imc(in)s)-6i/w +specialPapers presented
at theConsultants1 Meeting on Charged Particle and Photonuclear Reaction Data
Vienna, 24-26 April 1974

and at theSpecialists* Meeting on Nuclear Data for Applications
Vienna, 29 April - 3 May 1974

Edited "by
A. Calamand and A. Loren z
Nuclear Data Section
IAEA

Vienna, July 1974

Contents

page
Forewordix

List of papers presented at the two meetingsiii

List of statements from participants in theSpecialists1 Meetingvi

A,

Papers presented at the two meetings

B.

Statements from participants in theSpecialists' Meeting

- i-

171

Foreword

A Consultants' Meeting on Charged Particle and Photonuclear
Reaction Data and a Specialists' Meeting on Nuclear Data for
Applications by the IAEA Nuclear Data Section were convened in
Vienna, from 24 to 26 April and from 29 April to 3 May 1974
respectively, upon the recommendation of the International Nuclear
Data Committee.

This report includes documents presented at the two meetings
as well as statements made by the participants in the Specialists'
Meeting concerning their home programme.

The summary reports of the two meetings, including theirconclusions and recommendations, are published separately as
INDC reports (INDC(NDS)-59 for the Consultants' Meeting and
INDC(NDS)-6O for the Specialists' Meeting).

- ii -

Presented at thejConsultants'Meetg|
Presented at the]Specialists'Meetgj

List of papers presented at the two meetings

Designation

1. Survey of current and future needs for charged p a r t i c l e andphotonuclear reaction data, by A. Calamand
2. "Photonuclear Physics 1973, Where We Are and How We Got There"by E. Puller
Reprint from the Asilomar Conference on Photonuclear Reactions& Applications, March 26 - 30, 1973

Reference(The number refers
to a page of t h i sreport)INDC(NDS)-62

see original
publication

3. Photonuclear Reaction Data, 1973 - NBS Special Publication 380
U.S. Department of Commerce, National Bureau of Standards,
issued March 1973.
4. Photonuclear Reactions, by E. Hayward. NBS Monograph 118.
U.S. department of Commerce, National Bureau of Standards,
issued August 1970
5. Summary of Compilation and Evaluation A c t i v i t i e s (Photonuclear Reactions). Excerpt from recent USNDC meetings3

6. The Photonuclear Data Centre. March 1974*(Description of the centre a c t i v i t i e s ) .

9

7. Charged P a r t i c l e Cross Section
based f i l e s .

14(CPX) Data Center computer -8. Charged-Particle Cross Section Data Center(Dates and T i t l e s of Publications)19

9. Nuclear cross sections for cnarged-particle-induced reactions,
N and 0, compiled by H.J. Kim, W.T. Milner, and F.K.McGowan.
NUCLEAR DATA, Section A, Volume 3, Number 2, September I967.
(Sample).

see original
publication

10. Reaction List for Charged-Particle-Induced Nuclear Reactions
Z - 1 to Z - 98 (H to Cf), July 1972 - June 1973
by P.K. McGowan and W.T. Milner
ATOMIC DATA AND NUCLEAR DATA TABLES 12, 499-583 (1973).
11. Computerized Libraries of Nuclear Data,
March 1, 1974

by S. Pearlrtein
20

12. Generalized EXPOR Isoquants(Proposal by the Nuclear Data
Sectr.on, reproduced from Memo 4C-3/93).

33

13. Nucl«ar Data Section Short Guide to EXFOR

36

14* Principle8 of constructing systematized, bibliographic
nucltjar data f i l e s , By A.I. Abramov - Report INDC(CCP)-29/L.
- iii

-

see original
publication

List of papers presented at the two meetings (cont'd)0) -H+> nj "tocfl at
+»
-b C
(D 3
-p -p
R r-4
41 -ri
01 3
CO (D
m o
CD a

Designation

h O

0, O

15.

Photonuclear Cross Sections, by B. Buelow and B.
Forkman.
(Documents 15 and 16 are two chapters of the Handbook
on Nuclear Activation Cross Sections, Technical Reports
Series no. 156, IAEA, Vienna, 1974)

16.

Excitation Functions for Charged-Particle-Induced
Reactions in Light Elements, by J. Lorenzen and
D. Brune

17.
18.
19.
20.

Reference(The number refers
to a page of t h i sreport)pL, W "

see original publication-id -Nuclear Structure Data File - Preliminary SpecificationsMarch 29, 1974, by the Nuclear Data Project

40

Memo of .March 20, 1974 from W.B. Ewbank to the Nuclear
Data Project Compilers

69

The Digital Data Files Cof the Photonuclear Data Center,by H.M. Gerstenberg

73

Landolt-Boernstein - New series - Springer Verlag-Band I 5a - Q-values for 64 reaction types with 25
different projectiles-Band I 5^ - 1800 excitation functions for chargedparticle induced reactions-Band I 5° - Systematics of excitation functions fornuclear reactions induced by p,d, ^He anda particles
by H. Muenzel et a l .

21.
22.
23.
24.
25.
26.
27.

see original
publication

The State of Work on Non-Neutron Nuclear Data in the
USSR, by L.L. Sokolovskij, Yu.I. Fenin and F.E. Chukreev

82

Computerized Libraries of Nuclear Data for Applications,by S. Pearlstein (April 1, 1974)

104

Nuclear Data Project, paper presented at the IWGNSRD
in March 1972, by D. Horen127

Non-Neutron Nuclear Data: A proposal for International
Cooperation, by A. Lorenz (April 29, 1974)

133

Nuclear Data in Science and Technology: Structure andScope, by A. Lorenz (April 29 r 1974)
Information Center for Applied Users, by G.A.Bartholomew(April 26, 1974)
Draft Recommendations
IAEA Consultants Meeting on Charged Particle andPhotonuclear Reaction Data (24 - 26 April 1974)- IV-

to be publishedas INDC report139

see final version
in INDC(NDS)-59

List of papers presented at the two meetings (cont'd)00

A 0)
n! "co -p a) to-c) mDesignation

<B 3
+» +»
a <-t
0) pi
in u
a> c
fc o
PL,

Reference(The number refers
to a page of t h i sreport)

<D -H
ID O
O

Q>

O

28.

Conclusions and recommendations of the f i r s t meetingof the IWGNSRD, Vienna, March 197229.

6th INDC Meeting, Recommendations (October 1973)

142

30.

6th INDC Meeting, Subcommittees of INDC (October 1973)

144

31.

6th INDC Meeting, Requirements and applications ofborder-line nuclear and atomic data, by D. Berenyi(Oct. 1973)

148

Notes on a Computerized Decay Data P i l e , by C.M.Ledererand A. Shihab-Eldin (April 22, 1974)

150

NUSPEC (= Nuclear Spectroscopy Interactive Program
Package) Table of Isotope Project, Lawrence Berkeley
Lab., Tty CM. Lederer, A. Shihab-Eldin

156

34-

Draft by D. Horen (April 30, 1974)

165

35.

Status of Author's Guide, by G.A. Bartholomew(April 26, 1974)

32.
33.

T V

-

INDC(NDS)-46

v"

169

List of statements from participants in the Specialists' Meeting,concerning their home programme on nuclear data

page
1.

Present compilationalby P.M. Endt

2.

Remarks on the dissemination of non-neutron nuclear data,"by D. Horen173

Current Status of the Table of Isotope Project,
Berkeley, USA, by A. Shihab-Eldin

174

The state of non-neutron nuclear data in Prance andwithin the Euratom evaluation group, by J.Blachot et al.

175

Summary of Nuclear Data Evaluation at BCNM, Geel,
by W. Bambynek

178

Status Report of the NEA Neutron Data Compilation Centre,
Saclay, Prance, by P. Proehner

179

Remarks on Computerized Nuclear Data Piles,
by S. Pearlstein

181

Compiling Projects at Chalk River Nuclear Laboratories(CRNL), by G.A. Bartholomew

182

Summary of Nuclear Data Activities at the AAEC Establishment
at Lucas Heights, Australia, by B.J. Allen

I83

Statement of the Liverpool University Position,
by J.P. Sharpey-Schafer

I85

Report from Sweden on activities in the field of evaluationand compilation of nuclear data, by L. Stroemberg

186

3.

4»

5«

6.

7.

8.

9«

10.

11.

activities in the Netherlands,

12. "The National Nuclear Data Libraries" at the Institutul de
Fizica Atomica, Bucarest, by Al.I. Badescu et al.
13.

Report on the Yugoslav
by G. Paic

172

I87

Nuclear Data Activities,188

- 1 -A«

Papers presented at theConsultants' Meeting on Charged Particle andPhotonuclear Reaction data
and at theSpecialists' Meeting on Nuclear Data for
Applications

- 3-

SGMMARY 0? COMPILATION AND EVALUATION ACTIVITIES(Pnotonuclear Reactions)*7.

Photonuclear Data Compilation and Evaluation—E. Fuller
Fuller updated an earlier description of the activities ofthe photonuclear data center at NBS presented at the NCSAC meeting of
May 1971 (see NCSAC —37).

He noted that as a result of the NCSAC

recommendation support in the area of photonuclear cross section
cczr-pilation had increased with the National Standard Reference Data System
assuming responsibility for supporting the NBS compilation .effort.

laaddition a NTRA associate has been assigned to the project for the next
trso years.

One of the major outputs of the center is the Photonuclear

Data Index and, to date, two supplements.

The objective of this projecti3 to formulate and maintain a current photonuclear data file which canbe \zsed as source material.

The original index, NBS Miscellaneous

Publication 277 covars data from data from January 1955 to January 1965.
The two supplements cover data from 1965 to February 1970. A new
data index has been prepared in draft form and covers all publications
with a cutoff data of August, 1972. It is hoped to have a final versionof this document in time for the Asilomar Conference which will cover
all oublicatio^s from 1955 to 1973. The intention is to publish this index
ir. Nuclear Data A. All of the published data contained in the photoneutron
iricex has been stored in the centers files and can be retrieved according
to specific entries in the N3S photonuclear index.
The center does have plans for a compilation program*He noted that 2lready a group at Lund had published a compilation ofphotonuclear data directed toward activation analysis under the title,
Photor.uclear Cross Sections.

The authors are Bulow and Forkman.

At present this compilation is available as a Nuclear Physics report
No. JLUNP—7208 and it will be published as a 55-page chapter in thebook on activation analysis.

In the center's survey of publishedmeasurements 311 targets were identified and 207 data sets.
are includad in this body of data.
fo:- S5 of these casea.

256 isotopes

The Lund group has compiled results

The NBS effort will attempt a complete description

- 4 -of this data body.

An atlas is planned which will p r e s e n t 5 types ofdata for each targe-.;—first curves of all pertinent c r o s s sections in
a 16 X 22 c m f o r m a t , second resonance p a r a m e t e r s which give g r o s sfits for the c r o s s sections for photons cf l e s s than 30 MeV e n e r g y ,3) sum r u l evalues for the total absorption c r o s s section weighted•with v a r i o u s p o w e r s of the photon energy, 4) tabular c r o s s section
data over e n e r g y i n t e r v a l s of . 5 MeV, and finally 5) tables of yielddata for a l l i m p o r t a n t or useful reactions.

The yield data will

include b r e m s s t r a h l u n g weighted c r o s s sections at energy pointsof 10, 15, 2 0 , 2 5 , and 30 MeV for total neutron yield and m e a s u r a b l e
activities.

A total of 5 man years of effort is planned for completionof this compilation.
Goldstein noted that Abramov of the Instituteof P h y s i c s and P o w e r , Obninsk, USSR had circulated a r e p o r t on a
CINDA type compilation of threshold photoneutron data. A translationof this r e p o r t would be of value as would a response to the proposal on
the p a r t of USNDC. Fvdler indicated that the NBS Photonuclear Centeris planning a response to the Soviet effort.

He noted that this was alimited photoneutron index covering only c r o s s sections in the region, ofthreshold.

The index included the same article as many as 10 t i m e s .

He did not believe that.a need for such an expanded nuclear data index
existed.

Kolstad indicated that this was the first case-in which theRussians have asked for our comments and cooperation and an NDC
response would be" desirable.

Jackson stated that the c h a r a c t e r of

the compilation proposed was extremely detailed including entries fore v e r y piece of d a t a , graph, table, e t c . individually.

Horen noted thatthe m a t e r i a l is in the CINDA Indexformat and questioned why thischoice.
16•Jackson

It also appeared to him that the detail of the compilation was

excessive.

A New Action 16 was adopted on Jackson, to obtain atranslation of the Abramov document to circulate it together with al e t t e r of c o m m e n t .
*From USNDG-A-A (Meeting 24-26 October 1972, National Bureau ofStandards, Gaithersburg, Maryland)
Came out as M3S SP 380 due to publication problems (see p.3)

- 5-

1.

Photonuclear Data Center (E.G. Fuller, H.M. Gerstenberg, andH. Vander Molen)*

N33 Special Publication 380, Photonuclear Reaction Data, 1973
~w=-s published in March. This 125-page book contains a complete index toall seasure3ents in the field published in the period from 1955 to 1972.
Ir. addition, a brief sunnnary is given of the gross features of the giantresonance. Included are tha energy at which the cross section peaks, thenaxioum value reached by the cross section, tha width of the "resonance"at half naxiaiuni, and the two cross section integrals which are most useful
fcr estieatir.g yields, o*_o^m^ an<^ ^-l^^m)- Data are presented both intabular as well as graphical form for all nuclei where measurements havebean =,ade~ Where a number of measurements have been made for a single
nucleus, the parameters tabulated were taken from the single measurement
which was felc to give the most representative picture for that nucleus.
Related to this publication is the invited paper, Photonuclear
Physics. 1973. Where We Are and How We Got There, presented (EGF) at theAsiiornar Conference on Photonuclear Reactions and Applications (March1973). This contained a very brief history of the field, a review ofthe data novi available, and finally, a summary of the results of aworld-wide survey nade in *arly 1973 of existing an,d proposed facilities
and programs in photonuclear physics.

3C

Jrom DSSDC-7 (Heeting at Oak Ridge National Laboratory, 18-20 Jane 1973)

- 6 -

1.

Atlas of Photon gutron Cross Sections Obtained witheiiarsetic Photons (B. L. Berman)

A compilation, in a uniform format and current as of early 1373, ofphotoneutron cross-section data obtained with rronoenargetic photons frompositron annihilation in flight has been issued as UCRL-74622. Tnis
atlas was distributed at the International Conference en Fnotonuclear
Reactions and Applications in March. The USNDC has, of course, expressed its great desire that such a compilation be made available fora variety of applications purposes.
Over the years, a considerable body of data on photonautroa crosssections obtained with iror.oenargetic photons from the annihilation inflight of fast positrons has been acquired at the Livermore, Saclay, andGeneral Atomic Laboratories. The data on 65 nuclei studied with annihil=~icn photons (^9 fro- Livermore measurements, 25 from Saclay, and two
frc~: General Atro~i.c) ars gathered together hers and presented in a uniform format, in order to serve as a nucleus for a more complete ccmpila-.
tion and evaluation (which would include data obtained with continuous
bremsstrehlung radiation sources .as well). The photonuclear group at
the I National Bureau of Standards is undertaking such a comprehensive
compilation and evaluation, and the data in this atlas will be a majorpart of it. J-fearr^nile-, these data are available in both graphical anddigital form. It is hoped that this service to the physics community
will be utilised both for purposes of theoretical analysis and for those
associated with applications to other scientific disciplines and technologies
No attempt was made here to evaluate the data; i . e . , to choosa be—•;aan t>:o sets of data for the same nucleus measured a t different laboratories , or to compromise between them by 'presenting a set of recommended
intermediate values. I t should be noted, however, that the overall agreement and consistency between measurements made at the three laboratories i svery good indeed, especially when viewed in the light of the enorrous d i s crepancies between laboratories frequently obtained in the past for bremsstrahlung-induced photonuclear measurements.
From USNDC-7 (Meeting at Oak Ridge National Laboratory, 18-20 June 1973)

- 7A T L A S(of Photonuclear '.'rosa Section Data)

The Photonaclear T)\ta. Center i s developing a comprehensive, annotated compilation of selected data on the interaction of electromagnetic radiation with nuclei.

The photon energies of interest range

from the photodisintegration thresholds to the meson production threshold.
The object i s to present the best available data for each nuclide in a
uniform format in such a way that i t i s useful not only for theoreticalphysicists and active experimental workers in the field but also usefulfor the various applied workers in fields such as medical physics,
activation analysis, radiation shielding, etc.

I t i s planned to publish this compilation in two or three sections
the first of which i s scheduled for completion early in 1974.

For eachtarget nuclide or element for which sufficient data exist the compilation
will give:
I.

Figure 16^22 cm: Gives all pertinent cross sections
as a function of £ . There will be a few cases wherei t might require u$ to 3 separate figures to givejustice to all the available data,

13

Resonance Parameters that give a gross f i t to the absorption cross section for E < 30 MeV.

III.

Y
Sum Rules: cr (£ ) , <r ,(E ) , cr _(E ) for total absorption cross section. B Us the KigSest energy for which
absorption data exist. If data go to high energies,
1.e., 14G MeV, these quantities will also be given for
B = 30 MeV.
IB

IV.

Table 1 - Cross Section Data
Lists all pertinent cross section data as function of
B . AE = 0.5 MeV and finer if data warrant.
Y
Y

V.

Table 2 - Yield Data
This table will give:
1. Thresholds for all "important and/or useful"reactions.
2.

I so topic abundance.

3.

Radioactivity data for end products of reactions.

*" ^ - l ^ i 5
a.
b.
VI.

(E

i =1 O j 1 5 ' 2 ° *Z5* 3 ° HeV^ for""Total neutron yield.
Each reaction that resalts in a measurable
radioactivity.

A selected annotated bibliography on photopartide spectral
and angular distribution data.

Photonuclear Data Center
Center for Radiation Research
National Bureau of Standards
Washington, D.C. 20234
October 1, 1973

- 9The Photonuclear Data Center - March 1974
National Bureau of Standards
Washington, D. C. 20234

Definition
Fhotonuclear physics data are defined to be any experimental results thatgive information about the electromagnetic matrix element connecting the groundstate of a nucleus with any excited state or the continuum. The transition may
be induced by real or virtual photons. Data satisfying these criteria but which
are not included in the Photonuclear Data Center's files are those obtained from
Coulomb excitation and slow neutron capture experiments. While some such data
are included in the Center's files, no attempt has been made to include all groundstate, radiation widths obtained from delayed y~Y coincidence, Doppler shift attenuation, etc. , experiments.
What the Center Does
-Systematically abstracts, collects, and indexes data from the publishedliterature for the field of photonuclear physics.
-Maintains a library of digitized photonuclear cross section data.
-Serves as an information center for the field of photonuclear physics.
-Periodically publishes an updated cumulative index to the data publishedin the field and that in its files.
What the Center Has-Copies of the more than 2000 journal papers that have been published since1955 giving experimental data for the field.
-A file of 4200 data abstract sheets giving information and data from over
4600 separate measurements. Each sheet gives for a specific nuclide or element
all of the pertinent experimental data given in a particular journal reference.
(See example.)-A library of selected cross section data in digitized form. It now contains
data for over 675 curves measured for more than 99 different nuclides covering 68
elements.
-A computer-searchable index to data in the field that can generate bibliographies
satisfying specific assignments of one or more of the following quantities: Nuclide
studied. Reaction, Type of measurement, Excitation energy range, Source Type andEnergy, Angle data, Reference number.
-A sonic delay digitizer for entering data available in graphical form only
(e.g., reports, journal articles, etc.) into the cross section data library.
Services the Center Provides-'Publication of a biennally updated, completely annotated, cumulative index
to the data in its files. Latest issue: Photonnclear Reaction Data, 1973. HBS
Special Publication 380 (March 1973). This publication covers experimental data- 10 -

Services the Center Provides (continued)
for the field of photonuclear reactions published in scientific and technicaljournals in the period from 1955 through 1972. (See sample page.) It may bepurchased from the Superintendent of Documents, U.S. Government Printing Cffice,Washington, D.C 20402. Price $2.10 domestic postpaid or $1.75 G.P.O. Bookstore.
-Selected annotated indices and bibliographies covering specific types ofdata or reactions.*-Information in form of data abstract sheets for specific nuclides or classesof data.*-Within limited resources and on a case by case basis what it considers to be
the best available data for specific cross sections for specified nuclei. Data
are primarily furnished as data abstract sheets. As the digitized cross section
library is developed, information will also be furnished in tabular or large scalegraphical form.**
On request.

