic temperature of 1.40 MeV.
btil)uP
0102U30405U6lJ7iJ8U9101112131415
:;ld1921.I212’2.?3Z425L6272U29do31323334353637JtlJ9404142
43444546
474849so
‘TABLE II
LIB-IV GROUP STRUCTURE
ENERbY RANGE (EV)
1.’3ooOE+O71.U(JOOE+076.u653E*063.6788E+06202313E+061.J534E+068.Z085E*054.9787k+053.8774E+053.u197E+052.J518E*J51.8316E*0510*264E+O5l.llO~E*OS9.6517E*046.i379L*L)45.L475E+u144.oti6dE+043.1c428E+1342.4788E*041.YJ05E*1341.5034E+L)41.1709E+U49.118ME*037.I’317E+035.5J08E+034.3074E+033.J>46E*U32.b126E+03200347E+03105H46E+O31.z341E+u39.611c’E+027.4652E*025.8Z95E*024.54UOE+023.5358E+022.”153bE+021.b70t?E+021.U13tIE+02b.i44ZE*Ol3.7267E+012.~603E*Ol
1.371OE+O18.J153E*o05.0435E+O03.u590E+O01005S4E+OO1.1?54E+O06.d256E-LIl
‘he ‘o’ ‘1’ ‘2’and p3 Legendre com-
ponents of the matrices were generated when-
ever
used
lows
izat:
0.2%
cept
the ENDF/B data permitted. Tolerances
in running the MINX code were as fol-
resonance reconstruction 0.5%, linear-
on 0.2%, thinning (resol~ed range only)
and adaptive integration 0.1% (ex-
that 238U, 103Rh, and 133CS used a re-
construction tolerance of 1.0%).
4
1.UOOUL+OI6.06bJE*ob3.6788L*Ot.2e2313E+Ob1.3534ii*ob8.20&5~+O>4.9787L*033.t!774~+03
3.0197L*O>2.3518L+O01.8316L+O>1.4264t-*Ob1.1109L*OJ8.fJ517i+046.7379i+u+5.2475L+044.0868E*O+
3.181?8L+642.4768~+041.9305fi+041.5034E+041.1709L*049.1188L*OJ7*1OA7L*OJ5.5308:+0s4.3074:+03
3.3546&+OJ2.6126L+LIJ2.0347L*OJ1.584bk*oJ1.2341E+oJ9.6112t*OZ
7.4852i.~oz5.8295L+OL4.5400L*OL3.5358E*l)L2.7536k+od1.6702;+0<1.0130L*OZ6.1442i+Ol3.7267:*O12.2603E+011.3710~:ol8.3153L*OU5.0435~*ou3*0590L*OU
1.8554L+OU1.1254L*OU6.8256L-01l.uoooE-ob
Lt.THARGy
0.6920.5O.!J0.5O.!J0.50.5O*Z50.250.250.250.250.250.250.25().Z50.25
0.256.250.2!50.250.25
0.250.250.250.250.250.250.250.250.250.250.250.250.250.250.250.50.5U.50.50.50.50.50.50.50.500>
6.511.31
III. LIBRARY FORMAT
The user of LIB-IV should be familiar
with the format for the ISOTXS, BRKOXS, and
DLAYXS files as described in Ref. 4. The
amount of data in LIB-IV is so large that it
is impractical to try and list it in this
document. Therefore, an abbreviated listing
featuring group constants for239Pu has been
constructed to familiarize the reader with
the kinds of data provided and the format
of that data (see Appendix A). Note that
scattering matrices have been sub-blocked.
There is a record for each sink group con-
taining elements from all source groups and
all Legendre orders. Section IV describes
the processing methods used to obtain the
data in these files.
Certain manipulations may be required
to update, transmit, or use CCCC data.
Therefore, three utility codes are provided
as described below.
CINX -- will exactly collapse fine-
group data (ISOTXS, BRKOXS, AND DLAYXS) to
a subset coarse-group structure, and will
also change the format of the data to lDX/
PERT-V7> 8 form, if desired.
LINX -- will combine two multi-isotope
CCCC files (ISOTXS or BRKOXS only) into a
new composite file in CCCC format.
BINX -- will convert CCCC data (ISOTXS,
BRKOXS, or DLAYXS) from binary to BCD mode
or vice versa and selectively print the
contents of the files.
These codes are completely described else-
where. 9,10 For the convenience of the user,
operating instructions for LINX, BINX, and
CINX, have been included as Appendix B of
this report.
LIB-IV is issued on two 7–track BCD
tapes recorded at 800 bits per inch. Data
are blocked into records containing 50 card
images of 80 columns each, The last block
(record) in each file may be short. The
tapes contain six files as shown in Table
III.
Iv. PROCESSING METHODS
LIB-IV features cross sections for use
in the Self-Shielding Factor Method, 11,12
sometimes called the Bondarenko Method. In
the region of a resonance, the neutron flux
will be depressed, thereby causing a reduc-
tion in the contribution of that resonance
to the reaction rate, i.e. , self-shielding.
The magnitude of the self-shielding depends
on the temperature, composition, and geome-
trY of the problem in a complex way, but for
STRUCTURE OF
Filem_1 1
234
2 56
TABLE 111
LIB-IV TRAPJSMITTAL TAPE
Contents No. of Cards
LINX 460BINX 872CINX 857ISCTXS 192 273
BRKOXS 80 083DLAYXS 735
Total 275 280
many problems of practical interest, accu-
rate reaction rates can be computed using
average cross sections defined by
~ U;(E)T)@:(E,T, uo)dEu&(T,uo) =
.r
(1)
g$:(E,T,uo)dE
where the weight functions for material i
are given by
L&E,T,uo) = C(E)
[ 1UO+U;(E,T)1+1 “
(2)
In these formulas, t = O refers to flux
weighting, L = 1 refers to current weight-
ing, E is the neutron energy, T is the tem-
perature, g is the group index, C(E) is the
slowly varying component of the weight func-
tion (as described in Sec. II), and u~(E,T)
is the microscopic total cross section for
this material. The “background cross sec-
tion per atom” 00 is regarded as a parame-
ter by which composition and geometry ef-
fects can be introduced (see Ref. 12).
The flux of Eq. (2) is based on the
narrow resonance approximation, the B. ap-
proximation for small B, and the assumption
that the positions of resonances in differ-
ent isotopes are not correlated. Therefore,
the multigroup constants in LIB-IV are best
suited for large critical systems contain-
ing some light isotopes. The data can be
used in other applications with due regard
to the approximations used. 13
5
LIB-IV contains “infinite dilution”
cross sections at O“ K u~Lg(o,m) evaluatedby Eq. (l). Temperature and Go dependent
cross sections are to be obtained by in-
terpolating in tables of “f-factors”
.:, (T,uO)~kg(T,uo) = i ‘(o. ~ “fi (3)
ax!tg ‘m
The “total” f-factor in the BRKOXS file is
The special quantities ~ (average scat-
tering cosine), F (average log decrement),
and D (average fission yield) are reaction-
rate averaged at T = O and U. = CU. For ex-
ample,
ii=.8
i ~(E)uf(E)C(E)dE
Jguf(E)C(E)dE
(4)
This formula preserves the fission neutron
production rate. Similar formulas apply
for ~ and Fusing ue(E). The transport
cross section and transport f-factors are
computed csing
i ‘iui (T,uo) ,Utr g(TJJo) = U;lg(T>Uo)-Pg eog,
(5)
where Ue is the elastic scattering cross
section. The potential scattering cross
section given is based on the actual E-de-
pendent up used by MINX during resonance re-
construction and may not be meaningful out-
side the resonance range.
