Back
7.014000+3 1.388278+1 0 0 2 5
0.000000+0 0.000000+0 0 0 0 6
1.000000+0 1.500000+8 8 0 10 31
0.000000+0 0.000000+0 0 0 558 1
7-N - 14 LANL EVAL-JUN97 M.B.CHADWICK & P.G.YOUNG
Ch97,Ch99 DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 725 REVISION 3
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: ENDF/B-VI.8 **
** **
******************************************************************
****************************************************************
ENDF/B-VI MOD 5 Revision, May 2000, S.C.Frankle, R.C.Reedy,
P.G.Young (LANL)
The secondary gamma-ray spectrum for radiative capture (MF 12,
MT 102) has been updated for new experimental data at incident
neutron energies up to 400 keV. The Q-value for radiative capture
was also updated in File 3. Details of these changes are
described in Frankle et al. [Fr01].
The Legendre coefficients in MF=14, MT=102 were corrected by
dividing each coefficient by 2L+1.
******************************************************************
ENDF/B-VI MOD 4 Evaluation, August 1997, M.B. Chadwick and
P.G. Young (LANL)
Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code
in cooperation with ECN Petten.
This evaluation provides a complete representation of the
nuclear data needed for transport, damage, heating,
radioactivity, and shielding applications over the incident
neutron energy range from 1.0E-11 to 150 MeV. The discussion
here is divided into the region below and above 20 MeV.
INCIDENT NEUTRON ENERGIES < 20 MeV
Below 20 MeV the evaluation is based completely on the ENDF/B-
VI.3 (Release 3) evaluation by P. G. Young, G. M. Hale, and M.
B. Chadwick [Yo94].
INCIDENT NEUTRON ENERGIES > 20 MeV
The ENDF/B-VI Release 3 evaluation of n + 14N data extends to
40 MeV and includes cross sections and energy-angle data for all
significant reactions. The present evaluation utilizes a more
compact composite reaction spectrum representation of the data
above 20 MeV in order to reduce the length of the file, and we
have only included the ENDF/B-VI data below 20 MeV. To avoid
redundancy, the sections MT=78-90 are removed, since their
thresholds lie between 20 and 40 MeV. No essential data for
applications is lost with our representation above 20 MeV.
The evaluation above 20 MeV utilizes MF=6, MT=5 to represent
all reaction data. Production cross sections and emission
spectra are given for neutrons, protons, deuterons, tritons,
alpha particles, gamma rays, and all residual nuclides produced
(A>5) in the reaction chains. To summarize, the ENDF sections
with non-zero data above En = 20 MeV are:
MF=3 MT= 1 Total Cross Section
MT= 2 Elastic Scattering Cross Section
MT= 3 Nonelastic Cross Section
MT= 5 Sum of Binary (n,n') and (n,x) Reactions
MF=4 MT= 2 Elastic Angular Distributions
MF=6 MT= 5 Production Cross Sections and Energy-Angle
Distributions for Emission Neutrons, Protons,
Deuterons, Tritons, and Alphas; and Angle-
Integrated Spectra for Gamma Rays and Residual
Nuclei That Are Stable Against Particle Emission
The evaluation is based on nuclear model calculations that have
been benchmarked to experimental data, especially for n + 14N
and p + 14N reactions [Ch97]. We use the GNASH code system
[Yo92], which utilizes Hauser-Feshbach statistical,
preequilibrium and direct-reaction theories. Spherical optical
model calculations are used to obtain particle transmission
coefficients for the Hauser-Feshbach calculations, as well as
for the elastic neutron angular distributions.
Cross sections and spectra for producing individual residual
nuclei are included for reactions. The energy-angle-correlations
for all outgoing particles are based on Kalbach systematics
[Ka88].
A model was developed to calculate the energy distributions of
all recoil nuclei in the GNASH calculations [Ch96]. The recoil
energy distributions are represented in the laboratory system in
MT=5, MF=6, and are given as isotropic in the lab system. All
other data in MT=5,MF=6 are given in the center-of-mass system.