Attachments (3)-Ref. 70Vel, NBS 418-Sample page fr NBS 380-Abbreviations

March 18, 1974

- 11 REF-

п.. V./ejssiere, H. Beil, R. Bargera, P. Carlos, A. Lepratre
A
NucL. Phys. Alf39, 56I (I97O)

ELEM. SYM.

82

203

Pb
REF. NO.

70 Ve 1
DETECTOR

EXCITATIONENERGY

REACTION

egf
ANGLE

G,N

ABX

7-31

7-36

BF3-I

4PI

G,2N

ABX

14-31

7-36

BF3-I

4PI

G,3N

ABX

7-36

BF3-I

G,4N

ABX

23-31
30-36

7-36

BF3-I

4PI

0.6

0.5

0.4

0.5

0.2

0.1

7 S 9 10 11 U n ' U 15 16 17 18 19 20 21 21 !i 24 2S 2b 27 28 23 20
Fig. 1. Partial photoneutron cross sections ffy.n. <*y,i*> <fy. jo. and "}.,«» of *°*Pb. We also show thedescending part of t h : unique Lorentz line giving the best fit to the experimental ffy,T(£) curve.

TABLE 5Integrated cross sections and sum rule values of 10>Pb and " T A u . The notation used is definedin trie text
Reft.

')
")
present work
•)
'"Au
')
prccr.t work

E»
(MeV)

22
23
23
25
22
2$
25

aoA
Co'
(McV • b) (McV b ) 0.06 NZ
4.10i0.06
2.91Jb0.29
3.9IiO59
3.4S£0.23
3.OOiO.O5
2.97 i 0 . 3
3.4S±0.2

s.to
2.94
5.18
4.00
3.99
3.53
4.07

1.37
0.98
1.31
1.17
I.OS
1.05
1.23

ao'A
0.06 NZ
1.71
0.99
1.74
1.34
1.40
1.24
1.42

(mb)
280

251 ± 2 0200
23S+2O(mb-McV-1)
20.5
14.1 ±1.4
18.6±2.4
19.1 ±21415.3 ±1.5
17.2±2X

J . M i l l e r , C.Schuhl and C . T z a r a , N u c l . P h y s . ^ 2 ( L 9 6 2 ) 2 3 6 .
R . R . H a r v e y , J . T . G a l d w e l l , R . L . B r a m b l e t t and S . C . F u l t z ,P h y s . R e v . _13_6 ( 1 9 6 4 ) B 1 2 6 .
9S . C . F u l t z , R . L . B r a r a b l e t t j J . T . C a l d w e l l and N . A . K e r r ,Phys.Rev. 127, (1962)1273.
23
T,Toraimasu, J . P h y s . S o c . J a p . 2 £ ( 1 9 6 8 ) 6 5 5 .
8[over]
U.S. OEPARTME^4T OF COMMERCE
NATIONAL BUREAOOP STANDARDS

- 12 -KRYPTONA

ABUND.

78
80
82
83
84
86

0.35
2.27
11.56
11.55
55.90
17.37

G,N
12.0
11.5
11.0
7.5
10.5
9.9

O.P
8.2
9.1
9.9
9.8
10.7
11.9

Z = 36YTTRIUM

SEPARATION ENERGIES IMEV)
G.T G.HE3 G.A G.2N G.NP
19.9 16.9
4.4 21.1 19.4
19.6 18.2
5.1 ¡9.9 19.8
19.5 19.6
6.0 18.8 20.1
19.1 17.2
6.5 18.5 17.4
19.4 21.С
7.1 18.0 20.3
19.2 22.8
8.1 17.0 20.9

REF

NUCLIDE REACTION RtSZ
A IN.OUT

EXCIT

69.401

36KR

G.XP

АВГ ГЬЯ- 33 С 24- 33 SCI-D

66BE2

36KR82

G.G

LFT

69HO1

36KR84G.XP

ABY ThR- 33 С 24- 33 SCI-0

1

RUBI0IUMA

ABUND.

87
87

27.85

SOURCE

С

1

DETECTORTYPE ANG MUM
90

NAI-D И З
1..777 MEV90

Z = 37

SEPARATION ENERGIES IMEV)
G.P
G.T G.HE3 G.A G.2N G.NP

6.N

G.2P
13.5
15.4
17.4
18.2
19.»
21.Î

G.2P

Vl'll "9.9I 8.6
I'l 17.1
ï?"î 21.8\ïl 8.0
e l 18.6'VI \ïl
20*5
18.5 20.5

REF

NUCLIDE REACTION RESZ
A IN,OUT

71LE1
71L61
618A2

37RB
37RB
37RB

EXCIT

SOURCE

DETECTORTYPE ANG NUM

G.N
G.2N
G.XN

ABX tl- 24 D 11- 24 MOD-I 4PI 375
ABX 17- 24 0 11- 24 MOO-I 4PI 376
ABY ThR- 22 С 22
THR-I OST

5BT01

37RB85

G.N

RLY

6OGE3

37RBB5G.N

NOX THR

10- И

69KN1

37RB85&.N

RLY

10- 45 С 45
9- 11 С 22

58TOI

37RB87

G.N

RLY

60GE3

37RB87G.N

NOX THR

57ER1
57ERI

37R887
37RB87

G,A
G.NA

ABI
ABI

С 22
CTHR

ACT-I 4PI
THRESHOLD
BF3-I 4PI
THRESHOLD
ACT-I 4P I
ISOMER YIELD
BF3-I 4PI
THRESHOLD
BF3-I »PI
THRESHOLD
ACT-I 4PI
ACT-I 4PI

CTHR

8- 32 С 32
17- 32 С 32

Z»39

A

ABUND.

89

100.00R6F

NUCLIOE REACTION RESZ
A IN.OUT

EXCIT

67SH1

39Y 89

EtE/

FMF

2-

68PE1

39Y 89

E.E/

RLY

1-

71MO3
69SH6
68AL1

39Y 8939Y 8939Y 89

E.E/
E>P
G.G

70AR1

39Y 89

G.G

58SI1
63KA2
63VE2

39Y 8939Y 8939Y 89

G.u/
G.G/
G.G/
G.N

G.N
11.5

58CH2

39Y 8960GE3

39Y 89

G.N

62RE1
63GE1

39Y 8939Y 89G.N
G.N" B " ^W* ^•'6 9 g E t

7ILEI

39Y 89n s A 1
3 ,y e ,66FU2 39Y 89
6&ИА1 39Y 89
67BE2
698F.4
70ИАЭ
7UE1
56YE2
58KA1
61BA2
66FU2
69SH4
67TA2
70WA3
68SH1
69RI 139Y 8939V 8939Y 8939Y 8939Y 8939Y 8939Y 8939Y 8939Y 8939Y 3939Y 8939Y 8939Y 8971UM1

39Y 89GiP
7.1

SEPARATION ENERGIES (MEVI
G.T G.HE3 G.A G.2N G.NP
18.1 19.9
8.0 20.3 18.2

A

ABUND.
G.N
12.0
11.5
8.4
11.1

G.P
9.0
9.6
9.4
10.6

°-N ABX TH«__^28^¡"3-Г4Р?
^
28 DTHR-

G>f|

д(}х

n

2 J

A

ABUND.

90
91
92
94
96

51.46
11.23
17.11
17.40
2.3C

REF

NUCLIDE REACTION RESZ
A IN,OUT

RLY
1С 6
ACT-I 4PI
ABX 11- 27 D 11- 27 MOO-I 4P I 378
ABX 19- 27 D 11- 27 MOD-I 4PI 379
ABY THR- 22 С 22
ТНЯ-I OSTABX 10- 27 С 10- 27 BF3-I 4PI 329

60RE!
66BE3
70AX1
67HU2
64DU1

40ZR
40ZR
402R
402R
40ZR

G.G
G.G
G.G
G.N
G.P

0.56
9.86
7.02
82.56

REF

NUCUDE REACTION RESZ
A IN.OUT

63K42
71LE1
71L£1
61BA2
70HU

3BSR
38SR
38SR
38SR
38SR

G.G/
G.N
G.2N
G.XN
G.XN

D

n

г 6

4 p f

S.N
ABX 11- 27 D 11- 27 MOD-I 4P! 381
Ц - 6 e c 10- 68 ACT-I 4PI
G.N
A B Y
G.2N
ABI ThR- 28 DTHR- 28 BF3-I 4PI
G.2N
RLY THR-280 С15Э.230 ACT-I 4PI
ISOMcR RATIO Y 87
G.2N
ABX ТНЯ- 28 OTHR- 28 3F3-I »PI1*
G.2N
ABX 21- 27 0 19- 28 MOO-I 4PI J89
G.2N
RLY THR-305 C15O-3O5 ACT-I 4PI
G.2N
ABX 21- 27 0 11- 27 MOD-I 4PI 382
G.XN
ABX 12- 23 С 24
BF3-I 4P I
G.XN
ABX 12- 22 С 12- 22 BF3-I 4PI
G.XN
ABY THR- 22 С 22
IHR-I DSI
G.XN
ABI ThR- 28 DTHR- 28 BF3-I *PI
G.P
ABX
7- 24 С 17- 24 EMU-D OST
G.XP
SPC THR- 2* С 17, 24 EMU-D 4PI
G.PN
RLY THR-305 C150-305 ACT-I 4P I
P .G
A8X 13- 15 D 5- 9 NAI-D OST
P.G
ABX 120 5
SCO-D 905=4.97-3.15 M£V
P.G
ABX 10- 11 0 2- 3 NAI-D
0

Z»40

Z-38

SEPARATION ENERGIES IMEV)
G.T G.HE3 G.A G.2N G.NP
20.2 17.9
5.2 21.2 19.8
20.5 19.5
6.3 20.0 20.1
2C.1 17.4
7.3 19.9 18.1
2C.7 21.4
7.9 19.5 20.5

8*
86
87
88

DETECTORTYPE A.4G NuH

3 0225
MAS-D DST
2.5 MEV
3 D 65. 70 MAG-0 DST
5 LEVELS
ABX
0-240 D500
MAG-D 60
SPC 10- 26 D 2J
MAG-0 UKN
LFT
2
С 4
SCD-D 130
2 = 1.51 HEVABX 12- 30 С 32
NAI-D DSTRATIO G.C-/TO 2*
ABY
2- 21 С 22
ACT-I 4PI
RLY
1
С 5
ACT-I 4PI
ABX
0- 1 D 1
ACT-I 4P I
ISOMSRS 1*1.33 MEV
RLY THR
CTHR
BF3-I 4PI
THRESHOLDNOX THR
CTHR
BF3-I 4P 1
THRESHOLD
NOX
6- 55 С 55
THR-I DSTRLY 11- 12 С 11- 12 BF3-I 4PI

ZIRCONIUM
STRONTIUM

SOURCEEXCIT

SOURCE

G.2P
14.6
16.7
18.0
19.2

DETECTORTYPE ANG NUM

G.N
12.0
7.2
8.4
8.2
7.9

G,P
8.4
8.7
9.4
13.3
11.5

SEPARATION ENERGIES (M£V>
G.T G.KE3 G.A G.2N G.NP
20.7 18.3
6.7 21.3 19.9
18.6 14.9
5.5 19.2 15.6
15.7 17.2
Э.С 15.9 17.3
15.9 18.5
3.8 14.9 17.8
16.1 20.4
4.9 14.3 18.5
EXCIT

SOURCE

62CA1

38SR86

G.N

NOX

12- 30 С 30

56YE2

38SR86

G.XN

ABX

11- 23 С 24

ACT-I 4PI
ISOMER RATIO
BF3-I 4PI

65OU1
69SH4
63MI5

40ZR
40ZR
40ZR

G.P
G.P
G,XP

63VE2

385R87

G.G/

40ZR90

E.E/

FMF

2-

3BSR87
38SR87

G.XN
G.P

ABX
0 - 1 0 1
ACT-I 4P I
ISOMERS 1=1.33 MEV
A8X
9- 23 С 24
BF3-I 4P I
ABY ThR- 20 С 20
ACT-I 4P I

69BO2

S6YE2
680*3

708E2

40ZR90

E.E/

ABX

0-

56HE3
68PE1

38SR83
3aSR88

E.E/
E.E/

FMF
RLY

69SH5
69SH6
64BE7

38SR88
38SR8838SR3a

E.P
E.P
G.G

ABX
SPC
LFT

56YE2
71BL1

38SR8S
33SR88

G.XN
G.PI*

ABX
АВУ

69HA1

38SR83P.G

RLX

7 D187
MAG-D DST7 D 65. 70 MAG-D DSTBIELI. 4 LEVELS
14- 25 D 16- 30 MAG-0 UKN
14- 30 D 30
MAG-D UKN20 2
UK«-0 UKN
2=1.85 MEV
11- 23 С 24
BF3-I 4PI
150-700 C15C-70O ACT-I 4PI
SEE 68NY1
15- 22 0 4- 12 NAI-D 90 207*68SH4

40ZR90

E .P

69SH5
69SH6
63AX1
69RA1

40ZR904CZR9040ZR9040ZR90

E .P
E.P
G.G
G.G

56AX1

40ZR90

G.N

59MU2
62CA1

40ZR9040ZR90

G.N
O.N

65COI
67BE2
71LE1
66FU2
67BE2
71LE1

40ZR9040ZR9040ZR9040ZR9040ZR9040ZR90

G.K.
G.N
G.N
G.2N
G.2N
G.2N

G.2P
15.4
16.3
17.1
18.9
21.3

DETECTORТУРЕ ANG NUM

ABX
7
0 7
NAI-D 90
RLX
5- 10 0 5- 10 NAI-D 135
ABX
8- 13 D 8- 13 NAI-0 22
ABY THR- 22
THR-I DSTABX THR- 34 С 22- 34 HAG-0 OST
Д8Х
ABX 18- 26 D 17- 24 EMU-D DST
ABX
8- 24 С 20. 24 EH'J-0 OST
ABY
8- 22 С 22
SCI-I DST

11-

G.2P
17.7

* D 58MAG-0 DST
2.18 ТО 3.84 MEV
4 D 42- 61 MAG-D DST
2.18.2."74.3.84
SPC 11-20 D 20
MAG-D 90
ANALOG STATESABX 12- 23 D 16- 24 MAG-D UKft
SPC 12- 22 D 16- 23 HAG-D DST
ABX
8- 13 0 8- 13 NAI-D 135
LFT
9
0 9
NAI-D OSI
9=8.496 Mfv
RLX 12- 23 С 12- 23 ACT-I 4PI
THRESHOLD
RLX 12- 24 С 12- 25 ACT-I 4P!
NOX 12- 30 С 30
ACT-I 4PI
ISOMERIC RATIOABX THR- 70 С 12- 70 ACT-I 4PI
A8X THR- 28 DTH3- 28 BF3-I 4P I 10*
ABX 12- 26 D 12- 26 MOD-I 4PI 384
A8I THR- 28 ОТНЯ- 28 BF3-I 4P1
ABX THR- 28 ОГНЯ- 28 BF3-I 4P! 10*
ABX 21- 26 D 12- 26 MOO-I 4Pt 385

Abbreviations Used in Photonuclear Data Index

EXCIT

Excitation energy of specified nuclide for whichdata are given

RES

Result of measurement, type of information

ABI

absolute integrated cross-section data JadE

ABX

absolute cross-section data

AB7absolute yield data

FMP

form factor

LFT

excitated state lifetime

NOX

no cross-section data

RLI

relative integrated cross-section data

K.X

relative cross-section data

RLT

relative yield data

SPC

photon or particle energy spectrum

- 14 CPX D A T * CENTER COMPUTER IASED FILES
THERE ARE THREE COMPUTER BASED H U E S WHICH EXJST AT THE CPX DATA
C6NTgR- THESE ARE THE .".ABSTRACT FILE..V THE , .GROSS SECTION DATA F I L E , ,AND THE i,REACTION LIST F J L E - 7 . OF T H E S E . ONLY THE LATTER IS MAINTAINED ON
A CURRENT B A S I S , ALL THREE O F THE FILES EXIST ON C A R D S . COMPUTER LISTINGS
AND MAGNETIC TAPE,
AT THE PRESENT TIME Tf»E REACTION LIST FILE IS KEPT UP TO DATE WITH
THfe E X P E N D I T U R E OF ONLY O t 5 MANPOWER BY F, K, MCGOWAN, A PLAN IS BEINGC O N S I D E R E D IN WHICH THIS rlL"E WILL BE EXTRACTED FROM THE SAME LITERATURE
SCAN WHICH P R O D U C E S ,,RECENT REFERENCES', ,• THIS PLAN WOULD PROBABLY REQUIRESCME ADDITIONS TO THE NUCLiAR DATA GROUP.S KiY WORD LIST BUT THIS SHOULD
NCT BE A SERIOUS PROBLEM. TwE TWO MOST IMPORTANT PROBLEMS ARE TRAINING A
SCANNER TO COVER SOME ADDITIONAL MATERIAL AND GETTING THE COMPUTERPROGRAMMING DONE E F F I C I E N C Y . IT IS NOT CLiAR WHEN THIS PLAN CAN BE FULLY
IMPLEMENTED WITH THE MANPOWER THAT IS AVAILABLE.
REACTION LIST FILE
THE REACTION LIST FiLg TS ESSENTIALLY COMPLETE. WjTHIN THE SCOPEOUTLINED IN THE CURRENT SUPPLEMENT (SEE THE INCLOSED REPRJNT), THE EXACT
COVERAGE IS.
Z • T AND Z • 2 (H AND HE)
Z • 3 THRU 2 • 99 (LI THRU Es>
CCULflMB EXCITATIONANALYSIS

MAY 1969 • JUNE
1948 • JUNE
1956 - JONEJULY |97Q • JUNE

MOST OF THE ENTRIES FOR THI JULY F 973
STOR E D ON TAPE.