Accurate, high-order, group-to-group,
transfer cross sections are computed for all
reactions (at infinite dilution only) using
u=XL; g+g‘
JgC(E)dE
where g is the initial energy group, g’ is
the final energy group, m: is the neutron
multiplicity, and F~2(E+E’) is a Legendre
component of the probability of scattering
from E to E’. The only reaction for which
significant self-shielding is expected is
elastic scattering; all elements are assum-
ed to have the same f-factor as the elastic
cross section.* MINX produces matrices for
all neutron scattering reactions given in
ENDF/B, and all are added into the total ma-
trix in the ISOTXS file. The “inelastic”
matrix is the sum of all scattering reac-
tions except elastic and (n,2n). The (n,2n)
matrix in ISOTXS has been normalized for a
neutron yield of one.
The elastic cross section was obtained
by summing all final energy groups of the
elastic matrix, and the elastic removal
cross section was computed with
z iU;g = ueO;g+g’ “
g’#g
(7)
The inelastic cross section is the sum over
all reactions and all final energy groups
in the inelastic matrix with the (n,3n) con-
tribution divided by three. Finally, the
(n,2n) cross section was obtained by sum-
ming the (n,2n) matrix,
LIB-IV does not provide a fission chi
matrix. The correct definition for the i-
sotope chi vector is
$ =
J~dE ,dE’vi(E)u;(E)gi(E+E’)C(E)
J
, (8)
dEvi(E)a:(E)C(E)
However, if the distribution of fission neu-
tron secondary energies g~(E+E’) is a S1OW1Y
varying function of E over the range of in-
terest,
(6)
‘This approximation is explicit in the or-iginal methodll and codes using it,7 bu
!4maY not be,justified for some problems.
6
Jx;,==~,dE’g~(E*+E’) , (9)
where E~~is some well-chosen energy; MINX
uses E* = 1.0 MeV and processes the distri-
bution from MT18 only. These two approxi-
mations are appropriate for reactor prob-
lems, but they will be less adequate for a
fusion problem.
Values quoted for the average energy
released in fission (EFISS) were inferred
from data for four of the isotopes. 15 The
energy released through neutron capture
(ECAPT) was obtained by adding the reaction
Q-values16 to the energy released by decay
to a stable isotope computed from the Table17
of Isotopes.
v. CRITICAL ASSEMBLY CALCULATIONS
This library has been used in the cal-
culation of several CSEWG benchmark criti-
cals to provide a comparison with results
from other labs and codes and to give an
indication of how the library may perform
in reactor design calculations.
The calculational procedure is shown
in Fig. 1. All benchmark specifications
came from Ref. 18, all DTF19 runs used S16,
and the two fission source vectors used for
Pu- and U-fueled assemblies are shown in
Table IV. The keff results are shown in
Table V and the central reaction rate ra-
tios are shown in Table VT..
In general, only in a few cases do the
current LIB-IV results increase the spread20
in integral results already established
by other codes and libraries. One is en-
couraged by such agreement, and the lack of
any obvious anomalies further increases
one’s confidence in LIB-IV.
Since MINX is very similar to ETOX,21
one can easily extrapolate from past com-
parisons and validations12,22,23 of ~TOx
and the Shielding Factor Method, and state
that LIB-IV offers a simple, reliable, ac-
curate, fast, and directly interpretable
scheme for processing nuclear data for re-
actor calculations.
eCIIIXPUTLIEPdRY INTO IOX FOFWAT
tlox
COMPUTE EFFECTIVZ X-SEC MO INTZGFAL PARAMETERs
I
OTF
CONPUTE INTIGRAL Pm~TEp~
)(
o~
‘eff Cf tCTRAl REACT [ON RATIOS
Fig. 1. Calculational procedure.
TABLE IV
FISSION SOURCE VECTORS
QxL!Llz
1?-3456789
10
111?1314
151617Ill19
20212223242526
Chi forPu-Fueled
2.6650000E-033.2393000E-f)21.2144500E-01201O381OOE-O120i?236700E-01I07232300E-01101017300F-nl306035000F-022.6550000F-02109263OOOE-O2103B1OOOOF-O29*EI090000C-03609160000F-034.8490000F-03303850000E-032*3550000E-031.6340000E-031.131OOOOE-O37e8200000E-045.4000000E-1)43.7200000E-042c5700000E-041.7700000E-041.2200000E-048e4000000E-055.8000000E-05
Chi forU-Fueled
ls9R20000E-f13?.7500000E-021.1?17400E-01?o0520400E-012.?451600E-011.7777600E-011.1517800E-013.7930000E-02?.13033000E-022.0388000E-02104644OOOE-O21.0416000E-027.3530000E-03501600000E-033.6050000E-032.5090000E-031.741OOOOE-O31.2060000E-03803400000E-04507600000E-04309700000E-042e7400000E-041.8900000E-041.3000000E-04R09000000E-056.1OOOOOOE-O5
TABLE IV (cent)
Group
272R2930313?3334353637383940414?43444546474R4950
Chi forPu-Fueled
4.0000OOOF-05207000000E-051.9000000F-05103000000E-05900000000F-06600000000E-064eOOOOOOOE-063*oooooooF-f)62.0000OOOE-061.0000OOOF-061.0000OOOE-061.0000OOOE-06n.00o*0.o*0.0.0.0.000.0.
Chi forU-Fueled
4.2000000E-052.9000000E-052.0000000F-051.4of30000F-05900000000E-066.0000OOOE-064.0000000E-063.0000OOOE-062.0000000E-061.0000OOOE-061.0000OOOE-061.0000OOOE-061OOOOOOOOE-O6o.0.090.00000.0.000.0.
CODES UNCORRECTEDBENCHMARK USED KEFF
Pu-Fueleda
JEZEBEL lDX-DTF 1.00089VERA-11A lDX-DTF 0.99235zPR-6-7 lDX-DTF 0.97085
U-Fueleda
GODIVA lDX-DTF 1.01184ZPR-3-11 lDX-DTF 1.01515ZPR-6-6A lDX 0.98323
TABLE V
CSEWGBENCRMARKEIGENVALUES
HETEROGENEITYCORRECTION
0.0166
0.0(373
PO+POOCORRECTION
-0.0032
-0.003
DIFF+S8CORRECTION
0.0018
0.0013
S16+S(3(3CORRECTION
-0.0021-0.002
-0.0017
aArrangedin orderof spectrumhardness.
TABLEVI
CENTWU SPECTRALINDICIES(calculated-TO-EXPERIMENTAL)
Pu-FueledaRatioW.R.T.