This method of representation utilizes the LCT=3 option approved
at the November, 1996, CSEWG meeting.
Preequilibrium corrections were performed in the course of the
GNASH calculations using the exciton model of Kalbach [Ka77],
[Ka85], validated by comparison with calculations using Feshbach,
Kerman, Koonin (FKK) theory [Ch93]. Discrete level data from
nuclear data sheets were matched to continuum level densities
using the formulation of Ignatyuk [Ig75] and pairing and shell
parameters from the Cook [Co67] analysis. Neutron and charged-
particle transmission coefficients were obtained from the
optical potentials, as discussed below. Gamma-ray transmission
coefficients were calculated using the Kopecky-Uhl model [Ko90].
DETAILS OF THE n + 14N ANALYSIS
GNASH calculations [Yo92,Ch94] were performed for neutron and
proton reactions on nitrogen up to 150 MeV, and the calculated
results were benchmarked against experimental data. For neutrons
below 100 MeV, the present evaluation made extensive use of our
previous work [Ch96a]. Very minor differences with this earlier
work exist due to recent developments in the GNASH code. Much use
was made of measured data in the evaluation, since an accurate
modeling of reactions on a light nucleus is difficult. In this
way we were able to obtain a fairly good description of the
emission spectra of secondary particles and gamma rays.
Additionally, the (angle-integrated) emission spectra of heavy
recoils were calculated using our model described in Ref. [Ch96].
Some additional information on this evaluation can be found in
Ref. [Ch97].
Between 20 and 150 MeV, the optical models used (the neutron
potential of Islam below 60 MeV [Is88]; Madland's potential
[Ma88] at higher energies, with Lane transformations for the
proton potential) provided a reasonably good description of
measured reaction cross section data. But since a very accurate
description of the reaction cross section is important for
determining secondary particle spectra, we slightly modify the
calculated results to better describe the experimental data, and
renormalize the calculated transmission coefficients accordingly.
The SCAT2 code [Be92] was used to calculate the transmission
coefficients. No measurements for the neutron reaction cross
section on nitrogen exist above about 50 MeV. However,
systematics have been determined from a number of target elements
at 95 MeV by DeJuren [De50], and for 100 MeV protons by Kirby and
Link [Ki66] (at this energy the proton and neutron reaction cross
sections would be expected to be very similar). We have,
therefore, used these systematics to guide our evaluated reaction
cross sections. Additionally, below 50 MeV we have also been
guided by the proton-induced reaction cross sections of Carlson
et al. [Ca75]. Experimental total elastic scattering values of
Islam et al. [Is88], Olsson et al. [Ol90], and Petler et al.
[Pe85] were obtained by subtracting their angle-integrated
elastic data from the evaluated total cross sections (see below).
The evaluated total cross section was obtained by slightly
modifying the optical model results to agree with data,
principally the new high-accuracy results of Finlay et al.
[Fi93]. We use the ENDF/B-VI total cross section below 40 MeV
recently evaluated by Young [Yo94].
Preequilibrium spectra for incident energies below 100 MeV were
taken from our previous work [Ch96], where they were evaluated
from a combination of FKK calculations [Ch93], and measured
emission spectra data, while ensuring that unitarity is conserved
(i.e., making sure the sum of primary emitted preequilibrium
spectra does not exceed the reaction cross section). This
approach has the advantage of facilitating a good representation
of emission spectra experimental data. However, the lack of such
data above 100 MeV prohibits its extension to higher energies,
and therefore above 100 MeV, exciton model calculations were
utilized from the GNASH code [Ka77, Ka85]. This results in some
(small) discontinuities around 100 MeV in the production cross
sections, though the impact of this is negligible for most
applications.
Nuclear level densities were determined using the Ignatyuk
model [Ig75], as implemented by Arthur et al. [Yo92]. Pairing
energies were obtained from the Cook systematics with the Los
Alamos extensions to light nuclei from [Ar83]. This continuum
level density formulation is matched continuously onto discrete
low-lying levels at the lower excitation energies. Discrete level
information (energy, spin, parity, gamma-ray branching ratios) is
tabulated for each nuclide in an input file, which is based on
the Ajzenberg-Selove compilations. For each nucleus we performed
a level-density analysis and determined the excitation energy at
which we judged the level data complete. Gamma-ray transmission
coefficients were obtained from the Kopecky-Uhl model [Ko90].