-

JUNE

1973
1973
1973
1973

|97*

SUPPLEMENT

ARE

ALSO

EACH ENTRY CONTAINS THE TEXT MATERIAL (REACTION, PROJECTILE ENERGY,QUANTITY MEASURED AND REFERENCI) GIVEN IN THE PUBLISHED LIST AS WELL AS THE
iNDEy PARAMETERS DEFINED IN THE SECTION ON FILE STRUCTURE BELOW; OUR
PROGRAMS INCLUDE ROUTINES FflR RETRIEVAL AND ORDERING ON THESE INDICES AS
WELL AS RETRIEVAL AND O R D E B I N G ON AUTHORS NAME, JOURNAL, VOLUME, PAGE AND
YEAR (A SUPPLEMENT TO TME REACTION LIST IS PUBLISHED ANNUALY, ALL OF THE
EARLIER ISSUES ARE LISTED UN T H E INTRODUCTION OF THE 1972 . 1973 SUPPLEMENT(PAGg 5 0 | ) , TO DATE THE FIHE CONSISTS OF ABOUT 3 3 Q 0 0 R E A C T J O N ENTRIES FROMseME Hooo PAPERS* THE C§MPL§TE FILE CAN B§ CONTAINED ON ONE 9-TRACK, 800
BPI, BCD TAPE.
SERVICES PROVIDID
SINCE T ME REACTION tslsT FILE APPEARS IN THE OPEN LITERATURE IN IT7SENTIRETY AND IS UPDATED ANNUALY, MOST OF THE SERVICE PROVIDED INVOLVESFINDING REFERENCES AND SOMETjMfS D A T A FOR PE«PLE WHO DO NOT CURRENTLY HAVEACCESS THESE PUBLISHED UlsTs, WE HAVE ALSO PRODUCED SPECIAL LISTS OF
R N
TYPgS OF ENTRIES AND H A V E SUPPLIED PIRT OR ALL OF THE FILE ON TAPE,

- 15 REACTION LIST FfLE STRUCTURE IND DEFINITIONS
C
C

C
C
C
C
C
C
C
C
C
C
C
C

c
c
c
c
c
c
c
c
c
c
c
c
c
c
c
c
c
c
c
c
c
c
c
c
c
c
c
c
c
c
c
c

FORTRAN REQUIRED FOR RgAfllNG ONE REACTION LIST ENTRY
DIMENSION I N D X ( | I ) , R * C T < T O | 3 o > , R E F ( 2 0 )REAL'S RACT.REF
REAO(|,20tEND"200)INfiX l NViICNFORMAT(12,IX # 4(2x,l3»I3),5x,l2,4x ; J|fl,IX # l2,8X,l6)
READ< l|3o,END«2oO)((iAcTfK,J),K«|,lO)*U«liNV>
lr0RMAT< !0A8>
READ(|,38
DEFINITIONS(CN IS OUR SYSTEN ID Nfl.
NV IS THE NO, OF ViLJNgST. IN THE ENTRY (NOT INCLUDINQ REF)
RACT CONTAINS THE REACTION, ENERGYi QUANTITY MEASURED* ETC,
RET CONTAINS THE REFERENCE
(NDX(
[NDX(
INDX(
INDX(
INDX(
INDX(
INDX(
INDX(
INDX(

I)

2)
3)
4)
5)
6)
7)
8)
9)
10)
INDX( I I)DATA TYPE(SPECIFIC VALUES GIVEN BELOW)Z.TARGETA-TARSETZ.PROJECTiLE
A.PROJECTILE
Z-OUTSOINS
A.OUTGOINGZ«RESlDUAb!
A-RESIDUAH
REACTION TiVpE (SPECIFIC VALUES GIVEN BELOW)PROJECTILE gNgRQY IN KEVI3ATA TYPE

Oj DENflTiS DATA NOT PLITTED (OBSOLETE TYPE)
02 DENOTES ISOLATED VALUES (VALUE INCLUDED IN ENTRY)
03 DlNoTfS Hl-ENERQY CROSS SECTION DATA
04 DENoTlS ENERGY SPECTRA
09 DiNQTBS ANGULAR CflRBELATION DATAO« DlNeTfS RELATIVE DATA
07 D I N Q T B S TABULAR DATA (IN PAPER OR OUR FILES)
08 DiNoTfS COULOMB EXCITATION DATA
09 DENoTgS ANALYSIS (THEORY)

REACTION TYPE

00 DENoTgS ELASTIC SCATTERINQ
01 DINgTlS INELASTIC SBATTER1NQ
02 DlNoTiS TARGET • PRIJ (INCOMPLETE SPECIFICATION)
03 DtNoTiS DEFINITI REICTION (COMPLETE SPECIFICATION)
04 DfNoTfS POLARIZATION <ELASTJc)
05 DlNoTlS POLARIZATION (INELASTIC)
06 DENOTES TOTAL REACTION CROSS SECTION
07 DENOTES POLARIZATION (REACTION)
08 DENOTES FISSION
09 DENOTES SPALLATION
10 DENoTBS COULOMB EXCITATION

i,REACTION TYPE,i ANB ,,BATA TYPE,. ARE OPEN ENDED AND OTHER TYPES*AY BE AIDED AS THE NEED ARISES,- 16 DROSS SECTION DATA FILE
THE CROSS SECTION DATA rILE IS NOT COMPLETE IN ANY SENSE AND NO DATAHAVE BEEN ENTERED SINCE 1969, THIS FILE CONTAINS ABOUT I|OQQ I I D A T A SETS,,WITH A TOTAL OF SOME 3 Q O « O O Q " D A T A POINTS,,! MUCH OF THE DATA IS FOR
ELASTIC AND INELASTIC SCATTiERlNQ, POLARJZATUN AND TOTAL CROSS SECTION VS
ENERGY MEASUREMENTS, SOME STRIPPING AND PICKUP DATA ARE INCLUDED §UT THESEDATA ARE NOT AT ALL COMPLETE EVEN FOR THE PERIOD COVERED,SOME OF THE DATA IN T H IS FILE HAVE BE|N PUBLISHED AND A SAMPLE FROM
THE LAST PUBLICATION WHICH INCLUDES A LISTING Or ALL PREVIOUS PUBLICATIONS,THE INTRODUCTORY MATERIAL AND A COUPLE OP SAMPLE PAGES IS ATTACHED, THE
CCNTgNTS AND STRUCTURE OF TJHe FILE ARE DESCRIBED IN MORE DETAIL IN THE
SECTION ON FfLE STRUCTURE AND DEFINITIONS BELOW, ALL OF THE DATA CAN BE
CONTAINED ON ONE 9.TRACK, 8Oo BPI» BINARY TAPE,SBRVICES PROVID1D
ALTHOUGH THE FILE IS NOT MAINTAINED ON A CURRENT BASIS, ME DOf
To ANSWER SOME REfiUESTS FOR CROSS-SECTION D*TA, MOST OF THE
REQUESTS ARE FROM INDIVIDUALS IN THE MEDICAL',' C O N T R O L S THERMONUCLEAR,SPACEOR OTHER APPLIED F I I L Q S . IF THE REQUESTS ARE SPECIFIC AND LIMITED IN
SCOPe. WE USUALLY SUPPLY TiE D A T A IN HARD COPY FORM, WE HAV§ SUPPLIED THE
COMPLETE H L 6 ON MAGNETIC TiApE? HOWEVER,CROSS SECTI9N FfLE STRUCTURE AND DEFINITIONSCCCFORTRAN REQUIRED FOR RgAfilNG ONE CROSS SECTION DATA SETDIMENSION NUNDX(|3),ZEQC(7),TtTLE<|20)»XA(5oQ>,XB<5Qo>,VA(5oo>«
IYB<500)
REAL'S TITLE

C
C
C
C
C
C
C
C
C

c
c
c
c
c
c
c
c
c
c

READ( I ) f C N , N U N D X 7 Z E f i C , N T , < T l T | , , E ( l ) , ! • * , N T ) ,lNE»<XAU>»XB<I),YA(I>,YBr M i i * l i N I >DEFINITIONSICN IS OUR SYSTEM ID NuMgER
NT IS THE NUMBER OF W O R D S IN TITLE
NE IS THE NUMBER OF BAjA POINTS IN THE DATA SETNUNDX(|)
NUNDX(2)NUNDX(3)NUNDX(4)NUNDX<5>
NUNDX(6)NUNDX<7)
NUNDX(S)NUNDX(9)NUNDX(IO)
NUNDX<I|)
NUNDX(|2)

DATA TYPE (ALMAYS SET TO f IN THIS DATA)Z.TARGETA-TARGET
Z-PR0JECTDL6
A-PR0J6CTJL6
Z-OUTGOINfi
A-OUTGOING
Z-RESIDUAL
A-RESlDUAb!
REACTION iDYpE (YOU PROBABLY SHOULD NO? TRY TO USE)
ENERGY IN K E V (IF E,GT.9999IQOOKEV) E*99998ooOKEVXLABL INDIX

С
С
С
С
С
С
С
С
С
С
С
С
С

С
С
С
С
С
С
С
С
С
С
С
С
С
С
С
С
С
С
С
с
с
с
С

с

- 17 NUNDX<|3)« YLABL INDEXNUNDXC|2)«|» 2, 3 DENOTES THETA-C.M.i Ï-LAB, THETA-LAB
NUNDX<|3)«| DENOTES B S I G M A / D O M E Q A (ТИЕТА-СМ) (HB/STR)
NUNDX<|3)«2 DENOTES 3 I Q M A ( E - L * B )(MB)NUNDX(|3)-3 DENOTES DSIQM*/DSIQMA-R
NUNDX(|3)«4 DENOTES BOL(fHETA-CM)(PER-CiNT)NUNDX(|3)»5 DENOTES B O L ( I - L A B )(pER'CgNT)
ZEOC( |)«A»PROJECT!LEZË0C(2)MsTARGET
ZE0C(3)»*e0UTG0INQ,¡EXACT,,, .EXACT,,..EXACT,,

ZEQC(4)*AeRESlDUAL>7EXACT,i
ZEQC(3>»E«LAB <MEV>ZEQC(6)>0 OF REACTION (MfV)
ZEaC(7)«RUTHERrORD CiEfF
THETA IS ALWAYS IN D E 6 R E | S
E-LAB IS ALWAYS IN MIVPOL IS ALWAYS IN PER CgNT

XA(I)>THE ITH VALUE SF THE QUANTITY SPECIFIED BY *l*BL
YA(I)«THE ITH VALUE 9F ТнЕ QUANTITY SPiCIflED BY YLABL
I.E. X A I l b Y A ( l ) , ARE THE DATA P0JNT8XB(I)>THE UNCERTAINTY jN XA
YB<I)«THE UNCERTAINTY IN YA
THE FIRST 72 CHARACTiRs OF TITLE (9 WOIDS) CONTAIN THE REACTION
AS WELL AS SOME 0THE8 !N?ORMATJON (SHOKN ON THE DATA FORM)i
THE REFERENCE AND COMMENTS ARE CONTAINER IN WORDS I O THRU NT,
THE REFERENCE IS TERMINATED BY A S, COMMENTS FOLLOW THE S,DATA WHICH HAVE BEEN PROCESSED FROM TABLES ARE OFTEN INDICATED AS
SUCH IN THE COMMENT

- 18 ABSTRACT FILE
THIS FILE (GENERATED FOR IN HOUSE USE) PRECEDED THE REACTION LIST
FILE AND IS NO LONGER MAINTAINED. IT HAS A STRUCTURE SJMLLAR TO THE
REACTION LIST FILE BUT IT MAS NOT SO CAREFULLY DONE OR WILL INDEXED AND
DOES NOT CONTAIN AS MUCH INFORMATION, IT DOES CONTAIN SOME ^ 0 0 REACTION
ENTR|ES FOR ZeTARGET • f AND 2 FOR THE PERIOD PRIOR TO MAY f969, AT WHICH
TIME THESE NUCLEI WERE FIRST INCLUDED IN THE REACTION LIST,

- 19 -CHARGED-PARTICLE CROSS SECTIONDATA CENTER
Dateis and T i t l e s of P u b l i c a t i o n s ;Nuclear Cross Sections for Charged-Particle-Induced Reactions - Mn, Pe,
Co, ORNL-CPX-1 ( J u l y 1964), compiled "by F.K. McGowan, W.T.Milner, and
H.J. Kim. Available on request to the Charged-Particle Cross-Section
Data Center, Oak Ridge National Laboratory, P.O.Box X, Oak Ridge,
Term.. 37830.
Nuclear Cross Sections for Chaxged-Particle-Induced Reactions - Ni, Cu,
0RNL--CPX-2 (September 1964), compiled by P.K. McGowan, W.T. Milner,and H.J. Kim. Available on request to the Charged-Particle Cross-Section
Data Center, Oak Ridge National Laboratory, P.O.Box X, Oak Ridge Tenn.37830.
Nuclear Cross Sections for Charged-Particle-Induced Reactions - Li,Be,B,
compiled by H.J. Kim, W.T. Milner, and P.K. McGowan, Nuclear Data Al,
203-389 (1966), i s s u e s 3 and 4 combined $ 6.00; Academic P r e s s , 111 F i f t hAvenue, New York, N.Y. 10003.
Nuclear Cross Sections for Charged-Particle-Induced Reactions - C,compiled by H.J. Kim, W.T. Milner, and F.K. McGowan, Nuclear Data A2, 1-241( i 9 6 0 ) , i s s u e s 1 and 2 combined $ 6.00, Academic P r e s s , 111 F i f t h Avenue,
New York, N.Y. 10003.
Nuclear Cross Sections for Charged-Particle-Induced Reactions - N and 0,
compiled by H.J. Kim, W.T. Milner, and F.K. McGowan, Nuclear Data A3,
123-^86 (1967).
Reaction L i s t for Charged-Particle-Induced Nuclear Reactions, Z = 3 toZ = 27, 1948 - April 1969, compiled by F.K. McGowan, W.T. Milner, H.J. Kim,
and Wanda Hyatt, Nuclear Data A6, 353-648 (1969).
Reaction L i s t for Charged-Particle-Induced Nuclear Reactions, Z = 28 t o
Z = 99, 1948 - April 1969, compiled by F.K. McGowan, W.T. Milner, H.J.
Kim, and Wanda Hyatt, Nuclear Data AJ_, 1-232 (1969).
Reaction L i s t for Charged-Particle-Induced Nuclear R e a c t i o n s , Z = 1 t o
Z = 98, May 1969 - June 1970, compiled by F.K. McGowan and W.T. Milner,
Nuclear Data ^199 - 322 (1970).
Reaction List for Charged-Particle-Induced Nuclear Reactions, Part I: Z = 1
to Z = 98 (H to Cf), July 1970 - June 1971, Part I I : Coulomb Excitation
1956 - June 1971, F.K. McGowan and W.T. Milner, Nuclear Data Tables A9_,469 - 626 (1971).
Reaction List for Charged-Particle-Induced Nuclear Reactions, Z - 1 to
Z = 99 (H to Es), July 1971 - June 1972, F.K. McGowan and W.T. Milner,
Nuclear Data Tables AU, 1 - 126 (1972).
Charged-Particle Reaction List 1948-1971, F.K. McGowan and W.T. Milner,
Atomic and Nuclear Data Reprints Vol. 2, Academic Press 1973*
Reaction List for Charged-Particle-Induced Nuclear Reactions, Z • 1 to
98 (H to Cf), July 1972 - June 1973, F.K. McGowan and W.T. Milner,
Atomic Data and Nuclear Data Tables 12,, No. 6 (1973).

- 20 -

Computerized Libraries of Nuclear Data
S. Pearlstein
March 1, 1974

The use of nuclear data in applications is facilitated if the data are in
the form of a computerized library. A library in this form can be more widelydistributed, fewer processing codes need be written, and results may be more
readily compared. Format extensions to include non-neutron induced reaction
data in the Evaluated Nuclear Data File (ENDF) were approved by the Cross Section
Evaluation Working Group December 12, 1973. Comments are sought on the adequacyof the trial format for all significant data but in particular charged particle
reaction data. An ENDF tape of charged particle data in the trial format has
been generated for over 250 nuclides using nuclear systematics.
The ENDF formats have been used for neutron-induced reactions, photoninteraction, and radioactive decay data. These formats are described in ENDF 102
Vol. I (BNL 50274) and Vol. II (LA-4549). Although the ENDF formats were originallyconstructed for neutron-induced reaction data important to reactor applications,the mathematically oriented modules in many cases can be used to store other datatypes as well. Since many users of nuclear data are already equipped to process
neutron data files, minor modification of existing well known formats will
facilitate the storage, retrieval, display, evaluation, processing, and exchange
of non-neutron data. At the National Neutron Cross Section Center, the placementof experimental charged particle data in the generalized EXFOR system, used to
exchange data between the world neutron deta centers, eased the production ofan evaluated data set. The following material has been included to show theadaptability of these formats to charged particle data:
Enclosure 1 - Experimental charged particle data in generalized EXFOR.
Enclosure 2 - Evaluated charged particle data in the trial ENDF format.
Enclosure 3 - Graphs of evaluated (p,n), (p,2n), (p,3n) reaction datausing an ENDF plotting package.
Enclosure 4 - Partial list of charged particle reaction parameters
obtained from nuclear systematics.
Enclosure 5 - Trial ENDF format description (Also refer to ENDF-102).
A good starting point for the production of evaluated charged particle data
sets in computerized form are the extensive bibliography and data indexes suchas those compiled by the Charged Particle Information Center at Oak Ridge but
the assembly of carefully documented evaluations will take time. An ENDF tapeof charged particle data generated from nuclear systematics as described in
Enclosure 4 may be a useful first iteration of a computerized library. In somecases Bystematics will be notably deficient and these data sets should be replacedby improved evaluations as they become available.
I would appreciate comments about the trial ENDF formats. I would also bepleased to answer requests for the charged particle reaction data tape.

- 21 Enclosure 1
1
190012P1
740301
19001
53
19
J9C01
2
(P,XN> AND <P,PXN> REACTIONS OF YTTRIUM-89 WITH 5-89 19001
3
MEV PROTONS
19kJ01
4
5
AUTHOR(G.B.SAHA.N.T'.'PORILE.L.JAFFE)
3 9kC01
6
INSTITUTE ( 1 C A N M 0 O MCGlLl UN!VERSITY.KONTREAL.OUEBEC
19801
7
(
REFERENCE(J,PR, 144 , 962,6604 )19L 01
6
V
STANDARD(29-CU-63,P»N> S .N.CHOSHAL,PR•00,939.5000
19*01{29-CU-65,P«NP> S.MEGHIR.L.YAFFE,UNPUBLISHED
a 91- 01
10
PART-DET(N) NEUTRONS
J 9fcP9i
11
FACILITY(SYNCY)-MCGILL SYNCHROCYCLOTRON
19201
12METHOD(CHSEP) CHEMICAL SEPARATION AND POSITRON COUNTING
19001
13
DETECTOR(SCIN) TWO NA!<TL> COINCIDENT DETECTION OF 511 KEV
19001
14
ANNIHILATION GAMMA RAYS.
19*01
15
CRR-ANALYS UNCERTAINTIES INCLUDE RANDOM ERRORS ASSOCIATED WITH THEJ9SJ01
16
DETERMINATION OF PHOTO PEAK AREAS,DECAY CURVE ANALYSIS.19201
17
CHEMICAL YIELDS* AND SYSTEMATIC ERRORS ASSOCIATED WITH 19ki(?l18
COUNTER EFFICIENCIES AND SPREAD IN BEAM ENERGY, NO
19001
1.9
ERRORS IN REFERENCE CROSS SECTION OR DECAY SOHEMES WEREi9k)01
20
INCLUDED. RANDOM ERROR FROM SCATTER OF DATA IS MUCH
j"9io01
21
SMALLER THAW TOTAL ERROR WHICH RANGES 11-22 PERCENT.
19001
22
ENDBI8
S9
19001
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NOCOMMON
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ENDSUSENT
2219001 2
1
19021 0C2
740301SUBENT
19*01 22
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1
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- 22 -

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Enclosure 2
0 0 0
CHARGED PARTICLE 0>TA IN THE ENOF FORMAT
49001 1451
030389.
0
0
09001 1451
8
3.0
e.e
a
0
90C1 1451
YTTRIuM-89
EVALUATED 1974 BY S.PEARLSTEIN (BNL)
9001 1451
PRIM. REF.-PHYS, REV, 144(1966)962 SAHA, PORILE, AND JATFE
9001 1451
OTHER (P.XN) DATA AGREE TO ABOUT 60 PER CENT,
9001 1451
NO INDIVIDUAL. PARTICLE LEVEL EFFECTS INCLUDED,
9001 1451
0 VALUES-NUC,' DATA A9 (1971 )267,. WAPSTRA AND .&OVE'.
90(31 1451
DATA NEAR THRESHOLD CALCULATED FROM SYSTEMATICS OF
9021 1*51
KFK-747, LANGE AND MUNHEL. MODIFIED BY PEARLSTEIN
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FOR NUCL, POTENTIAL EFFECTS AT LOW ENERGIES,
9001 1451
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Annotated.listing appears on next page.