U-Fueleda
U235(N,F) JEZEBEL VERA-11A ZPR-6-6 GODIVA ZPR-3-11 ZPR-6-6A
Pu240(N,F) 1.0850PU239(N,F) 0.9363 1,0836 0.9625U238(N,F) 0.9485 1.1531 0.9377U238(N,G) 1.0534NP237(N,F) 0.9448 1.1758U236(N,F)U234(N,F,)U233(N,F) 0.9287 0.9993Th232(N,F)Au(N,G)
1.05400.9728 0.98431.0861 1.0563 0.94520.9925 0.9691 1.0309
1.05060.7851
0.9762 1.04050.9241 0.99891.07580.8491
CORRECTEDKEFF
0.995590.990350.98925
1.007141.015150.99183
aArrangedin orderof spectrumhardness.
8
APPENDIX A
SAMPLE DATA
This appendix contains abbreviated and DLAYXS CCCC-111 files. The 239PLIxnul-
BINX listings of the LIB-IV ISOTXS, BRKOXS, tigroup constants are featured.
LIB-IV ISOTXS LISTING
131NXC.,CONVERT MODE OF CCCC FILE
MODE=l (1 MEANs BIN TO RCO, 2 MEANS f3CD TO BIN]TYPET1 (1 MEANs ISOTX$, 2 MEANS BRKOXS, 3 MEANS DLAYXS)lRD= 1 1 -O -0 -O -O -O -0 -O -O
*KX FILEIsoTXs -- VERsloN 1 -- IJNIT 3kka●*UsER IDENTIFICATION**T2LASL MINX
FILE CONTROL PARAMETERS
NGROUPNISOMAXIJPMAXDNMAXORDICHIST
NSCMAX
NSBLOK
NUMBER OF ENERGY GROUPS TN SETNUMBER OF ISOTOPES IN SETMAXIMUM NUMBER (IF UPSCATTER GROUPSMAXIMUM NUMBER OF DOHNSCATTER GROUPSMAXIMUM SCATTERING ORDER$ETFF;:I:N SPECTRUM FLAG
= SET VECTOR=NGROUP, SET MATRTX
MAxIMuM NUMBER OF BLOCKS OFSCATTERING DATA
EIL(JCK~NG CONTROL FOR SCATTERING I)AT4
4
50
LIB~IV A 101-ISOTOPE 50-GROUP LIBRARY GENERATED WITH MINX FROM ENDF/B-Iv
ISOTOPE NAME1 HI2 HZ3 H3‘4 HE35 HE4b LT67 L178 t3E9Q Blkl
10 01111 C12
1.? NIIJ
13 0!614 F15 NA23lb MG17 AL2718 S1lQ CL.28 K21 CA.22 TI
23 v24 CH.?5 MN55?b FE27 C059.28 NI29 Cu3t3 CU6331 CU6532 Ufi7833 KR8ti34 KRR2
9
3536
373839urnQ14243444546474U49S@515253545556575859bublb?b364bsbbb7bfl6970717.?7374757b
7778
79/InMl828384
858b
87fi8899?91929390959b
979899
Ian
ltil
KR83KRf14
KRR6Z1RC2NB93
MOTC99
RHlG13AG107AG109
coCD113XE124XE126xE127xEli!8XE130XE131XE13.2XE134XE135XE136CS133SM!U9Eu1’ilEU152Eu153tu15u
GODY164LU175LlJ176TAlfllTA182
WIRZW183W184W1136
RE185RE187ALll~7
paTH.232PA233
11233U234U235U236U236
NP237PU238PU239Pu2ut’1131J211~
PU.?U2AU21JlAM.243cw~44
FP23ZNFP233SFP233RFP.235NFP?35sFP?35RFP?3c)NFP?3QsFP?39H
10
GROUP STRUCTURE
NEUTRON VE1OCITY uPPER ENkRGY
GROUP (CM/SEC) (EvI5,277U5E+G19 1.99711E+L17
: 3.6913(’39E+179 l,G100tit3E+U7
3 3.0?96klF+@9 6,!36531E+(464 2.359fJ6E+@9 3,67879E+06
5 IQ83755E+f19 2,23! 3tiE+U6
●
●
●
NUMaER (JF RECORDS TO BE SKIPPED
ISOTOPE RECOUDSla
: in23 254u 4t165 5086 6107 7A28 9649 !116
la 126811 1469i% 16.2113 182214 t97u15 2175lb 237617 257818 277919 2981?n 318.221 33832.2 358IJ23 3737?4 393625 4144126 U341?7 454228 U71629 49183? 511931 53193.? 551933 57.?034 592135 61?236 632437 65?538 672639 6928Ukl 710341 725142 745343 765544 785745 8@5946 826i47 846348 866449 8865561 906751 9.?6952 947153 967354 987555 10(47756 1022957 10431
11
58 l@b3359 10835bti IIU37tll 11.?396.2 114U1b3 11603b4 118U5t15 1.2t447b6 1?249t17 12451h8 1.?637b9 lZ’8397L4 13UU171 1324372 1344573 1360774 1384975 1405176 1425377 1U45S
78 1465779 14859f3v l’5n6181 1526382 1546583 1566784 1586985 16071l)b 1627387 1647588 16b7789 168799(? 17148191 1723392 1758593 175R794 175R995 17591q~ 1759397 1759598 1759799 17599
10t3 176fllInl 176f13
●
: (Skip to Pu-239 constants)
ISnTOPE 86
ISnTOPE CONTROL pAR4METtRS
HA13SID ARS(ILUTF ISOTOPE LABEL PU?39HIDENT LIBRARY 7DLNTIFTERtlt.tAT
FNDFRISOTUPE IDENTTFTCATION 1?60
AMASS GRAM ATnMIC wEICtiT .239ti5E+F13EFISS THERMAL ENERtiY/FISSTON (w*SFC/FISS) .351QhE-ltiECAP1 THERMAL ENERGY/CAPTURE (w*SEC/CAl’T) .187?7E-11TEMP ISOTOPE TEMPERATURE (I)EG K) B.SIGPUT AVE. PoTENTTAL SCATTERING (RARNS/ATOM) ,ltivkIflE+llADkNS kEFFRENCL ATON DENSTTY (A/13*CM) M.K13R ISUTUPL CLASSTFTCATJON ~ICHI FTSSITIN SPECTRUq FLAG (a/1/N=SET CHI/VECTOR/MATRIX) iIFIS (N,F) )(-SEC FLAG (ti/l=NO/YES) 1IALF (N,A) X-SFC FLAG (ti/l=NO/YES) n1 NP (N,P) X-SEC FLAG (U/l=N()/YES) GlIN2N (N,2N) X-SEc FLAG (n/l=NO/YFS) 1IND (N,D) x-SFC FLAG (ti/l=NO/YES) n
12
INT (N,T) X-SEC FLAG (@/l=NO/YES)LTOT hUMBER OF TOTAL X-SEC MOMENTSLTRN NUMBER OF TRANSPORT X-SEC MOMENTSISTRPD NUMBER OF TRANSPORT X-SEC DIRECTIONS
SCATTERING BLOCKS
8LOCK NAME TYPE ORDERS1 INELAS 2t317 4.? ELASTC 100 43 fN2N 3un 14 TOTAL 0 4
SCATTERING BANDWIDTH AND IN-GROUP SCATTERING P(ISITTON
●
●
46 46 2 46 U6 1 1
47 47 z ~7 Q7 ) 148 4R 2 4R 48 1 149 UQ 2 49 4Y 1 158 50 2 Sfl 5ti 1 1
PRINCIPAL CRnSS SECTIONS
GROUP STRPL STOTPL sNGAM
1 3.1796tE+flb 5.9umti3E+kIGI 2.55i522E-f13
2 3,5994tiEtGiU 6.67U8UE+tI@ 5.125/J5E-fi4
3 4.ZR234E+L7U 7.fi2359E+0fl ie6946bE-@34 4.731Q?E+aL! 7.79443E+vlfl 5.f3378@E-f135 4.97238E+DW 7.15a7t7E+c4n 1.ti?7313F-P2
●
●
●
46 1.86699E+ml 1.R6949E+L11 6.86168E-0147 2.57h16E+al 2.57883E+B1 2.lbY82F+fl@48 U.1756klE+Pl 4.17R41E+(41 7.72434E+fiId49 7.75153E+al 7.75453L+kll 1.89318Et~l5M 1.1Q912E+03 1.19914E+@3 3.Q5191E+P2
BLnCK 1 INFLAs SCATTERING,GROUP 1
POSN ORDER 11 2.Q61L45L-U,?