An important test of the accuracy of the data libraries is that
the evaluated emission spectra of light particles (A < 5) should
be consistent with the measurements by Subramanian et al. of UC-
Davis [Su86]. We have compared our calculated (lab frame) angle-
integrated emission spectra of protons, deuterons, and alphas,
with these measurements, with good agreement. The structure seen
at high emission energies is due to the inclusion of discrete
nuclear levels in our calculations. Also, kerma factors obtained
from the evaluated cross sections are in fairly good agreement
with experimental data [Ch96].
****************************************************************
ENDF/B-VI MOD 3 Revision, August 1994, P.G. Young (LANL)
This modification corrects the elastic and inelastic cross
sections (MT=63-90) at incident neutron energies above 13.5.MeV
given in MOD 2 of ENDF/B-VI. This correction was made to
improve agreement with elastic scattering measurements up to
25 MeV. The elastic neutron angular distributions above 20 MeV
were also improved over the earlier data distributed in MOD 2,
based upon fits to experimental data.
****************************************************************
ENDF/B-VI MOD 2 Evaluation, September 1992, P.G. Young (LANL)
Extension to 40 MeV
The modified version of the ENDF/B-VI evaluation created for
DNA (described below) is extended in energy to 40 MeV. This ext-
tension was accomplished using experimental data and the 9/92
Version of the GNASH code, which was updated for higher energy
calculations. More details will be given in a later progress
report.
The ENDF/B-VI evaluation was modified for DNA use to include
results from Hale's R-matrix analysis that include Harvey's new
total cross section measurement. These results are interim until
we can incorporate the new ORNL scattering data. The ORNL
preliminary scattering results confirm the parity of the first
resonance as being positive, as used in the R-matrix analysis.
****************************************************************
ENDF/B-VI MOD 1 Evaluation, May 1990, P.G. Young, G.M. Hale,
M.B. Chadwick (LANL)
N14 free atom evaluation
GENERAL COMMENTS:
The ENDF/B-VI data file for N14 is an essentially complete new
evaluation. Below 2.5 MeV, it consists of an R-matrix analysis of
the available experimental total, elastic, (n,p0), and (n,alpha0)
cross sections and angular distributions using the EDA coupled-
channel r-matrix code. At higher energies, the evaluation
is an update of the 1972 evaluation of Young and Foster [Yo72]
to include new experimental data since that time. More details
of the evaluation are included below.
MF=2 ------------------------------------------------------------
MT=451 No Resonance Parameters. Scattering Radius =8.86366-13 cm
MF=3 ------------------------------------------------------------
THERMAL (2200 M/S) CROSS SECTIONS
TOTAL 11.8135 B (N,GAMMA) 0.075 B
ELASTIC 9.9114 B (N,P) 1.8271 B
NONELASTIC 1.9021 B
MT=1 Total Cross Section
Zero to 2.2 MeV, SIGT is obtained from sum of elastic, (n,p0),
(n,a0) cross sections from r-matrix analysis, plus the (n,g)
cross section described below. The coupled-channel r-matrix
analysis was performed with the EDA code, fitting simultane-
ously almost all available total, (n,n), (n,p0), and (n,a0)
exp. data. The most important total cross section used were
[Me49,Bi59,Bi69] at lower energies, and [Ca70,He70,Fo71]
at higher energies. Significant shape difference found in
the 0.1 - 20 keV region as compared to ENDF/B-V.
2.2 MeV to 20 MeV, from [Ca70,He70,Fo71] using Ca70 alone
at sharp resonances. Smoothed by appropriate fits, log-log
interpolations is good to 1.3 pct to 0.4 MeV, linear inter-
polation is good to 0.5 pct from 0.4 to 20 MeV, absolute
error less than 1 pct above 2.2 MeV. Minor changes made in
ENDF/V.2 evaluation in certain regions of high structure.