2.

Format description appears in Enclosure 5 and EMDF-102.

0
1
2
3
4
5
6
7
8
9
10
11
12
13
14
15
16
17
18
19
20
21
22
23
24
25
26
27
28
29
30
31
32
33
34
35
36
37
38
39
40
41
42
43
44
45
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47
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49
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ENDF/B HAT NO. 1CO1

CROSS SECTION

ON

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ENDF/B MAT NO. 1001
CROSS SECTION"T—i

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(TIMES 10

8.00

- 28 -

Enclosure 4(P,N)

REACTIONPEAK

NUCLlDE

23-V - 49
23-v - 52
23-V - 51
24-CR- 52
24-CR- 52
24-CR- 53?4-CR- 54
25-MN- 53
25-^N- 54
25-MN- 55
26-FE- 54
26-FE- 53
26-FE- 56
26-FE- 57
26-FE- 59
26-FE- 62
27-C0- 57
27-CO- 59
27-C0- 6e
28-NI- 58
28-NI- 59
28-NI- 62
28-NI- 61
28-NI- 62
28-NI- 63
2 8 - M - 64
29-CU- 63
29-CU- 63
30-ZN- 64
30-ZN" 65
3B-2N- 66
30-2N- 67
30-ZN- 68
30-2N- 72

Q(KEV)

ENERGY
(MEV)

XSECT
(B)

-3.35
0.26
-1.53
-8.41
-5.49
-1.36
-2.16
'4,53
-0,09
-1.01
-9.03
-4.24
-5.39
-1.62
-3.09
-0.56
-4,(33
-1.86
2,04
-9,38
-5,58
-6.91
-3.03
-4,74
-0.72
-2,44
-4,15
-2,13
-7,95
-4,04
-5.96
-1.78

11,1
7.4
9.2
16,4
13,4
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10.0
12,5
8,0
9,0
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12.4
13,5
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11.2
8,6
12,3
10.1
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14.0
15.3
11,4
13.1
9,0
10.8
12.6
10.6
16,6
12.6
14,5
10.3

4.2-1
4,2-1
4.2-1
4.5-1
4.5-1
4,5-1
4.5-1
4,7-1
4.7-1
4.7-1
4.9»1
4.9-1
4.9-1
4,9-1
4,9-1
4.9-1
5.0-1
5.0-1
5.0-1
5.2-1
5.2-1
5.2-1
5.2-1
5.2-1
5.2-1
5.2-1
5.3-1
5.3-1
5.5-1
5.5-1
5.5-1
5.5-1
5.5-1
5.5-1

-3.7a

12.2
9,9

AVERAGE XSECT<B)
EVAPORATION SPECTT»5 MEV T"I0 MEV
2.1-1
2.5-1
2.4-1
1.1-1
1.7-1
2.4-1
2.3-1
1.9-1
2.5-1
2.5-1
9.9-2
1.8-1
1.6-1
2.3-1
2.1-1
2.4-1
1.6-1
2.2-1
2.3-1
8.8-2
1.5-1
1.2-1
2.0-1
1.6-1
2.3-1
2.1-1
1.7-1
2.1-1
1.0-1
1.7-1
1.3-1
2.1-1
1.7-1
3.1-1

1.9-1
1.7-1
1.8-1
1.6-1
1.7-1
1.8-1
1.8-1
1.8-1
1.7-1
1,8-1
1.5-1
1.7-1
1.7-1
1.7-1
1,7*1
1.7-1
1,7-1
1.7*1
1.4-1
1,3-1
1.6-1
1,5-1
1.6-1
1.6-1
1.6-1
1.6-1
1.6-1
1.6-1
1.4-1
1.5-1
1.5-1
1.6-1
1.5-1
1

1.

PARTIAL LIST OF MJCLIDES ON ENDF CHARGED PARTICLE TAPE,

2.

DATA EASED -ON PARAMETERIZATION OF THE SYSTEMATICS OF
KFK-767. LANGE AND MUNFCL, MODIFIED BY PEARLSTEINFOR NLCLEAR POTENTIAL EFFECTS AT LOW ENIRGIES.

3.

Q VALUES FROM NUCLEAR DAT A A9<1971)267, MAPSTRA AND COVE.

Enclosure 5

Format Modification: 73-9
Proposer! Non-Neutron Data Subcommittee

Date Approved: 12/12/73(as "Experimental").AtfectedFlles: 51-91

Purpose;

PurposeIt is desirable to expand the ENDF/B formats to include reactions relating toneutron physics and other applications such as fusion and space shielding
studies. The major types needed are charged particle induced reactions
arising in neutron source reactions, other inverse neutron reactions andreactions arising from intense charged particle fluxes produced by reactor,
outer space, and common accelerator sources. It is also necessary to specify
which secondary particle is designated in angular and energy distributions.
The solution proposed allows these data to be included with the following
advantages:
1.

No changes are required to existing neutron induced data
formats.

2.

The same MAT no. is used for both neutron and non-neutron
induced data. This is desirable since ENDF/B should contain only one MAT per target material.

3. Where appropriate, the same MT numbers are used for bothneutron and non-neutron data.
4.

No changes are required to codes processing the neutron data
files. If the non-neutron data files are merged with theneutron files only minimal changes are required to some ofthese peripheral codes.

Proposed solution
Files 62-67 and 72-76 would be used in analogy to Files 2 -7 and 12-16 (Add
60 to the present MF Nos.). Formats for data uncertainties will be containedin Files 82-87 and 92-96 In analogy to Files 32-27 and 42-46.

It

MT numbers plus new ones as required would designate the exit
channel(s). The exceptions would be MT « 1, 2, 3, and 4 where
the exit channel would be taken the same as the entrance
channel.*2.

Field 6 of the HEAD record is blank for all Files according to
ENDF 102, Volumes I and II. This field will specify the ZA as
1000*Z+A of the incident particle (1ZA) as a fixed point number.
An IZA of 0 will designate a neutron induced reaction. Other
IZA's are:Incident Particle
gamma
betA minus
beta plus
protonIXA1111 (defined)
-1000
1000
1001

deutorontriton
He-3
alpha

1002
1003
2003
2004

C-12

6012

0-16
8016
S-32
16032
IZA's for molecules and strange particles can be invented as needed.
3.

An MT number is repeated for as many sections as there are Incident
particles for which data arc specified. The convention is followedthat MT numbers are arranged in order of ascending ISA. ERDF/B
tapes can be supplied that do not contain merged neutron andnon-neutron f i l e s .
According to ENDF 102 field 5 of the HEAD record is blank for all
Files except File S for which Field 4 Is blank. It is proposed that
this field contain J'AA, the 1000*2+A of the particle designated in
the angular or energy distribution following the same code as described above.

*MT=4 would continue to equal the sum of MT=51,52...,91. New MT's 800-819 would
be defined to describe ( x , n o ) , ( x , n i > . . . ( x , n ^ g ) , ( x f n c ) , were x represents theincident p a r t i c l e . MT«*15 would be used to define the t o t a l (x,n) cross section.
Thus, for proton induced reactions f i e l d 6 of the HEAD record would contain1001 and (p,p') t o t a l would be described by MT=4, (p,p*) to discrete s t a t e s andthe continuum by MT=51--91, (p,n) t o t a l by MT*15, and (p,n') to discrete s t a t e s
and the continuum by NT=800-819. NT-15 and MT-800-819 cannot be used forneutron-induced reactions.

- 31 -

5.

The structure of Kilo 1 would bo changed to include I2A and J2A
in the dictionary. The CONT record for a non-neutron data
section would contain JXA and l'AA as floating point numbers intlic first and second fields, respectively, so as to maintain theorder in which I hey npprnr on the I IE AD card of each section.

6.

lite structure of Kile 62 could be constructed analogous to neutron
induced widths with (lie incident particle designated as in item 4
and resonance energies, widths, and other data defined by new
formats and procedures to be specified at a later time.

7.

Photon-induced nuclear reactions arc to be handled in the same
way as other non-neutron induced reactions. The word atomic should
be added to the definitions for MT-501, 502, and 504 andMF - 23-26. MT - 518, 532 and 533 should be cancelled.

ExamplesThe •tructurc of File 1 of a MAT containing Kile 3 Elections for (n,np), (n,and File 63 (p,V) data and a File 4 section for (n,np) outgoing portion angular
distribution data only isrZA.,LRP,LFI,0,NXC]lEAD[0.0,0.0,LDD,LFP,NWD,O/ll(N)JUST[MAT, 1,451,0.0,0.0,1,451,NCI,O.lCONT[MAT, ,451,0.0,0.0,3,2H,NC2,OjCONT[MAT, ,451,0.0,0.0,3,102,NC3,0]CONTI MAT, ,451,0.0,1001.0,63,102,NC4,0|CONT
TMAT, ,451,1001.0,0,4,2H,NC5,OjCONT
TMAT, ,(),0.0,(>.0,0,0,O,O|SKND

The structure of File 63 containing (p,y) data i s
MAT,63,MT=102/ZA,AWR,LIS,0,IZA«100]HEAD.MAT,63,MT-102/T,Q,LT,0,NR,NP/Eint/a(B)]TABi
MAT,63,0/0.0,0.0,0,0,0,OJSENDThe structure for File 4 containing (n,np) and File 64 containing(p»P°0 angular distribution for the emerging proton is[MAT,4,Mr-28,/ZA,AWT,LVT,LTT,JZA-1001,0]HEAD[MAT,4,0/0.0,0.0,0,oisEND[MAT, 64 ,M>112/ZA ,AWR,LVT ,LTT, JZA-1001, 1 Z A - 1 0 0 I ] H E A D[MAT,64,O/O.O,O.O,O,O,O,O]SEND

- 32 -The differential clastic distributions would be rationed to Rutherford
scattering. Angular distributions for inelastic scattering and reaction
data integrate to unity.
The structure of File 5 containing both (n,np) and File 65 containing energy
distribution data for the emerging proton is[MAT,5,MT«28/aA,AWK,O,Ji4A-1001,NK,o]lIEAD[MAT,5,O/O.O,O.O,O,O,O,O]SKND[MAT,65,MT=112/ZA,AWR,O,JZA-1001,NK,IZA-1001JHEAD[MAT,65,O/O.O,O.O,6,6,O,O]SEND
The structure of Flic 6 would follow the rules for File A.
Limitations
Simple additional tests would be required- to DICTION and RIGEL and dictionary
expansions made to the display codes. KIGEL can be modified by the NNCSC to output only neutron data files or only neutron and gammn files, etc. There would
be no limitation to the user receiving an ENDF tape containing only neutroninduced reaction and gansna-Kmn«a interaction data. This will probably be thenormal distribution recommended by CSEWC. However, for those users requiringother types of data these may be included in the ENDF system with a minimumof modification to formats and processing codes.

- 33 -

Generalized EXFOR Isoquants*)

Action 33 on NDS from Ninth Four Center Meeting(Moscow, June 1973)

There have been no detailed comments on generalized isoquants
as requested in action 32. A comment on possible structure can befound in Memo 4C-2/41, page 12. Therefore we do not consider this
discussion as a proposal. We think that the alternative solutions
presented here are capable of handling all types of reaction data.
NDS definitely favors "Solution II". We would like comments from theother centers on the various methods and on implementation,, so that
we may prepare a final proposal by March 1.

The key problem to be faced is the method whereby information
about the incident particle is provided in the isoquant construction.
In the past this has been "neutron" by default or "no particle" in a
few cases like spontaneous fission. Ve will examine two possible
solutions.

Solution I.
Construct additional mnemonics for the quantsfield which includes the incident particle.
Examples

T0T
NF
N2N

Advantage

PTOT DTOT, GTOT etc.
PP, GF, DP etc.
P2N, G2N} D2N etc.

l) No change is required in the present
EXFOR system.

Disadvantage

1)

Works nicely only if incident particle hasa simple representation like neutron (N) }proton (P) etc. What happens with LI-6
incident particles ?

2)

Dictionaries 10 and 14 will become long,repetitious and difficult to work with,

3)

Inconsistency of nomenclature in thatsome quantities will remain which havean assumed but not explicit first character N
like TOT instead of NTOT.

4)

Related to the first disadvantage is thefact that quantities representing multiple
outgoing particles will be extremely complicated.

Solution II.
Separate field for incident particle and reconstructed
quant-field. (Currently used in WRENDA.)* reproduced from Pour Center Memo 4C-3/93

- 34 -

ExamplesAdvantage

Z-S-A, N,TjZ$T
Z-S-A,N,F
Z-S-A,N,2N

Z-S-A,P,T0T etc.
Z-S-A P F
Z-S-A,P,2N

1)

Incident particle separated and clearly
identified with a field. Instead of theparticle (N or P) a full (Z-S-A) could"be given thus handling heavy particles
automatically.

2)

No more than normal increase in
Dictionaries 10 and 14.

3) Disadvantage four of the previous solution
remains but could be fixed as discussed
below.
Disadvantagel) Basic incompatibility of modifications
with all previously compiled EXFOR entries.
This leads to complications in processing
programs allowing them to handle bothversions simultaneously.

Adoption of this solution would seem to require the violationof one of the cardinal rules of EXP0R} namely "no changes to previously
compiled entries can be required". Hans Potters mentioned at theFour-Center Meeting that an automatic machine modification of theisoquant field of old EXFOR files could probably be done with reasonable effort. Pamela Attree is not so sure of the "reasonable effort",
she thinks there are complications, perhaps unforeseen by Hans Potters,
at centres where the internal files are kept in an EXFOR-like format,
complete with the ID-field.

Finally, there is the point that was suggested in Hans Potters'
memo to separate the final particles in the quant-field with a slash as
Z-S-A,N,P/N

to meanand thus generalized to
Z-S-A,N,Z1-S1-A1

It should be noted that a slash <Ls currently used with a different
meaning in the isoquant fields. Perhaps a different character fromthe permitted character set should be used instead. This proposal
seems reasonable if we ever plan to compile data representing heavy
particles in the exit channels and should be implemented simultaneouslywith Solution II if that option is selected so that major perturbations
are made only once.

- 35 -

One minor detail which would improve visual readability is
the suggestion to set off the incident particle and quantity fields
with parentheses as

Z-S-A(N T0T)
Z-S-A(P,2N)DA

etc.

This would seem to provide additional complication to the system
for little return.

Implementation Procedure
Non-neutron induced data will anyway he stored in libraries
separate from the neutron induced (plus spontaneous fission) library.
There is no advantage of merging both into the same library, even if
they have identical format.

Thus, let us start the non-neutron induced data with the newquantity scheme, without touching the present neutron-induced EXFOR,Later on one can decide what is more economical:a)to continue to keep two different quantity-dictionaries, orb)

to convert the neutron-induced EXPOR library in a one-off
program automatically to the new quantity scheme.

This can be decided only after the non-neutron induced EXFOR
library is in successful operation for some period. Until that time
no change in EXPOR should be made J

-36-

SHORT GUIDE TO EXFOR
Each EXFOR entry consists of several subentries. Each subentry may
include two types of information (l, bibliographic, 2. numericaldata). The first subentry contains only information applying to all thefollowing subentries. Each item of bibliographic information is identified by keywords (e.g.: TITLE, METHOD, STANDARD, ISO-QUANT, etc...)which may exhibit a coded information within parenthesis (e.g.» DETECTOR(SCIN), METHOD (ACTIV), ANALYSIS (LSP), etc. . . . ) . The meaning of most
keywords is obvious. Except for ISO-QUANT and the keywords using
similar codes (CMPD-QUANT, NUC-QUANT, STANDARD, RESID-NUC) the codesused are expanded in free text.
The numerical data belong to the following categories:-

numerical data which are common throughout the entry are
entered in the first subentry under the DATA CONSTANTS table.

-

numerical data which are common for a given subentry are
entered under the DATA CONSTANTS table of this subentry.
Each column of common data is independent and (probably) unrelated to other columns in the table.

-

numerical data which are relevant to the single quantity
defined by the keyword ISO-QUANT are entered in the DATA TABLE
under DATA (or RATIO). ISO-QUANT stands for "isotope andquantity".

There is only one ISO-QUANT per subentry. The first subentry
has no DATA-TABLE, therefore an EXFOR entry consists of at least
two subentries (see example page 2 ) . At the beginning of each table(DATA-TABLE or DATA CONSTANTS) there are two lines giving the DataHeading keywords (e.g.: STAND, DATA, H-LIFE, etc.) and Data-Unit
keywords (e.g. t MEV, B, N/0-DIM, etc. ...) for each data column.
A dictionary of Data-Heading keywords is given on page 3.

-37 »4TA fritOHf

IWrfflMMIMA*. ATOMIC 0ffit£f JttrMCr,\'*p r o t*rT

1 * * • ••*.1 • " • • ! •»'.'.
!Si«<•:«.'•First subentry:
informationcommon to theentire entry

i : c« »«• I t T-tf «*C»-. WT ,O»-. T M„ .

MTA CCMT4MT9
SIAJt* OTr

,;,
*"i

jil.o
?«.

....•........••••«•..

j]j a ta common| t o a H subentries^ l i n entry 30081

Data common
1?onlyt o sub-\Second/subentry

J entry 30081.002

PAT* T»iut

Data defined
under ISO-QUANT
of subentry
30081. oo;»

Data common to'subentry 30081.003

0. •«

J

. ere.. .