GROUP 2POSN ORDER 1
1 1.Ca81tRE-k12
2 n.77u43t-k32GROUP 3POSN ORDER 1
1 h.bB27?E-@32 2,9267?E-EI?3 2.87350E-82
ORDER 4
ORDER 21.9R279F-f12
3 41 11 11 11 1I 1
1 11 11 1
1 11 1
sFIS?.34f136k+@@2.lzlt28F+9Ql1.7”$’i33E+ti91.R7962E+AL71.9234k3k+kit4
9.12557F+dfi
1.41144t+Lll?.Ut49,2mE+til)].79R41F+41
7.95.?43E+vj2
ORDFW 31.323uIE-U2
PI+DER u7.96745E-(43
(lHDEQ d1.L18782F-(A56.96451E-!4U1.7448ME-W3
13
GROUPPOSN
11?34
GROLIPPOSN
;345●
●
●
GROUP?OSN
uORDER 1 OROER 2 OROFR 3 OROER 4
1.16116E-01 1.78123E-f13 l,43991E-k15 -1.57147E-t368.58675E-ti.2 5.62i352E-f14 6.91510E-@5 3,?Ii973E-klb5.U7C131E-U2 2.2n773E-f13 3,2454flE-u)4 2.lt4338E-t353.12u89t-143 43, 0. 0.
5ORDER 1 ORDER 2 ORDFR 3 CIRDkR 4
2.64095E-k31 3.79723E-n3 1.l14614E-d5 -4.143271?-6363.16531E-01 -9.914n4F-OU -l,16n4UE-d5 -2.57fi53F-Hb2.7@36QE-O\ 3.26128E-ti5 U,64688E-@6 -9.5m311nE-b4tl1.29825E-t31 5.45655E-05 8.37585E-d6 -4,?19Q6E-6i79.59246E-03 U.
[
POSN 1 = in-scatter
POSN 2 = I-1 to I
POSN 3 = I-2 to I9:
ORDER 1 nRDER 2 ORDER 3 OROER 41 TO 26
2728 TO 34
3536
37 To 38-39Ua4142434445464748495@
RI.OCK 2
Ft. tig
n. U, u. a.6.9fif175E-@9 -1.t44128E-@9 -2.62626k-10 -1.0R3n8E-lUv, a. G1. a.7.~55u2E-11 -2.7”3t4G?3E-l I -7.79106E-12 3.2411nF-l?2.?h264E-11 -8.38594E-12 -2.G!1697E-12 1.246hlE-12n. 0. il. ti.3.4235’5E-11 -1.a3332E-11 -2.0f177SF-l? 2,77UQ6E-l?3,1W699E-11 ‘1.29471E-11 -2.flV20RE-12 2.709@kiE-l?1.?286RE-11 -5.2Q0?2F-12 -7.?35U2E-13 1.1R2L35E-!2U.35R32E-12 -1.94541E-12 -1.814757E-13 4.14271E-134.73.257k-11 -2.l@974E-11 -2.?25@8E-12 4.R7287E-I?1.uh775t-11 -6.42997F-12 -6.46591E-13 1.5411113E-122.87846E-l? -b.53183E-13 -9.875k38E-15 1.3422iIE-135.412ult-12 -2.L392%uE-12 ‘7.Cib614E-13 4.bk3451E-t42.1379?E-l? u. n. 8,u.l]RIIE-l? - 1.5382tiE-12 5.4f3818E-13 1.499hUE-145.767RhE-13 u. me B.7eQ76@2E-lu ~. u. u,
ELASTC SCATTERTNC, URDEK ‘1GROUp
POSNI
GROUPPOSN
12
GROUPPllSN
12
GROUPPCISN
12
GROUPP17SN
12●
●
9
IURDER 1
3.l1469E+fifl2
ORDER 13.6Ynv71i+nM2.73n34E-u7
3ORDER 1
u.ul146E+bti2.5L4f125L-t12
uoUI)ER 1
c.?5\U8Etdm?.53016E-d2
5LIRDER 1
3.75?8’iE+toM?.56240t-ti2
ORDFR 2 (lROEti 3 ORDER d2*7n6118E+clu 2.37’3f39E+i40 2.06125E+@M
ORDER 2 ORDER 3 OROER 43.@6739t+~n .?,h620tiE+00 2.26742E+Mt43.82719F-f15 3.l19122E-n3 -6.R61i57F-kllJ
nRDER 2 URI)EN 3 nRpEf? 43.53767F+na 2.9527ZE+UGI 2.47ti75E+flu2.72197E-f13 2.4(45$ImE-k43 1.b7691E-43
nRl)tR 2 (lPl)F1/ 3 ORDER 4
3.@62.?9E+Vti 2.36329E+titl 1.9U63bE+t3i42.6516VE-03 6.79577E-ti4 2.87584E-fi3
ORDER 2 [JRI)FN 3 OROER 47.1866bE+clvj 1.4797F3F+tin 1.22K125E+oIM1.7d833E-f14 -1.95~19E-b33 1.968R5E-133
14
llLC)c K 3GkoLIP
P(7SN1
GROLJPPOSN
12
GUL)UPPOSN
11?3
Ctiouppflst.J
1 TO34
GHflUPPOSN
1 TO45●
N2N SC AT TFRTb G, ORDER 11
ORDFN I9.?488UF-11
2ORDER 1
t!.5q72538E-Vi~
3ORCJFti 1
v.1.32362E-t451.1758uL-n3
4ORDER 1
? P.1.2f155mE-031.32346E-ti?
5UUI)ER 1
3 n.9,61n5UE-n3u.Ib122E-d2
.