MT=2 Elastic Scattering Cross Section
Zero to 2.2 MeV, based upon r-matrix analysis described
above. Experimental elastic angular distributions in analysis
were [Fo55,Jo66].
2.2 to 20 MeV, based upon data of [Ch61,Ba67,St61,Ba63,Fo55,
Jo66,Ph61,Be66,Lu67] and, especially, [Ch86,Te85,Ba85,Pe85,
Pe74, Ne72]. Nonelastic cross sections were adjusted somewhat
to achieve agreement with elastic data.
MT=4 Sum of MT=51-82 Cross Sections.
MT=16 (N,2N) Based on [Fe60,Br61,Bo65,Pr60]. 30% error estimated
MT=51-62 Discrete Inelastic, Including N,Np Decay (LR=28)
Threshold to 20 MeV. From (n,ngamma) data of [Di70,Or69,Cl69,
Bu71,Ny71,Co68,Ha59,Be70,Di73] and, especially, [Ne89,
Ro74,Ne72,Au86], together with the (n,n') data of [Ch86,
Pe74,Ba63,Ba85,Ta87]. The level decay scheme of [Aj86]
was used to interpret the (n,ngamma) data.
MT=63-90 Inelastic Assuming Energy Bands Centered Around
the Excitation Energies Chosen. Note that N,Np (LR=28) and
n,nalpha (LR=22) decay are included and labeled. The cross
sections are adjusted by differencing between total and
nonelastic. Cross sections to the bands based on Hauser-
Feshbach and nuclear temperature calculations.
MT=102 Radiative Capture
Zero to 0.25 MeV, 1/v from 75 mb(+-10pct) at thermal [Ju63].
0.25 to 1 MeV, transition region.
1 to 20 MeV, deduced from N14(p,gamma)O15 data of [Ku70],
assuming charge independence. Energy scale adjusted to match
foot-hills of (p,gamma) giant resonance to resonance clusters
served in N15 compound nucleus.
MT=103 Sum of MT=600-606 Cross Sections.
MT=104 Sum OF MT=650-653 Cross Sections.
MT=105 SUM OF MT=700-701 Cross Sections.
MT=107 Sum OF MT=800-810 Cross Sections.
MT=108 (N,2ALPHA) Cross Section.
Based on [Li52,Mo67] and Hauser-Feshbach calculation.
MT=600 (N,P) Cross Section to C14 Ground State.
Zero to 2.2 MeV, taken from coupled-channel r-matrix analysis.
R-Matrix analysis based on [Jo50,Ga59], and esp. [Mo79].
2.2 to 13 MeV, based mainly on [Mo79] and inverse reaction data
of [Wo67].
13 to 20 MeV, smooth extrapolation.
MT=601-606 (n,p) Cross Sections to C14 Excited States.
Thres. to 20 MeV, from (n,pgamma) data of [Or69,Di70,Cl69,Bu71,
Ny71,Ro74].
MT=650 (N,D) Cross Section to C13 Ground State.
Thres.to 15 MeV, from inverse cross section data of [Ch61,Be63]
Near Thres.and direct data of [Mi68,Fe67,Ca57,Za63] at 14 MeV
Plus the (n,dgamma) data of [Ro74,Ne89].
15 to 20 MeV, smooth extrapolations.
MT=651-653 (n,d) Cross Section to Excited C13 Levels.
Thres. to 20 MeV, direct data of [Fe67,Za63,Ca57], and
(n,dgamma) data of [Or69, Di70, Ro74, Ne89].
MT=700-701 (N,T) Cross Sections to C12 Ground and 4.439 MeV Ex-
cited State.
Thres. to 15 MeV, direct data of [Ga59,Sc66,Re67,Fe67].
15 to 20 MeV, smooth extrapolations.
MT=800-810 (n,alpha) Cross Section to Discrete B11 States.