Third
Data defined
Subentry
under ISO-QUANT
of subentry 30081.003

TSXFOR/ENTRYKeywordEN
CN-CM
KN-MtN
EN-CM-MIN
EN-MAX
EN-CN-MAX
CN-OUMMY

EN-RSL•EN-RSL-EN-nSt
EN-6RR
EN-ERR1
EN-ЕВПг
• EN-ERR-KN-ERR
EN-KRM
EN-S6S
EN-HFS-ERR
MU-ACLER
Z
e-CM
e-HIN
E-CM-MIM
E-МАХ
E-CM-MAX
E-RSL
E-CRR
E-EXC
E-EXC-MK
E-EXC-MAX
E-LVL
E-LVL-INl
E-LVL-FIN
C-LVL-FnR
E-LVL-MIN
E-LVL-MAX
O-VALO-VAL-ERR
O-VAL-VIN
O-VAL-MAX
E-OCC
E-DGC-ERR
kVC-LN«VE-LN-ERR
*N6
ANC1
ANG2
ANG-CHANG-MIN
ANG-CM-MIN
ANG-KAXANG-CM-MAX

Explanation

Keyword( continued)

INCIDENT NEUTRON ENHI'OY. L A U - 4 Y 3 1 £ 4
INCITENT btUTROM ENi?nov, C-4-SV5TF.M
LCU L I M I T С" INCIDENT M-CI'f.r.GV RA>JT,E. LA9-SVSTEM
tCW L l i ' l T OF T N i l u e N T N-l-PFnc.Y FANr.E. C-M-SYSTi*M
HIÜH L I V I Ï ftf I N C I O K N T r.-l;.|Ltt.-.Y RANIiË. LAU-SYSTfcM
H I S » UI«MT CP INCtflKNT N-«NEMGY HANGF.. C-M-SV4TIÎM
CUCMY F.NRKOt. TO ВС USED AS THE NU4C4ICAL EQUIVALENT
OK AS INCIDENT NFUTRCN SPKCTRUM WHERE NO NUMERICALENEPCY VÍLUE t E GIVEN BY THE AUTHORI N C I P f N T - N i U T K O N RNERGY-nEJCLUTlON•UNSYMVKTRIC ENU-1GY PF 5СЩГ ION-UNSVI41TTHIC ElifRCY PEhntDT 1ПГ1ЕЧПОЯ OF k-OKOCHMCMATIC I N C I O l NT-N6UTR0N ENERGY OR
UNCf.OTAINTY OF THE CSNTRAL KNERGY I N AS INCIOENTNEUTnCN-SPFiCTDUM.
EKERGY ЕПКОП. I F fonfi THAN ONE ERROR I S O I V E N .
EKPLANATION UNPKR • E"R-AKALYS'•
SF.CCNO ENERGY EOOOR, I F МОЯЕ THAN ONE ERRCR I S S I V E N .
EXPLANATION UNOCR 'ERR-ANALYS 1• UNSYMME1RIC ENKRGY-tRHrR- UNSYMME TRIC EMenGY-5«MCR
NORMALIZATION ENERGY. TO PE USED WHEN A OATA SET I SNORMALIIEO TO ONE ENERGY ONLY.
RESONANCE-EMERGYERROn OF RESONANCE-ENERGY
MU I N AOLER ADLER- RESCNAhCE ANALYSIS. EQUIVALENT TORESONANCE ENERGYENEHOY CF CUTGfllNG PARTICLE. LAB-SYSTEMENERGY OF OUTGOING PARTICLF. C-M-SYSTEM
LCW L I M I T OF OUTGOING-PARTICLE E-RANGE. LAC-SYSTEM
LOW L I M I T OF OUTGCtNG-OAr-TtCLE E-RANCE. C-M-SYSTEM
HIGH L I M I T CF OUTCOING-PARTICLE E-RANGE. LAB-SYSTEM
HIGH L I M I T OF OUTGOINC-PAPTICLE E-RANG6. C-M-SYSTEMOUTGU1NG-PARTICLE ENERGY-RRSOLUTICNOUTGCING-PARTICLE ENERGY-ERROREXCITATICh-ENF.RGY
LCW L I M I T OF EXCITATION-ENERGY
flCM L I H I T CF EXCITATION-EHCHGYLEVSL-ENfcSGY
I N I T I A L LEVCL OF OAfMA-TRANSITIONFINAL LEVEL OF GAMMA-TRANSITIONLKVFL-EKCRGY FRPORLCw CNERCV-LIMIT CP A DISCRETE L6VEL-GRCUP
tlIGH SNERGY-LIMIT CF A OISCR.ETE LEVEL-«ROUP
O-VALUEC-VALU2 F.RRCR
LC««;R L t ' M T OF Q-VALueUPPFB L I M I T HF Q-VALUÏ
OtGnECATlCN I N NEUTRCN ENERGYERROR OF CEGREOATION I N NCUTRON CNERGTXAVE-LENGTH»<Avr-l.CNCTH EOKORANCLE. LAO-SYSTEMANGLE D E F I N I T I O N TO 6 Í SPECIFIED I N 0 1 8 SECTION
SAMt: AS ANGI USE ANG2.ANGJ.eTf I F M0R6 THAN ONe ANGLE
NFCnS TO SF OEFINEO
ANGL8. C-M-SYSTCM
LOW L I M I T OF ANGLE RANGE. LAB-SYSTEM
LOW L I M I T OF ANGLE RANGE. C-M-SYSTEM
HIGH L . I M T CF ANCLE RANGE. LAQ-SY5TEM
HIGH L I M I T CF ANGLE RANGE. C-M-SYSTEM

Explanation (continued)

ANG-RSL¿NG-CR4

ANGULAR RESOLUTIONANGLF-ERRCRCCSINE CF ANGL". LAO-SYSTi:4
COS-CH
C"!It>D r F ANCL<-, C-M-SY Г-1 CM
COS-MIN
LCW L I M I T MF CC1S.CF ANGLE. LAO-SYSTEMCflS-CM-MIN LOW L I M I T QF COS.CF Af.r.LF . C-M-SYSTF4
COS-MAXHIGH L I M I T CF CCS.CF ANGLE. LAB-SYSTEMCOS-CM-MAX HIGH L I M I T CF CCS.OF ANGLE. C-M-SYSTEMCOS-RÎLCOSINE CF ANGULAR RFSCLUTICN
COS-ERRCOSINE CF ANGI.E-ÍÍSKORHEADING F СП COLUMN G I V I N C THE OUANTITV S P E C I F I E D
0 A T AUNDFR MSO-UUAKT»
CATA-CMDATA r,IV«=N I N THE CENTRE OF MASS SYSTEM
OATA-MIH
LOW L I M I T OF DATUM
OATA-MAXHIGH L I M I T CF DATUM
DATA-ERR
OATA-EnBCR. CXPLAKATICN TO ПЕ GIVEN UNDER «ERR-ANALYS*
DATA-ERRl
FIKST O»T»-üliROR. I F f o n t THAN ONE CR«OR-CCt I S G I V 6 M .
EXPLANATION UNÛF» 'EPR-ANALYSDATA-ERR2 SECONO ПАТЛ-ЕИНОВ. I F MOKE THAN ONE ERROR-COL I S G I V E N .
EXPLANATION UNOCR "• HR-ANALYS•
ЮЬТЛ-ERR • UNSYMl'ETRIC ОАТА-ЕИРОИ. EXPLANATION UNOER 'ERR-ANALV9
OATA-ERR3 THIRD DATA-EnfcOR. I F MORE THAN ONE ERROR-CCL I S G I V E N . 1
EXPLANATION UNOFO "ERR-ANALYS•
1-OATA-ERR - UNSYMMETilIC DATA-ERROR. EXPLANATION UNOER «ERR-ANALYSRATIOHEADING FCH CCLUMN G I V I N G THE RATIO S P E C I F I E R UNOCR
MSO-OUANT'. OR THE OUANTITY/STANOARO RATIOR A T I O - M I h LC« L I M I T OF RATICIRATIO-MAX HIGH L I M I T CF RATIOTRATIC-ERd RATIC-EBRCRRATIC-EBF1 FIRST RATIO-EHRCR. I F МОГ.Е THAN ONE RATIC-ERROR I S
G I V E N . EXPIANATICN UNOFR -ERR-ANALYS»RATIO-ERR2 SFCCNO RATIC-EPRCR. I F МГ.РЕ THAN CNE K A T I C - E R R O R I S
G I V C N . (JXPLANATIOK UNOEH 'rHK-ANALYS •4-RATI0-ER4 « U N S Y M M E I R I C RATIC-ERHOR. EXPLANATION UNOCR 'CRM-ANALVS-RATIC-ERD -UNSYMMtTSIС RATIC-ERROR. EXPLANATION UNOER «ERR-ANALVSSTANDHEADING FCR C4LUMN G I V I N G THE NUMERICAL VALUE ASSUMEDFOR THE ISO-OUANT SPECIFIED UNOER -STANDARD*STANO-ERP STANDARD-ERRORSTANO1F I R S T STANDAPO-VALUE I F МОЯР. ТниН ONE I S G I V E N .
EXPLANATION UNDER •STANOARO1STANO2SECOND STAUPARC-VALUE I F МСГ.Е THAN CNE I S G I V E N .
EXPl ANATI ON UNCF4 «STANOARO'STANOI-ERH EBROR OF t-IMST STANCARO-VALUS
STANO2-FRR ER4CR OF SCCONO STANOARO-VALUE
TEMI>CnATUHET E M p
TEKP-ERRTEMPCKATUBE-CRRCP
H-LIFF
HALF-LICE OF RESIOUAL NUCLEUS
H-LIFË-ESR ERROR OF HALF-LIFE OF RESIDUAL NUCLEUS
F L A G . MCAMH1 OF FLAGS GIVFN UNO«B T H I S HEAOING TO BE
FufcG
FXPLAINFO IM в IB-SF.CT ICN UNOER «FLAG1.
NUMÜ6RNUMUCR. USED TO SPECIFY I N D I C E S . E . G . COEFF-NUMQERS•
LEVtl.-NUMPERS E T C .
NUMEER-CH COEFFICIENT NUMBER OF LfiGENORE OR COSINE COEFFICIENTSWHEN ТИГ F I T HAS HEEN ОЕГ.-UCCO FROM AN ANGULAR
D I S T R I B U T I O N I N WHICH T f E ENERGIES ARE GIVEN I N THE
CfNTRE OF MASS SYSTEM
j a F HFfCNAMCF.S. STRENGTH-FUNCTI CNS. E T C .
S l . _ rt j
S P I NMOMENTUM L ANGULAR MCMFNTUM L OF RESONANCFS, STRENGTH-F•S. E T C .
PARITYPARITY CF RESONANCE
HEADING FCR A COLUMN » I T H SUPPLEMENTARY INFORMATION P C *M I S C
WHICH NO CATA-HCACING KEYWOHO HAS 6fcEN OEFIMCD.
EXPLANATION TO OE GIVEN UNOER ' M I S C - C C L * KF.YWOBO

c o s

M1SCI
MIS»

FIRST MISCLLLAMEOUS COLUMN - I F MORE THAN CNE I S GIVEN
SAME USAGÍ AS -HISC-(.<-EF. ABOVE)
SECOND MISCELLANEOUS COLUMN - I F MORE THAN CNE I S GIVEN
SAME USAGE AS -MISC-CSEE ABOVE)

у
H°
U.
0
Я
Й
'4
J^
Ц
У
2.
j>
1
W
2
5.
>•'•
5
W

?4
,<*
^
О
4
g*
Ю

<ï
'
00

-39 -

ISO-QUANT

This keyword is used to specify the target isotope and thequantity which is presented by the compiled data set in the
DATA TABLE under DATA or RATIO.

The coding is divided into

5 subfields each separated by a comma.

The first subfield specifies the target isotope by the atomic
number Z, the element symbol S, the mass number A and the isomercode (for isotope in ground state, no isomer code is given) eachseparated by a hyphen.

Mass-number 0 stands for natural isotopic

composition of the element.

The other subfields specify the quantity.

- 40 -NUCLEAR STRUCTURE DATA FILE
Preliminary Specifications

Nuclear Data Project
Oak Ridge National Laboratory

February 7, 1974
Revised — March 29, 1974

- 41 -

I. INTRODUCTION
The Nuclear Data Project at ORNL is building a computer-based file of nuclear
structure data. This file contains, or will contain, the results of evaluations by the
Nuclear Data Project of all experimental nuclear structure data for A > 44 which havebeen published in Nuclear Data Sheets. In addition, it is desirable that the files contain such new data as may have become available since the most recent revision of the
Nuclear Data Sheets. In this latter activity it is necessary to solicit the assistance ofthe entii'e nuclear structure community in order that the task produces no large perturbation on the Project's principle activity of revising Nuclear Data Sheets.
This manual describes a standard input format for nuclear structure data. The
format is sufficiently structured that bulk data can be entered efficiently, and at thesame time, the format is flexible enough to provide a structure within which topics canbe added as their importance becomes clear.
II. GENERAL STRUCTURE OF THE DATA FILE
A. Introduction
The Nuclear Structure Data File (NSDF) is made up from a collection of "datasets", each of which describes the results of a single experiment or the combined evaluated results of a number of experiments of the same type. The appearance of thesedata sets within the computer file is of less concern here than is the appearance of thedata sets either before they enter the computer or after they have been retrieved. The
Nuclear Data Project has designed a card-based (or card-image-based) external representation of a nuclear structure experiment, which may be used for preparing input tothe computer file and for exchange of information retrieved from the computer file.
In the remainder of this manual, we shall refer to the group of cards or card images
as a data set, even though it is understood to be only an external version of the internal
data set which makes up part of the data file.
B. Examples of "Data Sets"
The next few pages present examples of data sets. In all cases, the standard
card formats have been used.

SAMPLE A

53CO
53CO C
53CO C
53CO C

64HI

6am

64KI
64NI
64NI
64HI
64HI
64MI
64 HI

53CO(!5) DBCAT
70CE04,70jA22,72CE01
FROH 54FE(P,2N) T. (T HUES H) = 2 6 . 3 HSV 4
DELATED PROTON. EMITTER, E ( P ) = 1 5 9 0 3 0 , I (P) = 1 . 5 * EST. FROM SIGMA
HO (BETA*) (P) COIN

7312216imi(P, P«)

740228L 0

73HDS

I. 1344
L 2275
L 2608
L 2865
L 3165
L 3560L 385097BO
97HB B- DECAY
97I1O FL E=10,J= 25,Q=80
P 0.
97NB
9/2 +
L 0.0
97H0
5/2*
L 480.9
97HO(3/2+)
L 657.9
97HO(7/2,9/2+)
G 177.97
97HO
G 657.92
97B0
B 1278.0
97HO
98.5
97«O
L 719.5(3/2+)G 238.37
97HO
97HO
G 719.47
L 1024.5
97KO(7/2,9/2+)
G 1024.53
97HO
97HO
B 911.0
1.0
97H0
L 1117.0(7/2,9/2+)
G 1117.01
97MO
97tlO
B 819.0
0.09
L 1148.6
97H0(7/2,9/2+)
G 1148.56
97H0
B 787.0
97BO
0.05
97HO
L 1268.6(7/2+)97MO
G 549.25
97K0
G 1268.63
B 667.0
97B0
0.21
97MO
L 1515.6(7/2,9/2+)
G 857.50
97fiO
G 1515.64
97HO
B 420.097HO
0.17
L 1629.1
97KO(7/2+)
G 909.57
97HO
G 1148.6
97MO
97H0
G 1629.13
97«0
B 307.0
0.07

OR

73BDS 1 0 , 1
72.1 H4

70AB11731221
1936

0.005
98.5
5.4
0.05
0.09
1.08
6.8
7.7

0.09
0.05 *

7.9

0.05
0.16
7.0

0.05
0.12
6.4

0.04
0.05 *
0.03
6.3

16

SAMPLE B- 43 -

98BO
98NB
98H0
98HO
98 BO
98HO
98HO
98HO
98 HO
98110
98HO
98 SO
98HO
98 MO
98«O
98 MO
98HO
98H0
98HO
98 KO
98K0
98KO
98RO
98BO
98MO
98KO
98HO
98KO
98HO
98MO
98NB
98KO
98HO
98F.O
98HO
98HO
98HO
98H0
98H0
98HO
98MO
98KO
98 HO
98SO
9800
9800
98HO
98HO
S8H0

98MO
98J1O
98HO
98RO
98H0
98 KO
98HO
98 KO

P

L
B
L
G
B
L
G
B
L
G
G

B
L
G
G
G
G
B

L
G

B
L
G
B
L
G

B

P
L
L
G
L
G
L
G
G

L
G
B
L
G
G

98KB 2.8- S STATE DECAT
(1*)
0*
0
4600
90.6
735.3
0*
735.3
3.8
3865
787.5
2*
787.5
3812
0.9
1432.12*644.6
1432.13168
1.5
1758.8H+.2*)
326.7
971.3
1023.51758.82841
2.5
1985.51250.22614
0.2
2207.11419.62393
0.4
2608.51821.01991
0.1

74HDS 11,247
2. 8 S
2

98SB 51-H STATE DBCAT(4-,S-)
0
0*

74MDS 11.247
10
51.5 H

736

731220
1 H2

4.5

5.5
5.6
3.0
6.2

0.8
0.8
5.6
0.07
0.8
1.5
0.14

5.2
0.2
6. 1
5.6
5.9

0.4
0.1

4.6E3

731220
1 H1

0*

735.5

787
787.2
1432
644.6
1431
1509
722.3
3091
1761

2»
97
2*

4.6
3.1
78

24.0

L
G
G
G

1231
2021

CC

7.4

1
2

971
1025
2018

L
G
B
L
G
G
G
B

4.6E3

T
T

259

3210
1701
— 1390
3455

9.4

9.4

6.4

434
1946
2021
1145

1
1.5
1

3.5

6.5

T
7

<59PDADOPTED LEVSL
Q -6037108870t 0(5/2+)99NB

SY6286ADOPTED, 100f1O(D, 3HE)
SY 7 4 2 0
SY 8 8 7 00.
(9/2) •
369
(V2)562('1/2,3/2)816
970(1/2,3/2)1271(1/2,3/2)1413(5/2,7/2)1573(5/2-,7/2-)
1746
1967

Q 3100

44 -

74HDS
30
21.4 H
74NDS
73TO02SY
14.3 S
2.6 B

99NB
99KB
99HB
991! B
99NB
99NB
9 9 NB
99KB

L
L
L
L
L
L
L
L
I.
L

99RU

ADOPTED LEVELS
207U6P
5 8390
0 -2052
0
5/2 +
L
89.36
L
3/2 +
322. 2L(1/2,3/2,5/2+)
L
340. 6(7/2+)
442. 8L(1/2,3/2)
L575. 2(7/2)
617. 5L(1/2,3/2)
I. 618.0(7/2+)
719. 2L(9/2 + )734. 2
L
050. 3I.
897. 2
L
1000. 2
t
1026
L
1048
L
1070
L
1261
L
(7/2 + , 9 / 2 + )1292. 1
L
L
1313
L
1382. 91497
L
L
1505. 1
L
1532. 91572
L
1662. 1
L
1749. 1
L
L
1761
L
2058. 6
(1/2-.3/2-)
L
2268

74NDS
AP

98HO (D,P)
L 0.0
L
98
236
L
353
L
529
L
L
552
L
619
L
688
L
„ 760
L
798
89fi
L
L
913
I.
952
L
io n
L
1261
1 391
I
I. 1 4 5 JI.
14') 1
1541
L
L
1672
172?
I.
17 5S
!•

74NDS

99R0
99RU
99RU
99R0
99RD
99RU
99RU
99RU
99RU
99 RH
99R0
99 RO
99RW
99RU
99RO
99RU
99R0
9 9 RO
99RU
9 9 RD
99RU
9 9 Rtf
99RU
99R0
99R0
99RU
99RU
99RU
99R0

99HO
99MO
99MO
99KO
99(10
99HO
9 9 MO
9 9 BO
99«0
99«O
99(10
99MO
99HP
9<»KO

nio
99no
90.10
T>11
9 )!10
9'lio
9910
90.10
99 no
<J o H o

90HO9') no

1,
1.
I.
i

1H4S
1 9 JOioun

SAMPLE C

4
1
1

2.7
1.6
2.5

1
1
3
(3)

0.7
0.7
2.3

2 0 . 6 NS

0
2

a
2
0
2
2
5
(«)
(3)
0,2
(2)
3
1
0
2

- 45 99MO
99MO
99HO
99HO
99M0
99 HO
99«O
99MO
9 9 KO
99SO
99HO
99 MO
99HO
99MO
99HO
99^iO
99 HO
99MO
99KO
99KO
99H0
9<?HO
99MO
99MO
99HO
99HO
99HO
99NO
99KO
99 HO
99KO
99HO
99HO
99HO
99HO
99HO
99HO
99HO
99HO
99HO
99HO
99KO
99MO
99MO
99HO

ADOPTED LEVELSQ 1372.2
L
0
L
L
235.5
L
352
L
525.5
L
L
615
6R7
L
L
753.5
793
t
L
8S9.5
905
L
T. 9 1 3
I.
945
7.
952
L
10 33
I.
1 150
I. 1199
T. 1209
L
126 1
L
1391
L 1453
L 1475
L
1493
L
1548
L
1672
L
1722
L
1755
L
1812
L
1845

L
L
I
L

1920
1930
1948
1965
2110
2200
2360
2430
2490
2540
2641
2734
2791
2952

L
L
L

t
L
L
L
L
I
h

395917

6 97301/2 +(3/2 , 5 / 2 ) *(7/2,9/2) +\ (3/2,5/2) +1/2 +(3/2,5/2) +(3/2,5/2) +(9/2 . 1 1 / 2 ) (5/2,7/2)(3/2,5/2) +(3/2,5/2)+
1/2 +

74NDS
AP

66.02 H
16.8 OS(3/2,5/2) +(5/2,7/2)(1/2,3/2)(1/2,3/2)1/2 +(3/2,5/2) +(3/2,5/2) +(1/2,3/2)(3/2,5/2) +(1/2,3/2)1/2 +
1/2 +
1/2 +
AP
AP
AP
AP
AP

99TC
99TC
99TC
99TC
99TC
99TC
99TC
99TC
99TC
91TC
99TC
99TC
99TC

COUL. EXCITATION
0
9/2 +
140.4
(7/2) •
140.4
1B1.7
t.
(5/2) •
G
41.0
G
181.7
L
726.3
(7/2,9/2) +G— 586.1
G
726.3
L 761 . 8
(7/2 .9/2) +
G
621.6
G
761.8

106KO
106^10100MO
106f1O

0

10610
106HO
106.10'SAMPLE D

7«tNDSLL
G

ADOPTEDnoo

L 0.0
I. 1 7 1 . 9
G 17 1 . 9
L 522.1
C, ) r »0.2

12
11
B9
14
86

LEVELS
SI

74NDS

0*

9.5 S
?

2 (2*)
2
5
5740319(E2)?