GROUP 5C4POSN ORDER 1
1 TO 47 0.46 2.f12463E-1409 .2.79F!2mk-135tl ,?,06193E-13
nl.flcK 4 10TAL SCATTERING, CJROER 4GROUP
POSN1
GI?OUPPOSN
12
GROdPPOSN
1z3
CROUPPOSN
1234
GROUPPnSN
12345999
1ORDER 1
3.14U3gE+ti@2
ORDFU 13.7Ll178ii+k+f31.15@59E-zll
3OROFU t
u.41807E+tiPi5.42962E-ki?3.10867E-62
l!(IROER 1
U.3b759E+ti611.11169E-015.72741t-ti2?.95941E-ki2
5LIRI)ER 1
4.fl169UE+kIn3.42155E-01.?.70369t-til1.a9t346E-kil9,28169E-42
(-IN!IER 23.53H32E+nti1.19268E-U21.188fIuF-m2
f)ROFR 23.i464n7E+Glkl3.2137aE-~32,2f!773E-t33a.
ORDER 22.19dUOE+@kI
-F).16571E-n43.261?AF-B55.45655E-n5Cle
ORDER 32,3fl&12E+kIn
OROFR 32.66549E+kIGf3.7(>2UlF.-02
ORDFH 3?.95?85E+M85.55181E-k435.?3447E-ti3
OPDFI{ 32,3633VE+Vfl7.487211E-IdU3.24S49k-04cl.
(lRDFR 31.4798@lk+@n
-1,9697’?E-034.646813E-k168.37585E-r460.
ORDER 4
.?.ki6922E+firl
ORDER 42,26839E+flti1.7q9’5LiE-02
ORDER u2.47f177F+&lL?2.3733bF-f131.74413(4E-M3
ORDER 4l,946136E+L’lkll?.879t79E-m32.1(3338E-U5d,
ORDLF? [email protected]?8E-43
-9,5C1311@E-nl!-4<21996F-U7
d.
15
CUDLIP seP(lSN (JRDFR 1 OR f)ER ~ OPIJFll 3
1 R.70955E+kl@ 2.4aQQbF-U2 3.lti12?F-,152 1. R6705E-i?l -b. ]Fll174F-n2 -2.33999 c-lo4
35 7.85542E-11 -2:73@n3E-11 -7:7YlLthF-1236 ?.?6264E-11 -8.385Q4F-~2 -?,tilh97E-12
37 T(.J 38 V. a. U.39 3.42555t-11 -I,q”5\3/F-]1 -70@~775E-1~Uti 3.ld69QE-11 ‘1.2Q471F-11 -?.\lq2b8t-~~01 1..?286FIF-11 -s.2Qt’122F-12 -7.?3S42E-1342 4.35832E-l? -1.9d541E-12 -1.Ra757r-13IJ3 IJ.73237E-11 -2.]0974F-11 -2,.?25URF-!2U4 1.46775E-11 -6.4?Y97E-12 -6.L16591E-1345 2.87R’\6L-12 -6.531~3E-13 -Q.875tiRF-1546 5.U12dlE-l? -.?.u922ME-J2 7.c4~Al/1~-1347 2.1379.?E-l? U. (q.08 4.17ubr4k-l? -1.5”\82kIE-12 5.4H81R~.-l349 1.13643E-l? k+. ~.58 U.92147E-13 d. (4.
ONDtQ Uif.
r’.e.
-1.viR3RfiE-ldn.3.?41!r’lF-l?1.2ft6t11F-124,,.2.771iQ(>E-122.709i314E-f?1.lf72R5F-f?4.1U271E-134.R72P,7E-I?1.54t81~3~-f~
1.542?L’IE-134.ht3451E-14(;:llc)cjt,ll~-f’q
u.‘u.
LIB-IV BRKOXS LISTING
131MX.-Q CONVERT hODE OF LCCC FILE
M(lnE=l (1 MEANs BTN TO @co, ? MEANS BCD TO BINITYPE=2 (1 MEANS lSOTXS, 2 NFANS uRKOXS, 3 MEANS DLAYXS)IRD= 1 1 -GI -O -O -O -O -B -fi -~
kk* FII.ERRKOXS -- VERSTON 1 -- u!+TT 3*****IJSER Il)ENTT~IcAT1oN** rpLAsL MINx
FILL CONTROL PARAMETERS
NGROUP NI.JM6ER OF ENERGY GROUPS rN SETNISOSH NUMBER OF ISOTOPES WITtl SELF-
SHIELDING FACT(JRSNSIGPT TOTAL NIIMf+ER OF vALLIEs OF VARIABLF x
WHICH ARE GIVEN. NSIGPT TS EOUAI. rUTHE SUM FROM 1 TO tNTSOSH OF NTABP(I)
NTEMPT TOTAL NIJMBER OF VALUES OF VARJA8LF TBwHICH ARE GTVFN. NTEMPT 1S EQuAL rnTHE SUM FROM 1 TO NISOSH flF NTART(I)
ISflTOPF NAML1 HtI! H23 ti34 HE 35 tlF4●
●
LN(SIGPO)/LN(lCl) VALUES FOR ALL lSOTOPES
‘ill
lnl
597
3n3
16
98 4~k30c3nuE+0u99 4,L30ti0klE+00
lk10 4.B00c40E+(4u181 4.0n0Fi0E+t30
TEMPERATURES (DEG C) FOR
ISOTOPE 1ST VALUE1 2,684tlklE+01~ 2068UG10E+Ol3 2.biluQl13E+01[1 2,6RU0t4E+015 2,6R4014E+01●
●
Q; 2.6840tiE+@l98 2,6840k)E+fll99 2.6R40UE+0i
140 2.684t3(4E+Gillnl ?.t)R4cI@E+fll
GRnUP STRUCTURF
GROUP TOP ENERGY1 l,9~711E+n72 1.ti@a@0E+fi73 b.d6531E+fd6.4 3,67879E+a65 2.?313tiE+f16●
●
●
>,vltlwk31.lcTwkl
[email protected]@@@[email protected]@FI@0E+410
ALI. ISOTOPES
.?NO VALUE6.2684eE+ki26,26840E+U26,?68UOF.+026..?b840t+026.26840E+k12
6.?6$14#E+klz602684?E+026.?6f14tlE+v126.2bt34L?t+k)26.26ROOE+L12
1.8?68iE:Qi;[email protected]+n3
l,82684EtG131.i326R4E+n31.82684E+m31.8268LIE+M3lp82613UE+@3
F-FACTOR START END GROI.JPS ANI) NUMdER OF SIGP(l TEMP vAL(IES
ISOTOPC JtJFH JBFL NTABP1 1 50 b2 1 58 63 1 50 6d 1 S@ 65 1 50 b●
●
v: 198 )99 1
lkifi 1Ikll 1
●
(1b
66b
● (Skip to Pu-239)
TnTAL SELF-SHIELDING FhCTORS IsO1OPE 86GROLIP 1sIGu TEMP 1 lEt4P 2 TEVP 3
1 l.@tiO@PE+&q 1.@@14P@F+@ti l.tiktl?mcai-’+v)~
2 9.QQ99Qt-471 9,Y9999E-U1 QoQ9Q99E-k!l3 9.99~87E-dl 9.999$37F-U1 q.9Q9t37F.-dl4 9.Q99iSE-dl 9*9Q915E-nl q.99915E-til
5 Q.99Rf17L-dl 9.998c!7E-P1 Q.Q98ti7F-kll9●
●
NTABT3z-i“43
17
GROUPSIGU
1?3u5
cl?olJPSIGO
1?345
GROUP.’31G0
;
345
:●