Thres. to 2.2 MeV, taken from coupled-channel r-matrix analysis
direct (n,alpha) data included [Jo50,Ga59,Sc66] but the
analysis mainly relied on Mo79.
6 to 20 MeV, Used above direct data, together with (n,agamma)
data of [Ha59,Di70,Or69,Ny71,Bu71,Be70,Cl68] and, especially,
the data of [Ne89,Ro74]. Near En=14 MeV, the direct (n,a)
data of [Li52,Ba68,Le68,Ma68] were also used.
MF=4 ------------------------------------------------------------
MT=2 Elastic Angular Distributions.
Zero to 2.2 mev, based upon r-matrix analysis described
above. Experimental elastic angular distributions in analysis
were [Fo55, Jo66].
2.2 TO 20 MeV, based upon data oF [Ch61,Ba67,St61,Ba63,Fo55,
Jo66,Ph61,Be66,Lu67] and, especially, [Ch86,Te85,Ba85,Pe85,
Pe74,Ne72].
MT=16 Angular Distribution for (n,2n) Reaction
In the absence of data, isotropy in the cm system is assumed,
and the corresponding 3-body phase-space is transformed to
the lab system. For any reasonable cm distribution
the strong forward peaking of the transformation will
dominate. Normalized for trapezoidal integration.
identical to ENDF/B-V.
MT=51 to 62 Angular Distributions for Inelastic Scattering
based mainly on (n,n') data of [Ch86], but the data of [Pe74,
Ta87,Ba63,Bo61,Ba85] were used as well.
above 7 MeV also used proton data of [Do64,Ha70,Od60]
assuming charge symmetry, and neutron data of [Ba63].
threshold shapes modeled after Hauser-Feshbach calcs.
MT=63-90 Angular Distributions for Inelastic Scattering.
Assumed isotropic in cm at all energies.
MF=5 ------------------------------------------------------------
MT=16 Spectrum of (N,2N) Secondary Neutrons
in the absence of data, only the 3-body phase-space distribu-
tion is given. Normalized for trapezoidal integration.
identical to ENDF/B-V.
MF=12 -----------------------------------------------------------
MT=102 (N,GAMMA) Multiplicities (same as ENDF/B-V)
Zero to 0.25 MeV, thermal spectrum based primarily upon mea-
surements of [Th67,Jo69,Gr68,Mo62].
.25 to 1 MeV, transition region where thermal spectrum is
phased into single ground-state transition.
1 to 20 MeV, deduced from N14(P,G)O15 data of [Ku70], who
observed no significant transitions except to ground state.
*** Note that gamma rays from N14(n,gamma,n') reactions are
included under MT=102 rather than MT=4. This produces
error messages when the checking code PSYCHE is run because
there is an apparent violation of energy conservation.
However, total energy is still conserved when MT=102 and
and MT=4 are considered together.
MF=13 -----------------------------------------------------------
All (N,XG) cross sections agree with the excitation cross
sections in MF=3 via the relevant decay scheme [Aj80,Aj86].
*** Note that gamma-ray production cross sections are not
included for MT=16. The reason is that all excited
states in N13 are unstable to particle emission and
the gamma-ray cross sections are negligibly small.
MT=4 (N,NG) Cross Section
From data of [Ha59,Di70,Or69,Cl69,Bu71,Ny71,Co68,Be70,Di73],
and especially, [Ne89,Ro74,Ne72,Au86] together with the
(N,N') data of [Ch86,Pe74,Ba63,Ba85,Ta87] and the level
decay scheme of [Aj86].
MT=28 (N,NPG) Cross Section
From data OF [Di70,Or69,Bu71,Ny71,Cl69,Ne89,Ro74,Ne72,Di73],
after subtraction of MF=13,MT=103 data.
MT=32 (N,NAG) Cross Section
From data of [Di70,Or69,Bu71,Ny71,Cl69,Ne89,Ro74,Ne72,Di73],
after subtraction of MF=13,MT=107 data.
MT=103 (N,PG) Cross Section
From data of [Di70,Or69,Bu71,Ny71,Cl69,Ne89,Ro74,Ne72,Di73].