SAMPLE E- 46 124TE
124SB
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TS
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE

124SB
P 0.
L 0.0
L 602.72
G 602.72
B 2297.1
I. 1248.54
G 645.82
B 1651.3
L 1325.50
G 722.78
G 1325.49
B 1574.3
L 1656.5
G 1053.8
B 1243.3
t 1747.0
G 498.4
I. 1957.85
G 632.36
G 709.31
G 1355.17
B 94 2.0
I. 2039.3
G 713.82
G 790.78
G 1436.66
G 2039.3
B 860.5
L 2091.8
G 765.3
G 1489.03
G 2091.8
B 608.

124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE
124TE

2774.87736.
816.8
1526.33

2172.
124.9
2885.92283.2
13.9

178HP
L
G
G
G
G
G
G
G
G
G
G
G
G
G

177HF(H,G)
7625.77532.67319.16451.06357.36304.96-241.06216.16192.06175.46110.
6092.06064.35988.R

73KDS 10,124
60.20 D 3

B - DECAY
32*
10,0

E2

22.61
4*
7.36
2.45
2*
11.50
1.44

7312202899.8
98.36

C

7.23

CC

11.25
1.U1

cc
c

10.3
E2
10.6
E2»7.9XB1
10.2

5.39
0.009
0.009
(6*)
0.05

69NE04

0.009

12.6

LE

GE

<0.05
0.16
1.42
0.93

c
c
cc
c

2.39
0.74
1.02
0.06

c
c
c
c

0.03
0.55

c

<0.13 *
0.08
0.39
0.0010

C
c

LT

(«)•

0.16
1.45
0.95
2.0
2*
2.44
0.76
1.04
0.06
3.63
2*
0.03
0.56

9.8

9.4

H1.E2

<O. 1

0.68

10.0

<"»•)

<0.13
0.08
0.40
0.0010
0.53
(2,3)
0.008
0.008

7.5
0.008
6.4

PRIMARY GANHAS
3-,4(E1)
(E1)

(11)

(E1)
(F.1)
(El)

74KDS
0.065
0.047
0.096
0.454
0.096
0.100
0.064
0.036
0.051
O.R20
0.109
0.121
0.142

SAMPLE F- 47 -

178W
178W

L

1 7 8 H F ( A , 4KG) ,0.0

181TA(F,4NG)
0*

178W
178 H
178H
178S
178W
178W
178B
178W
178W
178W
178W
178W
178W
178W

L
G
L
G
L
G

178L0
178L0

ADOPTED, 178TB B - DECAY
Q 2. 15E3
105.97E3 106 .58E3
0.
L
U*)
B
690.
90. AP
1
42.4
(2*)
G
42.4
.067
IF B1
L
300.
AP
(7,8,9)

105.9
105.9
342.2
216.3
694.2
352.0
1141.
046.5
1668.
527.
2253.
585.
2892.
639.

L
G
L
G
L
G
L
G

2+

12

(4*)
(E2)
(6+)
(8*)
(10*)
(12*)
d<»*)

L 390.8

178YB

178IB
178TB
178TA
170TA
178TA
178TA
•

178RE
178RE

(1*1
1.00
0.64

390.8
348.4
250.

G
G
B

10.

178BE
178IR
178IR

L

178PT
178PT

L

4.0

5.9
4.2
4.4

AP

0.

3

9.31 H

3

2.2 H

1

4.7

74HDS
7 7 2 0 . AP
(3)

ADOPTED LEVELS
0.

3340.

AP

2

13.2 B
74NDS

22 S

ADOPTED LEVELS

0.

AP

74NDS
10

(7)-

-2800.

AP

22.7 K

74 K

ACOPTEC LBVFLS
Q
L

4.9

ST

178U »C EECAY
2 6 . 8 7 E 3 104 • 93F3
1*
1 00

0.

2

28.4 B

IF B1
IF HI

0+

L 0

L

AP

74HDS
10

74HDS

ADOPTED LEVEL
SI6670Q 700

ADOPTED,
Q
-89.
0.
L
R 91

74HnS

2

74NDS

0*

21.0 S

7LTLT

C. Summary of Data Set Structure
A data set is composed of records; each record is made up of one or more card
images.
A data set must begin with an IDENTIFICATION record (with label information) andmust end with an END record (a blank card). Between these two records, there will be
as many additional records as are needed to describe fully the experiment or the evaluated data set.
Immediately following the IDENTIFICATION record is a group of records whichcontain information about the entire data set. The NORMALIZATION (N), Q-VALUES(Q), FORMAT (F), and PARENT (P) records are of this type.
The body of a data set is composed of numeric data records winch describe themeasured or deduced properties of levels, -y-rays, or-particles, etc. These records areassociated with the level which decays (for GAMMA records) or the level which is populated (for B+, B-, EC, ALPHA records). Thus, each LEVEL record is followed by agroup of records describing charged-particle decay into the level and "y-rajr decay out of
the level.
If a GAMMA record (or ALPHA or B+ or B-) properly belongs in a data set, but it
cannot be associated with any particular level, then the record may be placed in the data
set before any LEVEL records.
COMMENT records (C) may appear in the data set wherever they seem most appropriate.

General remarks will usually follow the IDENTIFICATION record, while com-ments about a specific number should follow the record which contains that number.
III. STANDARD ONE-CARD RECORD FORMATS
A. Introduction
In most cases, all information for a RECORD can be placed on a single 80-column
card. A "standard" format has been defined for each one-card record, such that themost commonly used quantities can be placed on a single card. The standard formats
are described in this section for each reference.

If a needed quantity is not included in- 49 -

th6 standard format or if a value will not fit within the field defined for the value by thestandard format, then a FORMAT record will be required (see Section IV). If a record
cannot be contained on a single card, then additional cards can be prepared as describedin Section V.
B. The Standard One-Card RECORD Formats
RECORD formats are given below in the same order in which they would normallybe encountered in a data set. Conditions under which each RECORD may appear or be
required are given in parentheses. The format descriptions give the fields (in inclusive
card-column numbers), the field names (the formal "name" of the quantity that goes into
the field), and a brief field description. Card columns not explicitly included in thefields are expected JXJ be blank. Additional information about each field can be found in
the reference section noted.
1. THE IDENTIFICATION RECORD(Required for jill data sets)
Field
Col .

ITame

Description

Reference

1-5

NUCID

Nucleus identification

VI. A

10-39

DSID

Data set identification

VI. B

40-74

DSREF

Data set references

VI. C

75-80

DATE

The date (year/month/day) when the data
set was placed in the computerized data
file

-

50 -

2. THE FORMAT RECORD(Required only if the standard format is not used. See Section IV)
Reference

Field

Name

Description

Col. 1-5

NUCID

Nucleus identification

7

F

The letter "F" is required

8

RTYPE

Record type being formatted

FORMATS

A complete description of thords of type RTYPE; e.g., E = 10, DE =19, J = 24, . . . SYM = COL, where SYM is
any quantity allowed for RTYPE records and
COL is the column on RTYPE cards wherethe value of SYM begins

10-80

VI.A

VI. D

3. THE COMMENT RECORD(Optional with any data set)
Field

Name

Description

Col. 1-5

NUCID

Nucleus identification

7

C

Letter "C" is required

8

RTYPE

Record type being commented upon

VI.D

SYM (FLAG)SYM = type of data being commented upon

IV.C

10-19

FLAG = character in col. 77 of all level orgamma records to which the comment
applies
If FLAG is omitted, there is some ambiguity about precisely which records areaffected by the comment
20-80

CTEXT

TEXT of the comment
Comment records may also be used to givenumeric data which is not included elsewhere in the data set, e.g., X-rays,
annihilation radiation

Reference
VI.A

4. THE NORMALIZATION RECORD(Optional, used mostly with doeay data f
Field

Name

Description

Reference

Col. 1-5

NUCID

Nucleus identification

8

N

Letter "N" is required

10-19

NR

Multiplier for converting relative photon
intensity to photojvjj'fcr TOO decaj's of
the parent through this decay branch

20-21

DNR

Standard uncertainty in NR

22-29

NT

Multiplier for converging relative transition
intensity (including co.u ex-sion electrons)
to transition!-- per 100 decays of the parent
through this decay ocancb

30-31

DNT

Standard uncertainty in WT

32-39

BR

Branching ratio multiplier Toi converting intense ty per 100 decay a through this decay
brxich to intensity per 100 decays of theparent nucleus

40-41

DBR

Standard uncertainty in Ril

VI.A

VII

VII

VII

5. TJiE PARENT RECGHJJ(Optional, presence is desirable for ricrfy aata sets)
Name
NUCID

Description

8

P

Letter " P " is required

10-19

E

Energy of the decaymsr level in keV

20-21

DE

Standard uncertainty in E

22-39

J

Spin or parity or both

40-49

T

Half-life; units must he given

VIII

50-55

DT

C-fandard uncertainty in T

VII

Field
Col. 1-5

Nucleus identification for parent nucleus

Reference
VI.A

VII

65-74

QP

Ground-state Q-value in keV (total energy
available for g . s . — g . s . transition);
will always be a positive number

75-76

DQP

Standard uncertainty in QP

78-79

MS

If E •/ 0, then M or Ml indicates the firstisomeric state; M2, the second, etc.

VII

6. THE Q-VALUE RECORD(Optional in most data sets)
Field

Description

Name
NUCID

Nucleus identification

8

Q

Letter "Q" is required

10-19

Q"

Total energy (keV) available for p~-decayof the ground state. May be negative

20-21

DQ~

Standard uncertainty in Q~

22-29

SN

Neutron separation energy in keV

30-31

DSN

Standard uncertainty in SN

32-39

SP

Proton separation energy in keV

40-41

DSP

Standard uncertainty in SP

42-49

QA

Total energy (keV) available for a-decay of
the ground state

50-55

DQA

Standard uncertainty in QA

56-80

REF

Reference citation(s) for the Q-values

Col. 1-5Reference
VI.A

VII

VII

VII

VII

-53 -

7. THE LEVEL RECORD(Optional, ^although a data set usually has at least one)
Name
NUCID

Description

8

L

Letter "L" is required

10-19

E

Level energy in keV

20-21

DE

Standard uncertainty in E

22-39

J

Spin or parity or both

40-49

T

Half-life of the level; units must be given

VIII. A

50-55

DTStandard uncertainty in T

VII

56-64

L

Angular momentum transfer in the reaction
determining the data set. Whether it is£ n , £„, 6£, e t c . , is determined from the
DSID field of the IDENTIFICATION record

65-74

S

Spectroscopic factor for this level as determined from the reaction in the IDENTIFICATION record

75-76

DS

Standard uncertainty in S

77

C

Comment flag; used to refer back to a particular comment record. Analogous to afootnote

Field
Col. 1-5Reference

Nucleus identification

Letter "C" denotes an unresolved doublet or
multiplet
78-79

MS

Metastable state is denoted by M or Ml forthe first isomer; M2, for the second, etc.

80

Q

The character " ? " denotes an uncertain orquestionable level
Letter "S" denotes a "pseudo-level" such asat the neutron or proton separation energy

VI.A

VII

VII

- 54 -

8. THE GAMMA RECORD(Optional. Must follow the1 LEVEL record for the level from which the y-ray decays.
Records for y-rays which are unassigned in a level scheme should precede the firstlevel of the data set.)
Name
NUCID

Description

8

G

Letter "G" is required

10-19

E

Energy of \ - r a y photon in keV

20-21

DE

Standard uncertaintj"- in E

22-29

RI

Relative photon intensity

30-31

DRI

Standard uncertainty in RI

32-41

M

Multipolarity of transition

42-49

MR

Mixing ratio 6 (sign must be shown explicitly
if known)

50-55

DMR

Standard uncertainty in MR

56-G2

CC

Total conversion coefficient

63-64

DCC

Standard uncertainty in CC

65-74

TI

Relative total transition intensity

75-76

DTI

Standard uncertainty in TI

77

C

Comment flag; refers back to a particularcomment record. Analogous to a footnote

Field
Col. 1-5

Nucleus identification

Letter "C" denotes unresolved doublet or
multiplet
78

ORG

Letter "C" denotes coincidence with a p r e ceding radiation

79

END

Letter "C" denotes coincidence with a following radiation

80

Q

The character " ? " denotes an uncertain orquestionable line or an uncertain placement of the transition
Letter "S" denotes an expected, but as yet
unobserved, transition

Reference
VI.A

VII

VII

VII
VII

VII

- 55 9. THE p~-RECORD(Optional. Must follow the LEVEL record for the level which is fed by the p .)
Name
NUCID

Description

8

B

Letter "B" is required

10-19

E

Endpoint energy of the p in keV

20-21

DE

Standard uncertainty in E

22-29

IB

Intensity of the p-decay branch in percentof the total p~-decay

30-31

DIB

Standard uncertainty in IB

42-49

LOGFT

Log ft for the p -transition

50-55

DFT

Standard uncertainty in LOGFT

77

COIN

Letter "C" denotes coincidence following
radiation

78-79

UN

Uniqueness classification for the p-decay,
e . g . , 1U, 2U; a blank signifies an allowedtransition

80

Q

The character " ?" denotes an uncertain orquestionable p~-decay

Field
Col. 1-5Reference

Nucleus identification

VI,A

VII

VII

Letter "S" denotes an expected or predictedtransition

10. THE EC (or EC + p ) RECORD(Optional. Must follow the LEVEL record for the level being populated in the decay)
Field

Name

Description

Col. 1-5

NUCID

Nucleus identification

8

E

Letter "E" is required

10-19

E

Energy for electron capture to the level.
If p + -energy is measured, it is placedon a COMMENT record

20-21

DE

Standard uncertainty in E

22-29

IB

Intensity of p + -decay branch in percent of
the total (c + p+)-decay

Reference
VI. A

VII

30-31
32-38

DIB

Standard uncertainty in IB

IE

Intensity of electron capture branch in percent of total (c + p+)-decay

40-41

DIE

Standard uncertainty in IE

42-49

LOGFT

Log ft for (e + (3 ) transition

50-55

DFT

Standard uncertainty in LOGFT

77

COIN

Letter "C" denotes coincidence between p
and a following radiation

78-79

UN

Uniqueness classification for e, f3+ decay,
e.g., 1U, 2U; blank signifies an allowedtransition

80

Q

The character " ? " denotes an uncertain orquestionable e, (3+ branch

VII

VII

VII

11. THE ALPHA RECORD(Optional. Must follow the LEVEL record for the level being populated in the decay.)
Name
NUCID

Description

8

A

Letter "A" is required

10-19

E

Alpha energy in keV

20-21

DE

Standard uncertainty in E

22-29

IA

Intensity of a-decay branch in percent of thetotal a-decay

30-31

DIA

Standard uncertainty in IA

32-39

HF

Hindrance factor for a-decay

40-41

DHF

Standard uncertainty in HF

Field
Col. 1-5Reference

Nucleus identification

77*~ COIN

Letter "C" denotes coincidence with following
radiation

80

Q

The character " ? " denotes uncertain or questionable a-branch
Letter "S" denotes an expected or predicteda-branch

VI.A

VII
VII

- 57 12. THE END RECORD(Required for all data sets)
Field

Description

Col. 1-80

All columns are blank

C. Summary
The following figure summarizes the standard one-card formats for all allowed
record types.

IF
<
<
>
>

NUCLEAR DATA SET-ORNL NUCLEAR DATA PROJECTиSTANDARD FORMATS
i

23

;

: nucleus! nucleus
i nucleus
i nucleus\ nucleus• nucleus
i nucleus| nucleus! nucleus
i nucleus! nucleus

22 23 24 25 26 27 28 29

0 ¡31 32 33 34 35 36 37 38 39 iO 4 1

SYST.

• ¡24 43
4 4I 45 4G 47 4 8 14950 51 52 53 54 55 56 57¡58 59¡60¡61 62
3 44

PUNCH

LE
LT
GE
GT
АР
SY

3 04 65J66 67 68 G9J70J71 72 73¡700

I

symbol5ty e of data setDE

key number (KN)
•DT-

•Q/3-

- r t"
1• I t -

I

i

:

DQ/3

MS

- 59 IV. PREPARING FORMAT RECORDS
A. Introduction
If the standard one-card formats described in Section III.B are used, then there isno need to include a FORMAT record. A FORMAT record | s required if the data items
in a one-card record are too wide for the standard fields or if the data appear in an orderdifferent from the standard record or if data of a nonstandard type are to be included on
the one-card record. Only the first card of a record may have its organization describedby a FORMAT record. Continuation cards for the record will always contain their own
format information (see Section V). A FORMAT record may not be used for the IDENTIFICATION record, a COMMENT record, the NORMALIZATION record, the Q-RECORD,
the END record, or another FORMAT record.
B. Organization of the FORMAT Record
The FORMAT record will alv/ays contain the letter "F" in col. 7 and a character
RTYPE (see Section VI.D) in col. 8 to identify the type of record the format of which is
being specified by the FORMAT record. The FORMAT record must consist of only a single
card; i . e . , continuation cards are not allowed. The text of the FORMAT record is containedin cols. 10-80. The text consists of a series of equalities separated by commas or blanks;e.g., E = 10, DE = 20, J = 23, L = 40. In general, the form DTYPE = COL in a FORMAT
record implies that the data of type DTYPE is always contained in a field beginning in column COL of the RTYPE record. By implication, the field width includes all space up to
the next larger value of COL given for some other data type DTYPE.
If a FORMAT record is used, care must be taken to avoid conflicting format specifications. The same data type may not be identified with more than one location on thedata record; i . e . , E = 10, E = 25 is in error.
Since each field width is assumed to be the maximum available for the particular
data type, it is important to specify the complete format of the record RTYPE. If the textof the FORMAT record for level records is E = 15, J = 25, T = 40, then ten card columns
are allowed for E, 15 for J, and 41 columns are allowed for T. If any level record contains other information, e.g., the letter "C" for "unresolved doublet" in col. 77, then astrange value for the half-life (T) will be inferred since the information is within the fielddefined for "T" type information.