38TLMIJ 1 TEMP 29.8L462UE-141 9.89868E-?lR.ho5fJ6E-ol 9.H54QtiF-~15.79352F-fll b.4q97UE-f41LI.17ub7E-i31 4.b2hR3F-nl3.R,2QuciL-Mt ti.]9595E-fil
3QTtMP 1 TFMP 2Q.65823E-C1 9.n-5kl15E-til7.757i?0E-4tl 8.3Rti?8F-C41/.I,87762E-ul 5.4177FlE-Gll3,’i4tJ72E-bl 3.7525nE-fll3.?3443F-U1 3.37b6tiE-nl
UPT~14P 1 TFUP 29.?4ci9dE-dl 9.46$.33E-mj6.501O9E-O1 7.dta58dE-nl
3.99?8@E-dl 4.139flbF-@l~.Q57q5k_til 3*[email protected] ?.762?2E-fll
TEMP 39.97Ub{[email protected]$313?E-dl5.21u89E-tilfl.7B47Uk-til
T~FAp 3Q,Q3999E-131fl.882V8E-L416.m3f190E-ElU.fit)llnt!-ol3.62546E-t41
TEMP 39.622k$9E-til7.U94314RE-hl
4m3hbEi5ii-1313.ti86147E-vll2.82257E-MI
CAPTIJKE SELF-SHIELDING FACTORS TSOTnPF 86GROUPSIGU
12345●
●
●
GROUPSIGO
12345
GROUPSIG(I
123
:GROUPSIGO
;345
●
●
●
1TE~P 19.99997E-Lll9.Q9QY9E-till.m@@[email protected]+8GI
3RTEMP 1q.86RURE-bl9.U2799E-M1A.?6682E-013.QtiUqbE-,113.33294E-i41
39TEMp 19.77642E-L418.lb723E-01U.7a?Id6E-L+l?,72354E-012.3d52flE-til
48TEMP 19.u7423E-u16.Q7cilRE-dl3el~9~82E-41
2,1bn35E-dl1.92’l176E-til
lFMP 29.9331HE-([email protected]@t3tiE-nlu.q29fi4E-ml4.283P$3F-131
lEMP 29.9f12Gt9E-(41B.7R557E-al5.622RdF-013.3LJ868E-GI12.132211E-nl
TEMP 29.63917E-GJ17,b?ti31E-t314,[email protected]@l2.15973E-01
TEMP 3Q.9vQ9PE-vI19.9q993E-@ll.@l’l$lOlt+tifll,flOmbQk+@kl1,t!L4t?22E+ati
TEMp [email protected]?U7E-018.92RUUE-01s.~sqhfl~-k!l5.T1542E-Idl
TE!4P [email protected]~16.46628E-QI1U,@7859E-FJl3.47?9bE-k31
TEMP 3907uLa41E-018,12995E-tfl4.5f322RE-Idl2.8ti551E-iIl?.4713f!E-iIl
FISSION SELF-SHTELDING FACTORS ISOTOPF 86GROUP tSIG(J TEMP 1 TEMP 2 TEVP 3
1 l.nkIfl@flE+tifl 1.@@k4WdFtUfi I,uFInkl@E+tiPI
z 9.99998E-kll 9,99998E-81 9.99q9RE-til
3 9.9998UE-fil 9.999fl&F-Jil 9.9Qq8fIE-bl4 Q.99RY5E-t41 Y.Q9R95E-al 9,998Q5F.-M1
5 9.99761E-kll y.yq7blE-fll Q.99761E-01●
●
●
18
GROUPSIGO
1.2345
GI?OIJPSIGO
1a?34s
GROUPSIGO
:345●
:
38TEMP 19.9ki818E-kil9,?626i?E-til7.@0US7E-014,98194E-014.43986E-91
39TEMP [email protected]@7E-014.31637E-01
&@TtMP 19.63A72E-@l8,m0222E-015.58R77E-Idl4.?1033E-kIl3.88603k-01
TEMP 29*95449tiE-019.485R6E-ml7.5i’435E-nl5.586B2F-015.t32317E-01
TFMP 21.0@lz([email protected]?8F-nl5,29FIflklE-Ql4.70627E-01
TEMP [email protected]
TRANSPORT SELF-SHIELDING FACTORS
TEt4~ 3Q.98568E-01Q.65114E-018.@9246E-@l6,25742E-@l5,71L729E-01
TEMIJ 3l,@k17ti@E+009.61.282E-017.l15334E-015,[email protected]’3424E-@l
TEMP 39p81219E-01R.h2668E-91fI.fAb6@[email protected]
TSOTOPE 86
GROUPSIGO
123459
●
●
GRCIUPSIGLI
12345
GROUPSIGO
12345
GHOIJPSIG(I
12345●
:
1TEMP 11.m0aut7k+tivi9.9999RE-t319.999713E-k)l9.99853F-til9.996b4E-@l
3RTEMP [email protected]~638E-~1
3~TEMP 19.e58@7E-til7,73b19E-Ulu.R75’j7E-uI3.54212E-bl3.23171E-ttl
UclTEMP 1
9.?4(471E-EI1fl.5kimluE-dl3.Q9139ti-41t2.95583E-L412.73i?93E-dl
TEt4P~
l.O@OndEtfl@9,99998E-nl9.99978E-fll9.99t353F-nl9.99bbUE-01
TEMP ,?9.89860F-V19.k$5438E-tI16.4q789E-Pl4.62411E-OJ4.193c13E-@II
TEMP z9.83dI?7E-018.38754E-@l5,[email protected]
TFMP 2
9,[email protected](_2F-flt2.99hA9F-fll2.76d52E-dl
TEMP 3l.@@aO~E+nO9.’[email protected]‘3.996bUE.-61
TfMP 3Q.q7u56k-k319.37R92E-017.18856E-015.?1243E.-tilU.7M.2!iI?E-G31
TEMP 3Q.q3’?95E-alfi.R8?u’5E-til6.~3716E-til0.fi785UE-al3.62.27?E-M1
TLMP 39.62’197E-kfl7.48932E-dl4.364bClk-til3.G48439E-al2.82m6UE-til
19
GROUPSIGO
12345
GROUPSIG(I
t2345
GROUPSIGO
:3
;●
●
b
3RTEMIJ 19.92R8mE-kjl9.38063E-418.a6b35E-til7.?5028E-i417.k!b3Q7k-tll
3Q
TLMP 19.85274E-L3113.97c179E-kil7.44R28E-LIIA.72fY13.2E-til6.56345E-01
49TtMP 19.717.2UE-E1R.44862k-til&.Rb481~-@l
6.?6c!71E-dl6.13021E-til
CROSS SLCIIUNS
GROUP xsPLl1 4.1295@E-iiiz~ 2.56521E-t713 4.dn817F-nl
4 7,t35782E-025 U,52797E-818
9
●
TFHP [email protected]”5174F-nl7.53948E-@l7,3?668E-ml
TEMP 29,9”5ti4tiE-C419.2Q181E-nlT.79962E-nl6,93847E-016,74234F-nl
TEMP [email protected].?534F-@l
xSINl,[email protected]!E+@fl
TkMP -51.n@2f14t+titiQ.76121E-til8.75359E-c17.U432Sk-Ul7.61276E-01
TEMfJ 3
9.q8943k-kll
9.529M8E-u18.16149E-U17.2M367E-EII6.97763E-141
TEMP 39.P1711?E-U19.r4~lJ~7~-~1