MT=104 (N,DG) Cross Section
From data of [Di70,Or69,Bu71,Ny71,Cl69,Ne89,Ro74,Ne72,Di73],
and estimates of MF=3,MT=651-653.
MT=105 (N,TG) Cross Section
(N,TG) estimated from (n,t) as discussed under MF=3,MT=741,
and from (N,XG) data (see list below for MT=107).
MT=107 (N,AG) Cross Section
From (N,A) data of [Ga59,Sc66,Mo79] and (N,AG) data of
[Ha59,Ny71,Or69,Bu71,Di70,Di73,Cl68,Co68] and esp. [Ne89,
Ro74,Ne72]. Level decay scheme of [Aj80] was used.
MF=14 -----------------------------------------------------------
Data on 9 strongest lines from inelastic scatt. and particle
reactions taken from [Mo64] -- same as ENDF/B-V.
MT=4 Inel. Scatt. to N14, 1.63 and 4.91 MeV Anistropic
MT=102 (N,GAMMA) Angular Distributions.
Zero to 0.4 MeV, all photons are isotropic.
.4 to 20 MeV, anisotropic distribution for the single ground
State transition is based upon N14(P,Go)O15 data by [Ku70].
MT=103 (N,P) to C14, all isotropic.
MT=104 (N,NP)+(N,D) to C13, 3.85 MeV anisotropic
MT=105 (N,ND)+(N,T) to C12, all isotropic
MT=107 (N,ALPHA) to B11, all isotropic
MF=33 -----------------------------------------------------------
To be provided at a later date.
*****************************************************************
REFERENCES
[Aj80] F. Ajzenberg-Selove and C. Busch, Nucl.Phys.A 336, 1
(1980)
[Aj86] F. Ajzenberg-Selove, Nucl.Phys.A 449, 1 (1986)
[Ar83] E.D. Arthur, Los Alamos National Laboratory progress
report LA-9841-PR (1983).
[Ba63] R.W. Bauer et al., Nucl.Phys. 47, 241 (1963)
[Ba67] R.W. Bauer et al., Nucl.Phys.A 93, 673 (1967)
[Ba68] R. Bachinger and M. Uhl, Nucl.Phys.A 116, 673 (1968)
[Ba85] M. Baba et al., Nuclear Data for Basic and Applied Science
Proc. Conf., Santa Fe, NM, May 1985, Vol.1 (Gordon and Breach,
1986) p.223
[Be63] R.E. Benenson and B. Yaramis, Phys.Rev. 129, 720 (1963)
[Be69] F.D. Becchetti, Jr., and G.W. Greenlees, Phys.Rev. 182,
1190 (1969)
[Be92] O. Bersillon, Proc. ICTP Workshop on Computation and
Analysis of Nuclear Data Relevant to Nuclear Energy and Safety,
Feb./Mar. 1992, Trieste, Italy, to be published in World
Scientific Press; also Progress Report, Bruyeres-le-Chatel
1977, CEA-N-2037 (1978) p.111
[Bi59] E.G. Bilpuch et al., private comm. to BNL (1959)
[Bi62] E.G. Bilpuch et al., private comm. to R.J. Howerton (1962)
[Bo65] M. Bormann et al., Nucl.Phys. 63, 438 (1965)
[Br61] O.D. Brill et al., Sov.Phys.-Dokl. 6, 24 (1961)
[Bu71] P.S. Buchanan, private comm. (1969)
[Ca57] R.R. Carlson, Phys.Rev. 107, 1094 (1957)
[Ca70] A.D. Carlson, R.J. Cerbone, Nucl.Sci.Eng. 42, 28 (1970)
[Ca75] R.F. Carlson, A.J. Cox, T.N. Nasr, et al., Nucl.Phys.
A445, 57 (1985); R.F. Carlson, A.J. Cox, J.R. Nimmo, et al.,
Phys.Rev.C 12, 1167 (1975).