- 60 C. Allowed Data Types
Each record type is permitted to contain only a limited (but extendable) set of datatypes. For example, a GAMMA record is not allowed to contain information of data type
DTYPE = J (nuclear spin). Neither may a LEVEL record contain LOG FT information.
For each record type, the following table lists the data types permitted as of 11/15/73.
1. For the PARENT record
2. For the Q-VALUE record
All allowed data types are included in the standard format description in Sections
III.B.5 and III.B.6.
3. For the LEVEL record
Allowed data types, E, DE, J, T, DT, L, S, DS, C, MS, Q, are described withthe standard formats in Section III.B.7. Additional allowed data types are:
DTYPE

Description

MV

Level energy in MeV

DMV"Standard" uncertainty in MV

UEV, UKV, UMV

Uncertainty in level energy, expressed in eV, keV, and MeV,
respectively

PE

Percent uncertainty in level energy

UE

Uncertainty in level energy, given in same units as the level
energy itself

A

Percent isotopic abundance

SIGNG

Thermal-neutron capture cross section

SIGNA

Total thermal-neutron absorption cross section%EC, %SF, %IT, %N

Percent decay of the level by electron-capture, spontaneous
fission, isomeric transitions, or emission of a J3~, /3 + , a,proton, neutron(Section VII)g-factor of the level
MOME1, MOME2, . . .

Electric moments: dipole, quadrupole, . . .

M0MM1, M0MM2, . . .

Magnetic moments: dipole, quadrupole, . . .

CONF

Nuclear configuration of the levelF

A "free-form" field (see Section IX)

- 61 4. The GAMMA Record
Allowed data types, E, DE, RI, DRI, M, MR, DMR, CC, DCC, TI, DTI, C, ORG,
END, Q, are described with the standard formats in Section III.B.8. Additional allowed
data types are:
DTYPE

Description

MV

Gamma energy in MeV

DMV"Standard" uncertainty in MV

UEV, UKV, UMV

Uncertainty in •y-energy, expressed in eV, keV, and MeV,
respectively

PE

Percent uncertainty in y-energy

UE

Uncertainty in y-energy,
itself

BE1, BE2, • • •Reduced electric transition probability (downward) given inunits of e 2 x (barns)^, where L = 1, 2, . . .

BM1, BM2, • • •Reduced magnetic transition probability (downward) given inunits of ^ x (barns) L , where L = 1, 2, . . .

CEK, CEL, CEL1,

ce-intensity for K, L, Lj_, . . . conversion

KC, LC, L1C, . . .

Theoretical K-, L-, L^-conversion coefficient

EKC, ELC, EL1C,

Measured K-, L-, L^-conversion coefficient

K/L, M/L, L1/L2,

ce-intensity ratios

PRI, PTI

Percentage uncertainty in RI, TI

URI, UTI

Uncertainty in RI, TI given in same units as RI, TI

F

A "free-form" field (see Section IX)(Section VII)

given in same units as the y-enevgy

5. The B -Record
Allowed data types, E, DE, IB, DIB, LOGFT, DFT, COIN, UN, Q, are describedwith the standard formats in Section III.B. 9. Additional allowed data types are:
DTYPE

Description

MV

Beta energy in MeV

DMV"Standard" uncertainty in MV (Section VII)

UEV, UKV, UMV
UE

Uncertainty in p-energy given in eV, keV, MeV, respectively
Uncertainty in p-energy given in same units as energy

-62 PE

Percentage uncertainty in p-energy

EAV

Average energy of the (3-spectrum

F

A "free-form" file (see Section IX)
6. The EC Record
Allowed data types, E, DE, IB, DIB, IE, DIE, LOGFT, DFT, COIN, UN, Q, aredescribed with the standard formats in Section III.B. 10. Additional allowed data types are:
DTYPE

Description

MV

Energy for electron capture to a level given in MeV

DMV"Standard" uncertainty in MV

UEV, UKV, UMV

Uncertainty in capture energ}' given in eV, keV, MeV, respectively

UE

Uncertainty in capture energy given in same units as the energy(Section VII)

itselfPE

Percentage uncertainty in capture energy

EAV

Average energy of the p -spectrum

TI

Total (capture + p+) intensity of the decay branch

DTI

Uncertainty in TI

K, L, M, N+

Probability for electron capture from the K, L, M, N+O . . .
shells
7. The ALPHA Record

All allowed data types are included in the standard format description in Section
IV.B.ll.

V. RECORDS CONTAINING MORE THAN ONE CARD
A. Card Enumeration
If all the information for a given record type cannot be contained on a single card,then it is possible to use additional cards to fully describe the record. The first card ofa record will have the number 1 or a blank in col. 6. Subsequent cards will have running
numbers: 2, 3, . . . up to 9. It is not allowed to have continuation cards with the IDENTIFICATION record, the FORMAT record, the NORMALIZATION record, or the END record
since these records consist of a single card. (The FORMAT record consists of a single
card for each record type for which a special format is described.)

- 63 B. Formats for Continuation Cards
The first card of any* record type has a standard format. The standard format may
be overridden when necessary by a FORMAT record (Section IV). Additional cards forany record type (if permitted) do not have a standard format, and their format cannot be
described with a FORMAT record. The second, third, and subsequent cards of any r e c ord type will contain structure of the type CEK = 47, %SF < 10E-3, MOME1 = 0.037 4.
The data types in the general structure "DTYPE = data uncertainty" are limited to thesame set of names that are allowed for describing nonstandard formats for the various
record types (see Section IV). Here, however, the DTYPE identifier and the data value
need not be equal, out may be connected by a relational operator from the following list;LE

less than or equal to (^)

LT or <

less thanGT or >

greather thanGE

greater than or equal to (S:)

AP

approximately equal to («)

SY

obtained from systematics

CA

calculated value

The alphabetic representations must contain a blank on either side, i . e . , " GT ", " AP ".

VI. DETAILED FIELD DESCRIPTIONS
A. NUCID
The standard nucleus identification consists of two to five characters giving the Avalue and the chemical symbol of a nucleus, e . g . , 9B, 20F, 98RU, 177HF. The nucleus
identification must be contained within the field defined for it (cols. 1-5 on most cards).
It is recommended that the nucleus identification always begin in col. 1; i . e . , it is leftadjusted. The nucleus identification must be included on every IDENTIFICATION record.
It is strongly recommended that it also be included on every card of a data set except the
END record. The data set will be handled correctly if all cards except the IDENTIFICATION record contain blanks in the NUCID field, but such decks are very difficult to edit.

B. DSID
The content of a data set is described in a standard way in the DSID field of the
IDENTIFICATION record. The standards may be described under three general headings: 1) decay data sets, 2) reaction data sets, 3) "adopted" data sets.
1. For a data set describing the results of a measurement of radioactive decay, theDSID field contains three parts separated by one or more blanks — the decaying nucleus,
the type of decay, and the word "DECAY", e.g.,
22NA
64Y
116M2IN
127MXE
133BA
214AT
252CF

B+
BBIT
EC
A
SF

DECAY
DECAY
DECAY
DECAY
DECAY
DECAY
DECAY

The decaying nucleus is identified by its standard NUCID (Section VI. A) and, if
necessary, also by an embedded metastable-state code, M, Ml, M2, etc. The code refers
to the MS-field of the LEVEL record which describes the decaying level of the parent
nucleus.
Five deca3' types are recognized in the DSID field:
p-decayelectron capture and/or |3+-decay
a-decayisomeric state decay (y- radiation only)
spontaneous fission
2. For a data set describing results of a nuclear reaction study, the DSID field contains the target and the incoming and outgoing particles such as:
20NE(P,D)
48CA(A,A») for (a,a')109AG(40AR, 40AR')
90ZR(A,4NG)
The target nucleus and the reacting particle may be given in the standard form (see NUCID,
Section IV.A). The reacting particles may alternatively be taken from the list of abbreviations:p proton (1H)
N neutron
A a-particle (4HE)

M+l v

M-J

/u-mesonP+"D

deuteron (2H)

PO • 7r-meson

Ttriton (3HE)P-

G v-ray

NU neutrinoEelectron

3. An "ADOPTED" data set contains the best representation of the present experimental knowledge about the levels of a nucleus. The data set will be named, e.g.,
ADOPTED 187RE LEVELSADOPTED 64NI LEVELSADOPTED LEVELS
If all level information for a nucleus is contained in a data set for a single experiment, it is not necessary to make an ADOPTED data set as well. However, if more than
one experimental data set contains level information about the nucleus, then, a separate
ADOPTED data set MUST be made, even if the ADOPTED data set contains only the QVALUE record and a simple ground-state LEVEL record.
An ADOPTED data set always contains (in its IDENTIFICATION record) a reference to the Nuclear Data Sheets or similar evaluation where the supporting data have been
compared.
An ADOPTED data set contains a Q-VALUE record (e.g., as produced by the Atomic
Mass Adjustment Program), which includes at least On, S n , Sp, if available.
An ADOPTED data set contains a LEVEL record for every level that has been reliably observed.
GAMMA records may also be included in an ADOPTED data set.

- 66 -

C. DSREF
References to supporting publications or analysis are placed in this field by meansof standard Nuclear Data Project reference key numbers. If the data set describes asingle measurement, then the key number of the published report of the measurement issufficient. The DSREF file may include more than one key number, each of which refers
to a particular publication. If different experimental results have been combined or modified to form the data set, then the DSEEF field should also refer to the source of the combination or modification, e.g., the Nuclear Data Sheets as 73NDS, 74NDS.
The DSREF field will be used mostly internally to the Nuclear Data Project to keep
records of which data have superseded or been modified by others. The DSREF field will
be so assigned that distinct data sets will also have distinct DSREF fields.
D. RTYPE
A single-letter code that gives a name to the RECORD type.
RTYPE
Blank
N
P
Q
L
G
B
E

A

Description
May be IDENTIFICATION record or END record
NORMALIZATION record
PARENT record
Q-VALUE record
LEVEL record
GAMMA record
B- record
EC (or EC + B+) record
ALPHA record

In a FORMAT record, RTYPE may not be blank or "N".

- 67 VII. UNCERTAINTIESEvery experimental number entered into the data file should have an uncertainty
associated with it if at all possible. Uncei"tainties may be numeric or non-numeric.
Numeric uncertainties may be symmetric or asymmetric.
A. Standard Numeric Uncertainty
The "standard form" for expressing numeric uncertainties is as an integer uncertainty in the least significant digit(s) of the experimental number; i . e . , 448.7±0.7 — 448.7 7;
0.3721 ±0.0014 — 0.3721 14. The RTYPE for a standard uncertainty is usually formed byadding the prefix D to the RTYPE of the datum, e.g., E, DE; RI, DRI; MV, DMV.
An asymmetric uncertainty may be written in the standard form by including signs;+ 0.100.84—- 0.84 +10 - 3 . The convention on asymmetric uncertainties is that they combine algebraically with the datum, such that -3

describes a range from -7 to -2.

B. Non-numeric Uncertainties
The non-numeric uncertainties include not only the symbols for approximate, calculated, systematics, but also the relational operators such as greater-than, less-thanor-equal-to, etc. The non-numeric uncertainty may be given either as a symbol or as a
two-letter code in the uncertainty field:
Symbola

Letter codeAP

Meaning
approximatelyCA

calculatedTHtheoretical>GTgreater than

2= or > =GE

greater than or equal to<LTless than=s or <=

LE

less than or equal to

SYsystematics(It is more natural to place certain of the relational operators in front of the value itself,e.g., > 1.3, LE 14, but at present these cannot always be handled by the system.)- 68 VIII. EXPECTED AND ALLOWED UNITS
j Half-lives must include units. Use
FS = 10" 15 s
PS = 10"12

H = hours

D = day

NS = 10~9 s

Y = year6

US = ^ = 10~ s

KY= 103 y

MS = 10~3 s

MY= 106 y

S

GY= 109 y= second

M = minuteComputer-standard exponential format may be used. Examples:
3.7 PS = 3.7 E - 12 s
4.21 GY = 4.21 E 9y
JEL Signs of certain experimental quantities (nuclear moments, Y-ray mixing ratios)
are as important as the numbers, themselves. If the sign is known, it should be given
explicitly. If the sign is not known, then the absence of any sign is just as descriptive as
the + - (or ±). If a value is known to be > 0, it must have a sign.

- 69 -

MEMO
March 20, 1974

To: Nuclear Data Project Compilers

From: W.B. Ewbank

Subject: Data Bank Standards
In anticipation of entering blocks of information from Nuclear Data Sheets into the computer-based data bank, the following standards are presented as minimum requirements forthese data blocks. Some requirements are already in common use from preparing drawings. Other requirements are necessary or desirable for present and planned auxiliary
programs. Comments are welcome and encouraged.
I. A-Chain CompletenessFor each A-chain there should be at least one data set for each isotope. Usually there
will be more.

II. Isotope CompletenessFor each nucleus, there should be at least one data set for each distinct experiment giving level information about that nucleus. A rough guide to experiments is: "If it should be
displayed in the Nuclear Data Sheets, there should be a data set".
For each nucleus there should be one, and only one, "Adopted levels" data set.
By convention, if only one data set exists for a nucleus, that data set will be treated as an"Adopted" data set. It should include the Q-record just as for any other "Adopted" dataset (see IV. A below).

III. Data Set Identification
No two distinct data sets may have the same ID-record. The computer will accept only
the first one. In a very few cases (e.g., capture gamma as noted below), a degeneracy
may be removed artificially by adding a qualifying phrase.
Since we are using the ID-record in a "generic-key" indexing system, all data sets whosenames begin with a given sequence of characters can be retrieved as a group, regardlessof how the ID-records end. In general, the broadest categories should be mentioned firstin the ID-record, with nuances and finer points coming later.

- 70A. Radioactivity
For radioactivity data sets, the data set name (col. 10-39 of the ID-record) wall include
the parent isotope and the type of decay (B-, IT, EC, B+, A, SF). Data bank programs
will make no distinction between EC and B+ as a decay type.
Isomers should be identified by their half-life, not by codes such as M, Ml, etc.
Some acceptable data set names are:
63NI B- DECAY
2.6-M 99NB B- DECAY
54MN EC DECAY
3.89 79SE IT DECAY
106IN B+ DECAY
B. Nuclear Reactions
Wherever possible, the reaction should be given completely and explicitly, including thetarget.
Some experiments can be grouped efficiently; e.g., COUL. EXCIT. could summarize
Coulomb excitation by protons, alpha particles, and heavy ions. Again, however, if you
think it is necessary to display them separately in the Data Sheets, they should also beentered into the data bank as separate data sets.
Some acceptable data set names are:169TM(N, G)
177HF(N, G) PRIMARY GAMMAS
65CU(3HE,A)
90ZR(P, P') IAS
COULOMB EXCITATION
COUL. EXCIT.
(HI,XNG) REACTIONS
181TA(P,4NG)
181TA(N, G) E = 2 K E V
C. References
If the data set was used in a published A-chain (either as a figure or a table), you must
include the year and flag: 74NDS, 71NDS.
Other principle references may be included in the reference field or may be carried on
separate comment cards.

-71 D. Date
The date when the data set entered the computer is automatically added by the system. You
should not write anything in col. 75-80 of the ID-record, since it will be ignored and lost.

IV. Data Set Contents
Uncertainties should be given for all measured values and all adopted values wheneverpossible! Sometimes a general comment about uncertainties can obviate this requirement.
However, no program can yet use an uncertainty which is not given on the same card withthe primary quantity.
No more than two significant figures should be used for a standard uncertainty. The needfor nonsignificant zeros can be removed by writing the measured quantity in computerexponential style; e.g., 3500± 100 can be written 3.50E3 1.0.
A. "Adopted" Data Sets
The adopted data set for a nucleus must contain the Q-record for that nucleus.
The Q-record must include at least Q(p-), S n , S .
Each level record must include an adopted half-life (if known) and its uncertainty.
If a level deca3's by means other than isomeric transitions, the percent branching must be
given if it is known.
Each level record may include a spin-parity only if it can be established according to NDP
rules.
B. "Decay" Data Sets
1. Gamma records
Uncertainties on y-ray energies should be included if available.
Include relative intensity (usually photon intensity) in same units as given by an author oras adopted by you after a renormalization. (You probably listed them on a Data Sheet, sothey should be in a data set, anyway.)
Include Y"ray rnultipolarities if known or if assumed for constructing the decay scheme.
Give the total conversion coefficient if the conversion intensity is important.

2. Beta- and EC-records
Intensities should be given'in percent of this type of decay, such that BR x intensity gives
absolute percent per decay of the parent state.
If the IB-field on an E-record is blank, then the IE-field is presumed to contain total intensity (e + p + ).
An EC-decay data set must include a Q-card with at least a Q((3~) entry. (I hope this restriction is temporary.)
Don't forget "1U" or "2U" in col. 78-79 for unique transitions.
3. Normalization record
Better to give all normalization information here than to "hide it" by giving total transition
intensity with each y-ray.
4. Parent record
Must be included with all decay data sets.
5. Level records
Include uncertainty in E (level) if available.
Give adopted Jn where available.
C. "Reaction" Data Sets
1. Gamma records
See notes above for "decay" data sets.
2. Level records
Give Jw only if it is established or strongly suggested by this particular reaction.
For transfer reactions, give ^-transfer if it is supported by an angular distribution.

WBE:sjb

- 73 -The Digital Data Files of the Photonuclear Data Center
Henry M. Gerstenberg

The various files of digital data maintained by the Photonuclear Data Centerare specified by the acquisition number assigned to a particular data set. Ample
allowance has been made for any conceivable future demands on the system from thisrelatively small branch of nuclear physics. By the use of appropriate designators,
each associated with a well-defined sub-area of physics, the file system could be
expanded for use in other sub-areas. The major categories now being used arelisted in Table I. The various categories are then defined and discussed in detail.
Finally, specific examples are given.
Table I.

File Categories

Series

Cross Section
SpectraAngular Distribution
Manipulated
Combination(Not yet designated)
Evaluat ed Cro s s Sect ion

00,00010,00020,00030,00040,00050,000-80,000
90,000Range of
Acquisition Number
1 - 9999
10001 - 19999
20001 - 29999
30001 - 39999
40001 - 49999
50001 - 89999
90001 - 99999

Each file consists of a number of data sets. A particular data set consists ofan identifier card and two label cards followed by an arbitrary number of comment
cards and a series of data points. A data point is defined as a set of either twoor three numbers depending apon.whether or not a flag is indicated in the appropriate position on the identifier card for that particular data set. In the more usualcase the two-number set gives abscissa and ordinate values. When the three-number
set is flagged, abscissa, ordinate, and uncertainty in ordinate. are given for eachdata point.
The identifier card uses eight fields to specify the information contained in agiven data set. The information given in these fields and their position on a cardis indicated in Table II. The two label cards following the identifier card simply
explain the abscissa and ordinate axes. A total of 32 character spaces is allowedon each card; the information normally starts in the first column.

74 Table II.

Field
PositionStart of Field-Right or Left
Adjusted

Acquisition Number

1 - 5

Rlglt

Number of Data Points

7-11

Right

Photonuclear Data Center Reference Number

13 - 18

Left

Nuclide for which data are given(target nuclide for photon's incident,
residual nucleus for capture reactions)

24-30

Left

Reaction

32 - 43

Left

Information

No entry: indicates data were digitized by
Data Center.
1: flag to indicate digital data wereobtained directly from source.

45

No entry: two-number format for each data
point used
1: flag to indicate three-number format
for each data point, i . e . , uncertainties
in ordinate values are given.

47

Modification Code - used only for manipulated
data f i l e to define successive manipulations
carried out on some original data set.
Manipulations are defined by comment cards.

49 - 50

Right

Cross Section File - 00,000 Series (1 to 9999)
Any reaction cross section normally listed In the Photonuclear Data Index may
be placed In this file. This may be digital data sent to the Center by authors ordata digitized from journal articles. The intent is to use this file only for experimental cross section data that have not been modified. Thus, (y.sn) data,
derived from measured (y,xn) data by a calculation, are not included. The acquisition number assigned to any data set is the lowest number currently available
between 1 and 9999.