7.31’[email protected]@ki’5E-?l
Xsli3.14199E+f4C43.71598E+004.43h77Etflti
4..?77ll3E+t4k!3.7817@E+@0
[email protected]_173uE+nti1.kf62R8E+@l8,7G!955E+(4$
LIB-IV DLAYXS LISTING
131NX... CONVERT MODE OF CCCC FIIE
MOf)E=l (1 r4EANs HIN TO RCl), .? MEANS f3Cfl TO BIN)TYPE=3 (1 MEANS ISOTXS, 2 MEANS i3RKOXS, 3 MEANS OLAYXS)IRD= 1 1 1 1 -M -M -U -b -0 -0DELAYED NEUTRON PRFCLJ12SOR DATA DLAYXS
IJSFR IDENTJF7CATIUN T2LASLNJ0Y
FILE VERSION NUMBER 1
FILE CONTROL PARbMETFtis
NGROUP NIIMBER OF fvFUTRON ENERGY GROUPS IN SETFJISOD NuMf3ER (IF lSOTUPES TN l)ELAYED
NEuTRON SETNFAM NUMF5ER OF DELAYED NEUTRON FAMILIES
IN SETIr)lJM DUMMY TO MAKE UP U-k4URl) RECORD
FAMILY NUMBER OF K-TH YIELD VECTOR1 TH232~ 112333 11235
lJ~-j8z PUI?396 Pu24@7 PU.241
20
XSM(If3.65cJ43E-tilR.27t,[email protected]
7.lbf133E-til5.78t39E-til
2.u133aE-k132.fl133RE-F132.8133RF-ti-$?.R133RE-k$32.R13”\RE-k13
42
42
DELAYED NEUTRON PRECURSOR DECAY CONSTANT FOR FAMILY NFAMILY N
i 12370E-@l2 :3340@E-fll3 .12100E+m0.4 .3Z100E+005 .l?19uE+nl6 .3290@E+01
7 .I?580E-018 .334?0E-1719 .131@&E+@’d●
9
34 .i240@F+nti40 .35i?00E+0041 .161L30E+G11U2 .347m0F+@l
FRACTION (IF DELAYED NEUTRONSGROUP FAMILY 1
1 TCJ 5 fl.b 4.?8756E-oU7 l,@itfluIE-L33u 1.39243L-B39 1.67277E-$13
10 3.13473@E-k!3●
99
EMITTEO INTDFAMILY 2G)[email protected]@23.45R42E-f421.8R974E-m22.591334E-f13
NEUTRON ENERGy GROIJP FROMFAMILY 3 FAMILY 40. k!,5.96U11E-B3 l*54fl(’)vE-vjz1.82556F-k12 5.19319E-ti21.52397E-u2 3e7?657E-@2l,56667E-t12 u,73ht15E-kIZ1.25841E-ti2 5.3i37alE-02
PRFCIIRSOR FAMILYFAMILY 5 FAMILY b0. 4.S.97a21E-tiT t.u9255E-a32.nk$276E-02 ‘i.fln689E-@310U3715E-ti2 3,59288F-P31.l?266QE-@2 [email protected] 5.19376E-F13
GROUP FAMILY 37 FAMILY 38 FAMILY 39 FAMTLY 4M FAMILY fJl1 10 5 a, ki. la,
FAMILY 02U. n,
6 3.99911E-@a 6.26133k!E-@2 6,b935PE-(43h.
1.2224%E-02 5,7k3477E-437 R.99575E-uO f3.632fihF-@2 1.36R61E-02
5.zl151vF-fi43,(>35f16E-ti2 1.ti9673E-ti?
8 5.93667E-ijU U,15176E-$4Z1.49163F-lZ3
I,78613E-u29
1.71bf,2E-O? tl.Giln9@F-713 7.@4.?55E-m4‘5.14U83t’-04 .?.0G1511F-fi2 1.71OI55F-M2 5,!411’53E-L42 2.33A71E-L32 i?.U56fllF-133
lU f).7~Q26E-M4 1.253’52E-03 1.72@34E-Id2 5.377c17E-ti? 2.’ikiQ5Ok-ti2 2.2U5Q8E-f15
MAXIMUM ENERGY BOUNDGROUP .J
1 1.99711E+c172 l,IdUL3@OE+073 b.t36531E+G164 3.67879E+06●
●
●
NuMBER OF FAMTLIFS T(l WhTCH FISSTUN IN ISOTOPE CONTRIBUTES I)ITLAY!EO 14FUTRON Pl~ECiJQSnNS
ISnTOP/NllMIjLR 11 62 63 (14 65 6b 6
7 6
NUMbFI+ OF RECORDS TO BE SKIPPED TO ltEAl_I I)ATA FOR lsOTIWt
21
●
s (Skip to Pu-239)
FAMII.Y NUMBER OF K-Tti YIF1.D VECTOR
FAMLIY/VFCTUR 1 .? 3 4 5 h1 ?5 26 27 28 29 3~
APPENDIX B
OPEWTING INSTRUCTIONS FOR THE
UTILITY CODES LINX, BINX, AND CINX
The CCCC utility codes used to manipu-
late LIB-IV are described more completely
elsewhere. 9,10 However, for convenience,
the operating instructions for these codes
have been included in this report as Tables
B-I, B-II, and B-III.
TABLE B-I
LT.NXOPESATION INFORMATION
Input/Output Units
3 — primary binary input file.a4 -- secondary binary input fi e.8 -- final binary output file.
k
6 -- listing of messages and diagnostics.
User’s Input
None
aISOTXS or BRKOXS only.
bUser identification, version, andlibrary identifier are taken fromthe primary input file.
TN GROllPFAMII,Y 54.42q13;41i-ti40.5944bF-ti46.lli557E-ufl6.hu351E-3u6.b4351E-ti4
i>.h4351k-wLl
n.h4351k-14uh.b14351E-bljh.643SlE-MUh.bu351E-nu
FAMTLY h1.5@[email protected].?2F-au2,1@[email protected]’575t4E-f14
The versions of LINX, BINX, and CINX
included on the LIB-IV transmittal tape are
for the LASL CDC 7600. They can be easily
converted to a short-word machine such as an
IBM 360 by following the instructions found
on the “C IBM comment” cards which will be
found in the codes.
TABLE B-II
BINX OPERATINGINFORMATION
Input/OutputL!nits
3 -- inputbinary (BCD) unit.a8 -- output BCD (binary) unit.5 -- system input for user’s input.6 -- system output for listing and diagnostics.