[Ch61] L.F. Chase et al., report AFSWC-TR-61-15, (1961)
[Ch86] J. Chardine et al., report CEA-N-2506 (1986)
[Ch93] M.B. Chadwick and P.G. Young, Phys.Rev. C 47, 2255 (1993)
[Ch96] M.B. Chadwick, P.G. Young, R.E. MacFarlane, and A.J.
Koning, Proc. of 2nd Int. Conf. on Accelerator Driven
Transmutation Technology and Applications, Kalmar, Sweden, June
1996.
[Ch96a] M.B. Chadwick and P.G. Young, Nucl.Sci.Eng. 123, 1 (1996)
[Ch97] M.B. Chadwick and P.G. Young, in APT progress report:
1 July - 1 August 1997, internal Los Alamos National Laboratory
memo T-2-97/M-45, 6 Aug.1997 from R.E. MacFarlane to L. Waters
[Ch99] M.B. Chadwick, P.G. Young, G.M. Hale, et al., Los Alamos
National Laboratory report, LA-UR-99-1222 (1999)
[Cl69] G. Clayeux and G. Grenier, report CEA-R-3807 (1969)
[Co67] J. L. Cook, H. Ferguson, and A. R. De L Musgrove, Aust.J.
Phys. 20, 477 (1967)
[Co68] H. Conde et al., Neutron Cross Sections and Techology,
Proc. Conf., Washington, DC (National Bureau of Standards,
1968) p.763; also report AE-354 (1969)
[De50] J. Dejuren and N. Knable, Phys. Rev. 77, 606 (1950)
[Di70] J.K. Dickens et al., Nucl.Sci.Eng. 40, 346 (1970)
[Di73] J.K. Dickens et al., report ORNL-4864 (1973)
[Do64] P.F. Donovan et al., Phys.Rev. 133, B113 (1964)
[Fe60] J.M. Ferguson and W.E. Thompson, Phys.Rev. 118, 228 (1960)
[Fe67] P. Fessenden and D.R. Maxson, Phys.Rev. 158, 948 (1967)
[Fi93] R. W. Finlay, W. P. Abfalterer, G. Fink, et al., Phys.Rev.
C 47, 237 (1993)
[Fo55] J.L. Fowler and C.H. Johnson, Phys.Rev. 98, 728 (1955)
[Fo71] D.G. Foster, Jr. and D.W. Glasgow, Phys.Rev.C 3,576 (1971)
[Fr01] S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos
National Laboratory Report, LA-13812 (2001).
[Ga59] F. Gabbard et al., Nucl.Phys. 14, 277 (1959)
[Gr68] R.C. Greenwood, Phys.Lett. 27B, 274 (1968)
[Ha59] H.E. Hall and T.W. Bonner, Nucl.Phys. 14, 295 (1959/60)
[Ha70] L. Hansen, private communication (1970)
[He70] H.T. Heaton et al., Bull.Am.Phys.Soc. 15, 568 (1970) and
private communication from R.B. Schwartz (1970)
[Ig75] A. V. Ignatyuk, G. N. Smirenkin, and A. S. Tishin, Sov.J.