User’s Input-
One card (1215):MODE,NTYPE,IRD(KI.0)
MODE = 1 means binary input and BCD output.MODE = 2 means BCD inputand binaryoutput.NTYPE= 1 meana ISOTXS.NTYPE= 2 meana BXXOXS.NTYPE= 3 means DLAYXS.IXD(I)= 1 mesnsprint the Ith recordtype.
aISOTXS, BRKOXS, or DLAYXS only.
22
TABLE B-III
CINX OPERATINGINFORMATION
InputFiJ.es
3,4,12-- Fine-groupbinaryCCCC-111ISOTXS,BRKOXS,and DLAYXS files, respectively.
Output Files
8,9,13 -- Coarse-group bimry CCCC-111 ISOTXS, BRKOXS,and DLAYXS files, respectively.
10 -- Coarse-group lDX binary format.
System Files
5 -- Data cards.6 -- Computer printout.PUN -- PERT-V output on cards.
Data Cards:
1. Run Options Input Card (Format 516).MF Najor functions (0/1/2 = collapse/lDX/both).NCG Number of coarse groups (omit if NF = 1),ICF Collapsing flux (0/1 - thermal-Fermi-Watt/input)
(omit if MF= 1).NDT Number of downscattering terms (including ingroup)
(omit if MF = O).NPF Neutron precursor file (0/1 = No/Yes) (- for PERT-V
data).
2. Number of Fine Groups per each Coarse Group (Format 1216)(omit ifMF= 1).
3. Parameters for ICF = O Option (Format 4E12.5) (omit ifMF=lorICF#O).
TE Nuclear temperature (eV) for thermal spectrum region(0.025 used for LIB-IV).
EB Upper limit (eV) for thermal region (0.1 used forLIB-IV).
TC Nuclear temperature (eV) for WATT spectrum region(1.4 x 106 used for LIB-IV).
EC Lower limit (eV) for WATT region (0.8208 x 106used for LIB-IV).
4. Input Flux (Format 6E12.5) (omit if MF = 1 or ICF = O).
REFERENCES
1. D. Garber, Ed., “Data Formats and Pro-cedures for the ENDF Neutron Cross Sec-tion Library,” Brookhaven National Lab-oratory report BNL 50274 (1976).
2. C. R. Weisbin, P, D. Soran, R. E. Mac-Farlane, D. R, Harris, R. J. LaBuare,J. S. Hendricks, J. E. White, and R. B.Kidman, “MINX: A Multigroup Interpreta-tion of Nuclear X-Sections from ENDF/B,”Los Alsmos Scf.entific Laboratory report(in preparation).
3. B. M. Carmichael, D. A. Meneley, andD. R. Vondy, “Report of the Subcommitteeon Standard Interface Files,” Los AlamosScientific Laboratory report LA-532&-MS(1973) .
4. B. M. Carmichael, “Standard InterfaceFiles and Procedures for Reactor PhysicsCodes, Version III,” Los Alamos Scien-tific Laboratory report LA-5486-MS(1974) .
5. R. E. MacFarlane and R. M. Boicourt,“NJOY: A Neutron and Photon Cross Sec-tion Processing System,” Trans. Am.Nuc1. SOC, ~, 720 (1975).
6. C. R. Weisbin and R. J. LaBauve, “Spe-cifications of a Generally Useful Mul-tigroup Structure for Neutron Trans-port, “ Los Alamos Scientific Laboratoryreport LA-5277-MS (1973).
23
7.
8.
9.
10.
11.
12.
13.
14.
15.
R. W. Hardie and W. W. Little, Jr.,“lDX, A One-Dimensional Diffusion Codefor Generating Effective Nuclear CrossSections,” Battelle Northwest Labora-tory report BNWL-954 (March 1969).
R. W. Hardie and W. W. Little, Jr,,“PERT-V, A Two-Dimensional PerturbationCode for Fast Reactor Analysis,” Bat-telle Northwest Laboratory report BNWL-1162 (September 1969).
R. E. MacFarlane and R. B. Kidman,“LINX and BINX: CCCC Utility Codes forthe MINX Multigroup Processing Code,”Los Alamos Scientific Laboratory reportLA-6219-MS (1976).
R. B. Kidman and R. E. MacFarlane,“CINX, Collapsed Interpretation of Nu-clear X-Sections,” Los Alamos Scientif-ic Laboratory report (in preparation) .
1. I. Bondarenko, Ed., Group Constantsfor Nuclear Reactor Calculations (Con-sultants Bureau, New York,
R. B. Kidman, R. E. Schenter, R. W.Hardie, and W. W. Little, “The Shield-ing Factor Method of Generating Multi-group Cross Sections for Fast ReactorAnalysis,” Nucl. Sci. and Eng. ~, 189-201 (1972).
R. E. MacFarlane and M. Becker, “Self-Shielded Cross Sections for NeutronTransport in Iron,” Trans. Am. Nucl.Sot. ~, 668 (1975).
R. E. MacFarlane and M. Becker, “Self-Shielding of Elastic Transfer Matrices,”Trans. Am. Nucl. Sot. ~, 495 (1975).
M. F. James, “Energy Released in Fis-sion,” J. Nucl. Energy ~, 517 (1969).
16.
17.
18.
19.
20.
21.
22.
23.
N. B. Gove and A. H. Wapstra, The 1971Atomic Mass Evaluation, The Nuclear-Reaction Q-Values (Academic Press, Inc.New York, 1912) .
C. M. Lederer. J. M. Hollander, and J.Perlman, Table of Isotopes, Sixth Edi-tion (John Wiley and Sons, Inc. , New~, 1967).
H. Alter, R. B, Kidman, R. LaBauve, R.Protsik, B. A. Zolatar, “ENDF-202 CrossSection Evaluation Working Group Bench-mark Specifications,” Brookhaven Nation-al Laboratory report BNL-19302 (1974).
K. D. Lathrop, “DTF-IV, A Fortran-IVProgram for Solving the MultigroupTransport Equation with AnisotropicScattering,” Los Alamos Scientific Lab-oratory report LA-3373 (1965).
E. M, Bohn, Ed., “Benchmark Testing ofENDF/B-IV,” Brookhaven National Labora-tory report ENDF-203 (February 1976)-.
R. E, Schenter, J. F. Baker, and R. B.Kidman, “ETOX, A Code to CalculateGroup Constants for Nuclear ReactorCalculations ,“ Battelle Northwest Lab-oratory report BNWL-1OO2 (May 1969).
R. B, Kidman, “A Comparison of Two FastReactor Cross Section Processing Codes,”Hanford Engineering Development Labor-atory report HEDL-TME-72-57 (February1972) .
W. W. Little, R. W. Hardie, R. E. Schen-ter, E. M. Pennington, B. A. Hutchins,and L. N. Price, “Numerical Comparisonof Data Processing Codes for Fast Reac-tors,” Trans. Am. Nucl. SOC. ~, 144(1969) .
* USQ0VSf4NMWTPiW4TlN130FFlCE 107&W7-343/fOS
24