Nucl.Phys. 21, 255 (1975); translation of Yad.Fiz. 21, 485
(1975)
[Is88] M.S. Islam, R.W. Finlay, et al., Phys.Med.Biol. 33, 315
(1988)
[Jo50] C.H. Johnson and H.H. Barschall, Phys.Rev. 80, 818 (1950)
[Jo66] C.H.Johnson, et al., Neutron Cross Sections and Technol.,
Proc. Conf., March, 1968, Washington, DC (National Bureau of
Standards, 1968) p.851
[Jo69] L. Jonsson, R. Hardell, Symposium on Neutron Capture
Gamma Rays, Studsvik (1969) p.199
[Ju63] E.T. Jurney, H.T. Motz, report ANL-9797 (1963) p.241
[Ka77] C. Kalbach, Z.Phys.A 283, 401 (1977)
[Ka85] C. Kalbach, Los Alamos National Laboratory report
LA-10248-MS (1985)
[Ka88] C. Kalbach, Phys.Rev.C 37, 2350 (1988); see also
C. Kalbach and F. M. Mann, Phys.Rev.C 23, 112 (1981)
[Ki66] P. Kirkby and W.T. Link, Can.J.Phys. 44, 1847 (1966)
[Ko90] J. Kopecky and M. Uhl, Phys.Rev.C 41, 1941 (1990)
[Ku70] H.M. Kuan et al., Nucl.Phys.A 151, 129 (1970)
[Le68] B. Leroux et al., Nucl.Phys.A 116, 196 (1968)
[Li52] A.B. Lillie, Phys.Rev. 87, 716 (1952)
[Ma68] D.R. Maxson et al., Nucl.Phys.A 110, 609 (1968)
[Ma88] D.G. Madland, Proc. OECD/NEANDC Specialist's Mtg. on
Preequilibrium Nuclear Reactions, Semmering, Austria, 1988,
report NEANDC-245 'U' (1988) p.103
[Me49] E. Melkonian, Phys.Rev. 76, 1750 (1949)
[Mi68] D. Miljanic et al., Nucl.Phys.A 106, 401 (1968)
[Mo62] H.T. Motz et al., Pile Neutron Research in Physics
(IAEA, Vienna, 1962), p.225
[Mo64] I.L. Morgan et al., Texas Nuclear Corp. NUcl.Phys.Div.
annual report (Aug. 1964)
[Mo67] J. Mosner et al., Nucl.Phys.A 103, 238 (1967)
[Mo79] G.L. Morgan et al., Nucl.Sci.Eng. 70, 163 (1979)
[Ne72] D.O. Nellis and P.S. Buchanan, report DNA-2716 (1972)
[Ne89] R. Nelson, S. Wender, et al., Private comm. (1989)
[Ny71] K. Nyberg-Ponnert, Phys.Script. 4, 165 (1971)
[Od60] Y. Oda et al., J.Phys.Soc.Japan 15, 760 (1960)
[Ol90] N. Olsson, E. Ramstrom, and B. Trostell, Phys.Med.Biol.
35, 255 (1990)
[Or69] V.J. Orphan et al., report GA-8006 (1969)
[Pe74] F.G. Perey et al., report ORNL-4805 (1974)
[Pe85] J.S. Petler, M.S. Islam, R.W. Finlay, and F.S. Dietrich,
Phys.Rev.C 32, 673 (1985)
[Ph61] D.D. Phillips, LANL, private comm.to R.J. Howerton (1961)
[Pr60] J.T. Prud'homme et al., report AFSWC-TR-60-30 (1960)
[Re67] D. Rendic, Nucl.Phys.A 91, 604 (1967)
[Ro73] J.C. Robertson, J.Nucl.En. 27, 531 (1973)
[Ro74] V.C. Rogers et al., report DNA-3495F (1974)
[Sc66] W. Scobel et al., Z.Physik 197, 124 (1966)
[Su86] T.S. Subramanian, J.L. Romero, F.P. Brady, et al., Phys.
Rev. C 34, 1580 (1986); J.L. Romero, private communication
to MBC (1994).
[Su88] A. Suhaimi, report JUEL-2196 (1988)
[Ta87] A. Takahashi et al., report INDC(JAP)-103/L (1986)
[Te85] J.A. Templon et al., Nucl.Sci.Eng. 91, 451 (1985)
[Th67] G.E. Thomas et al., Nucl.Instr.Meth. 56, 325 (1967)
[Wo67] C. Wong et al., Phys.Rev. 160, 769 (1967)
[Yo72] P.G. Young and D.G. Foster, Jr., report LA-4725 (1972)
[Yo92] P.G. Young, E.D. Arthur, and M.B. Chadwick, report
LA-12343-MS (1992)
[Yo94] P.G. Young, G.M. Hale, M.B. Chadwick, ENDF/B-VI Release 3
of N-14 evaluation (1994)
[Za63] M.R. Zatzick and D.R. Maxson, Phys.Rev. 129, 1728 (1963)
************************ C O N T E N T S ***********************
1 451 563
Back
|