Spectra File - 10,000 Series (10001 to 19999)
This file contains data dealing with spectra of outgoing neutrons, protons,
alpha particles, photons, etc. The acquisition number assigned to a data set isthe lowest number currently available between 10001 and 19999. The energy or energies of the particles in the incident beam inducing the reaction Is given on acomment card.

Angular Distribution File - 20,000 Series (20001 to 29999)
Angular distributions of any reaction product with respect to the incident
beam direction are contained in this f i l e .
The acquisition numbering system is
identical to that of the spectra f i l e except that the. range of numbers is between
20,001 and 29999. Data are normally given in terms of a Legendre polynomial expansion of the angular distribution.
Point-wise data, i. e. , angle vs differential
cross section or yield may also be entered. The energy or range of energies of thedetected particles is given as a comment.

Manipulated File - 30,000 Series (30001 to 39999)
Data from the cross section f i l e that have been modified are found in thisfile.
Typical examples of manipulated data would be (1) the inverse cross section
as obtained by detailed balance, and (2) normalization of a cross section measured
at a single angle for comparison with integrated over angle cross section data.
The acquisition number of the manipulated data is found by adding 30,000 to
the acquisition numbers of the unmodified data set. If more than one manipulationof the original data set is made, then an additional two-digit integer code (anumber between 1 and 99) is punched on the identifier card. These modifications
are defined on the comment cards of the manipulated data sets.

Combination File - 40,000 Series (40001 to 49999)
At the present time this f i l e contains data sets that are the combination of
two or more data sets from the cross section f i l e .
Most of the data in this series
are created with the program COMBIN. Examples of data sets in this f i l e are:(1) the (y,xn) data set as obtained from the (y»n), (y,2n), and (y,3n) data sets
kept in the cross section f i l e ; (2) the cross section for a 'composite1 naturalelement as made with the isotopic data for that element.
The data used to create this f i l e as well as the data in the f i l e itself are
not smoothed. The emphasis i s to modify the data as l i t t l e as possible in obtaining the desired result.
The acquisition number assigned to a data set in this f i l e
is the lowest number currently available between 40,001 and 49999.

Evaluated Cross Section File - 90,000 Series (90001 to 99999)
The contents of this f i l e contain the 'recommended or best value1 data to be
used in the Atlas of Evaluated Photonuclear Cross Section Data. This f i l e will
generally consist of those cross sections which make the largest contribution to
the total nuclear absorption cross section.
Except where data warrant a finer resolution, points are. given at every half
MeV. Cross sections are obtained by interpolating and 'smoothing' data presented
in the cross section f i l e .
Cross section magnitudes are those obtained from thebasic data. Any renormalizations that are felt to be neces.sary to obtain a 'best
value1 or consistency with other measurements are indicated on the comment cards.
Acquisition numbering is accomplished by adding 90,000 to the cross section being
evaluated.

- 76 -

CROSS SECTION
FILE

pa
COMBIN PROGRAM{DETAILED BALANCEj
PROGRAMANGULAR
DISTRIBUTION
FILEW

COMBINATION

SPECTRA

FILE

FILE

MANIPULATEDFILESMOOTHING W/ OPERATION \EVALUATEDCROSS SECTION
FILE

Relationships of files and programs are discussed in the preceding pages.

- 77 Example 1.

Gross Section File

The four cross sections listed here are used later to indicate
how the basic measured data are used to generate other files.

304
69 66BR1
PHOTON ENERGY* (MEV)
CROSS SECTION. (MB)59PR141 <G.N).8788+01, .4410+01. .9097+01, .0000, .94o7+ol, ,1517+o2, ,9717+ol, ,3l75+o2.1003+02, .3388+02, .Io34+o2, ,4524+o2, .Io65+o2, ,432O+o2, .Io96+o2, ,5829+o2.1126+02, .6455+02, .1158+02, .7315+02, ,1188+02, ,8o25+o2, .1219+02, .9955+02.2861+02, .3124+02, .2892+02, .3022+02, .2923+02,-,532o+ol,.2985+02,-.1719+02,

305
47 66BR1
PHOTON ENERGY, (MEV)
CROSS SECTION, (MB),2954+o2,-.257o+Ol

59PR141 <G»2N).1560+02, .5370+01, .1591+02, .6320+01, .1622+02,- ,1300+01, .1653+02, .9110+01.1684+02, .1920+01. .1715+02, .2000-01, .1746+02, ,195o+Ol» .1777+02, .7230+01.1808+02, .2061+02, .1839+02, .3436+02, .1870+02, .3488+02, ,19Ol+o2, .3688+02.1932+02, .4834+02, .1963+02, .4282+02, .1994+02, .59 34+02, ,2o25+o2, .5613+02.2056+02, .5293+02, .2087+02, .4660+02, .2118+02, ,5070+02, .2148+02, .4256+02.2180+02, .4267+02, .2211+02, .4832+02, .2241+02, .4309+02, .2272+02, .3143+02.2303+02, .3408+02, .2334+02, .3081+02, .2365+02, ,2518+02, .2396+02, .3309+02.2427+02, .3137+02, .2458+02, .1378+02, .2489+02, .1157+02, .2520+02, .2037+02.2551+02, .2993+02, .2582+02, .1243+02, .2613+02, .1324+02, .2644+02, .1967+02.2675+02, .4420+01, .2706+02, .1024+02, .2737+02, ,2o2o+O2, .2768+02, .2820+02.2799+02, .2320+02, .2830+02, .1800+01. .2861+02, .6000+01, .2892+02, .7200+01.2923+02, .8000+01, .2954+02, .3000+01, .2985+02, .1670+02,

306
17 66BR1
PHOTON ENERGY,CROSS SECTION, (MB)59PR141 (G,3N).2799+02, .7400+00, .2830+02, ,5730+01, .2861+02,-,6800+00, .2892+02, ,381o+Ol.2923+02, .1670+01, .2954+02, .4170+01, .2985+02, ,4ci5o+Ol, .3ol5+o2, ,76oo+0l.3045+02, .9180+01, ,3o78+o2, ,75o0+0l, .31o8+o2, ,878o+Ol, .3138+o2, ,762o+Ol.3170+02, .1275+02, ,32o2+O2, ,l0l0+02, ,3233+02, ,1CI68+O2, ,3265+o2, .165o+O<2.3296+02, .1078+02,

225
231 64AL2
PROTON ENERGY, (MEV)
CROSS SECTION, (MB)

6C 12

(P»G)

,9790+00, .1293-01, .1047+01, .1389-01, .1093+01, ,158 0 -0l, ,1138+01, .1675-01.1183+01, .1771-01, ,1229+01, ,1961-01, ,1297+01, .2104-01, ,1365+01, .2295-01,1383+01, ,2343-01, ,1456+01, ,2486-01, .1524+01, .2582-01, .1616+0l» .2488-01.1331+02, ,1989-oi, ,1335+ 0 2, ,2370"0l, ,1345+02, ,2o86 O l.1361+02, .1755-01, .1370+02, ,1851-01, ,1379+02, ,1947-Ql,1354+02, ,1896-nl

-78 Example 2.

Spectra File

This file contains data dealing with tne spectra of neutrons,
protons, alpha-particles, photons, etc. Shown below is an example
of a neutron spectrum obtained with a peak bremsstrahlung energyof 14- MeV.
**#•*•***•*••**•*»•****•******•****#*•*#•***»**•****»•*•*•»***»•*••**»#***«.>* * • * * • * • *10033
14 65MU1
73TA181 (G»N)
NEUTRON ENERGY, (MEV)(DN/DEJ/E
C
DATA TAKEN WITH A PEAK BREMSSTRAHLUNG ENERGY OF 14 MEV,
.6020+00* .3091+05, .1005+01. .1691+05, .1391+01, .8331+04, .1793+01, .4042+04.2212+01, .1931+04, .2598+01, .9804+03, .3001+01, .5613+03, ,34o4+ol, .3679+03.3807+01, .2640+03, .4210+01, .1757+03, .4598+01, .1299+03, ,5ol7+ol, .7663+02.5403+01, .4730+02, .5804+01, .1418+02

Example 3. Angular Distribution File

Angular distribution of any reaction products are contained inthis file. The sample below gives -A_/A_ for a Legendre polynomial
fit to the neutron angular distribution obtained with a peak bremsstrahlung energy of 13 MeV. The neutron energy ranged from about.5 to 3.5 MeV.

20001
12 66MU1
73TA181 <G»N)
NEUTRON ENERGY, (MEVJ
ANGULAR DISTRIBUTION, (-A2/A0)C
BREMSSTRAHLUNG BEAM WITH PEAK ENERGY OF 13 »EV WAS USED.
CENERGY RANGED FROM ABOUT .5 TO 3.5

NEUTRON.5999+00,-.3185-02, .1187+01. .2535-02, .1672+01, .5184-02, .2132+01, .Ilo4~ol.2541+01, .2970-01, .2912+01, ,5158-ol, ,327o+Ol, ,894o-ol» .3577+01, ,1177+no.3909+01, .1*60+00, .4228+01, .1616+00, .4394+ol, .1678+00, .4561+ol, ,174o#•##******»#*****•******•**••****•*************•*•***•***»•**•••**•*•*•••*»*#••*

Example 4.

Manipulated File

The (y»p) cross section derived from the (p,y) cross section,
given by data set 225, by means of the detailed balance program.

30225
231 64AL2
6C 12 (G,P)
PHOTON ENERGY, tM£V)
CROSS SECTION, (MB>C
(P.G) CROSS SECTION USED TO GET (G,P) CROSS SECTION USING DETAILEDC
BALANCE PROGRAM.
.1687+02, .2809+00, .1693+02. .3203+00, .1697+02, .3785+00, ,17ol+o2, .4158+00.1705+02, .4548+00, .1710+02, .5206+00. .1716+02, .5852+00, .1722+02, .6669+00.2846+02, .1863+01, .2854+02, .1967+Ql, .2863+02, ,2Q7O+O1

79 Example 5.

Combination File

A sample of the data set in the combination file. This data
set gives the total neutron yield cross section, (y,xn). It was
obtained by combining data sets #s 3O4-, 305, and 306 from the crosssection file along with the appropriate neutron multiplicity factors.

40020
69 66BR1
5<?PRl41 (G.XN)
1
PHOTON ENERGY. (MEV)
CROSS SECTION* (MB)C
CG»XN) OBTAINED FROM {G»N)+2»(G»2N)+3*(G»3N).
C
305, AND 306. DATA CUTS OFF AT 29.85 M E V - T H E.8788+01.
.1003+02.
.1126+02,.1250+02.
.1374+02,.1498+02,.1622+02,.1746+02,.1870+02,.1994+02,.2118+02,.2241+02,.2365+02,.2489+02,.2613+02,.2737+02,.2861+02,,2985+02»

USED DATA SETS NUMBER 304,
M
OF THE N A N D 2N DATA.

, .9407+01, .1517+02, .9717+01,.4410+01, .9097+01, .0000.3388+02, .1034+02, .4524+02, .1065+02, .432 O +o2, .1096+02,.6455+02, .1158+02, .7315+02, .1188+02, .8025+02, .1219+02,.1221+03, .1281+02, .1379+03, .1312+02, .1614+03, .1343+02,.2229+03, .1405+02, .2510+03, .1436+02, .2894+03, .1467+02,.3356+03, .1529+02, .3310+03, .1560+02, .3199+03, .1591+02,.2661+03, .1653+02, .2404+03, .1684+02, .2094+03, .1715+02,.1656+03, .1777+02, .1572+03, .1808+02, .1512+03, .1839+02,.1250+03, .1901+02, .1288+03, .1932+02, .1385+03, .1963+02,.1345+03, .2025+02, .1219+03, ,2o56+o2, .1167+03, .2Q87+02,.9423+02, .2148+02, .9906+02, .2180+02, .1033+03, .2211+02,.9840+02, .2272+02, .8668+02, .2303+02, .9568+02, .2334+02,.7299+02, .2396+02, .8762+02, .2427+02, .7864+02, .2458+02,.4046+02, .2520+02, .5160+02, .2551+02, .619 O + O 2, .2582+o2,.3172+02, .2644+02, .4221+02, .2675+02, .3158+02, ,27 O 6+o2,.5490+02, .2768+02, .5117+02, .2799+02, .5864+02, .2830+02,.4120+02, .2892+02, .5605+02, .2923+02, .1569+02, .2954+02,.2836+02

Example 6.

.3175+02.5829+02.9955+02.1933+03.3143+03.2923+03.1837+03.1371+03.1116+03.9241+02.9612+02.5461+02.5890+02.4130+02.3354+02.1594+02

Evaluated Cross Section File

Samples of evaluated data for Pr-141. Smoothing of the data wasdone on data sets #s 305 and 306 as found in the cross section f i l e .
90305

26 66BR1

59PR141

PHOTON ENERGY, (MEVJ
CROSS S E C T I O N . (MB)C
SMOOTHED DATA P O I N T S .

,1750+02,,1950+02.
,2150+02,.2350+02,,2550+02,,2750+02,,2950+02,,4977+01,.5442+02,,4833+02,,3326+02,,2062+02,,1090+02,,4018+01,(G»2N)MARCH.74 HMG,1800+02, .1624+02,.2000+02, .5734+02,,2200+02, .4441+02,.2400+02. .3023+02,.2600+02. .1760+02,,2800+02, .9070+01,.3000+02, .2760+01

90306
12 66BR1
5<?PR141 (G.3N)
PHOTON ENERGY. (MEV)
CROSS SECTION. (MB)C
SMOOTHED DATA POINTS. MARCH.74 HMG,185o+O2,,2050+02,,2250+02,,2450+02,,2650+02,,2850+02,.2960+02, .1900+02,,5566+02, .2100+02,.4064+02, .2300+02,,2688+02, .2500+02,.1541+02, .2700+02,,7234+Ql, .2900+02,.4227+02.5236+02.3675+02.2367+02,13o3+o2.5760+01

1.2750+02,-.4751+00, .2800+02, .8382+00, .285o+O2, . 2 l H + o l , .2900+02, .3367+<)l.2950+02, .4655+01, .3000+02, .5976+01, ,3o5o+02» .7235+01, »31oo+o2, .85o*+ol.3150+02, .9755+01, ,3200+02, .1100+02, ,325n+o2, .1223+02, .33po+o2, .1348+Q2

-80 -

Examples of Computer-Drawn Cross Section Data

Figure 1 is an example of the computer-drawn cross section datafor praseodymium. The open circles show the a(y,n) data from the data
set #305 as found in the cross section f i l e .
The points show thesedata after smoothing. The smoothed data were then interpolated, to obtain values at every half MeV, and placed in the evaluated cross section
f i l e as data set #90305. The a(y,3n) data (the crosses show the basic
data and the line shows the smoothed data) were handled in a similar way.
Figure 2 shows the o-(p,y) data set #225 as found in the crosssection f i l e .
These data were used as input to the detailed balance
program; the output was the inverse reaction cross section and is shownin Fig. 3. The output was placed in the manipulated f i l e as data set#30225.

RCQ NO305

REFERENCE 66BR1

EXCIT- NUC 59PR141

POINTS
REF1CTIQN

47(G.2N)O
CD.•••©•.
©'•.

m LO

©

©

• ©

" ©
©o'p

O

a( Y ,3n) X 2

.©

• \ ©
© ©\ ©

CD o
.

. CO

©

©•.

CO

o
CO —
CO
CD

14

©

©
'.

©

+ 6-.

© .©

16

18

20

22

24

26

28

PHQTQN ENERGY, (MEV)
Fig. 130

32 - 34

- 81 -REFERENCE 64HL2

RCQ NQ
225
EXClT- NUC

GC 12

P0INT5RERCTI0N

231

(P.G)

00

2-00

0

4.00

6.00

8.00

10-00

12.00

14.00

POINTS231

PRQTQN ENERGY. (MEV]
Fig. 2
RCQ N0 30225

REFERENCE 64RL2

E X C I T . NUC

16

18

20

6C 12

22

24

REflCTIQN

(G.P)

26

28

PHOTON ENERGY. (MEV)
Fig. 330

- 82 -

I.V. Kurchatov Institute of Atomic Energy

The State of Work on Son-Neutron Nuclear Datain the USSR (Working Material for IAEA Consultants
Meeting on Charged Particle and Photonuclear
Reaction Data and for the IAEA X-Center Meetingin April-May 1974J"

Authors:
L.L. Sokolovskij
Yu.I. Penin
P.E. Chukreev

Moscow, 1974

(Translated from Russian lay the IAEA)

-83-

I.

BASIC INFORMATION Off THE CEKTER FOR ITOCLEAR STRUCTURE AND
REACTION DATA OF THE STATE COMMITTEE OH THE UTILIZATION OFATOMIC ENERGY

In accordance with the recommendations of the International Working
Group on Nuclear Structure and Reaction Data (l) the State Committee on
the Utilization of Atomic Energy of the USSR decided to set up a Center
for Nuclear Structure and Reaction Data.

This Center has been establishedin the I.V. Kurchatov Institute of Atomic Energy in Moscow.

At present

the staff of the Center consists of fifteen people including five physicists, two of whom are theoreticians and three experimentalists.
Head of the Center is Mr. F.E. Chukreev.

The

Apart from the physicists, theCenter also has technical staff who deal with the computing operations of
the Center and assist the physicists in their work.

The Center has its

own Videoton 1010B computer with a set of peripheral equipment for input,
output and storage of information.

The Center is working in close contact with the Data Center at the
Leningrad Institute of Nuclear Physics of the USSR Academy of Sciences
at Gatchina, with the Nuclear Data Center at Obninsk and with a numberof groups of physicists working at various research institutes andhigher educational establishments in the USSR,

The first phase of activity of the Center, which was set up in 1972,
involves three main tasks:
1.

Accumulating a sufficiently large amount of information on
atomic nuclei and nuclear reactions;2.

Establishing the computer capability to deal with theaccumulated material;

3.

Surveying and analysing the nuclear data requirements ofSoviet scientists—' .

The first of these tasks is being performed in close collaboration
with the Center at the Leningrad Institute of Nuclear Physics.

\J

Here and below by "nuclear data" we mean only non-neutron nuclear data,- 84-

Both Centers assemble all information on nuclei without
attempting any preliminary evaluation.

The collection of informationis one of the main tasks of the Centers and is being done by rational
division of the work between them with subsequent exchange of all theinformation collected.

Unless sufficiently complete information isavailable in a form which facilitates access to the evaluator andpermits automation of the routine work, it will be difficult to attract
highly qualified physicists to work on the evaluation of the nuclear
data necessary for solving scientific and technical problems.
The solution of the second task - the setting up of a system for
retrieving information from the files of the Center - is closely coupledwith the establishment of strict formats of storing information and thisquestion will be considered below.
It is intended that the Center will not only collect information but
will also organize the evaluation of the data necessary for solving
scientific and technical problems within the scope of the State Committee
on the Utilization of Atomic Energy and for fundamental research.

The Center shall provide non-neutron nuclear data for the following
principal applied fields:

1.

Reactor construction

2.

Nuclear fusion research.

3.

Safeguards technology

4.

Material analysis using nuclear-physics methods

5.

Production and application of synthetic radioactive isotopes

6.

Shielding and dosimetry

7.

Medical applications of radioisotopes

8.

Nuclear physics, astrophysics, etc.
A more detailed account of the requirements of each of these fields

is given in Bef. (2).

-85-

At the moment

it is difficult for us to define more clearly thefield of activity of the Center, because our analysis of user requirements is not yet complete and a list of priorities has not yet beenvrorked out'. Nonetheless it can be said that in the field of reactor
construction the bulk of the work on evaluating nuclear data v:ill beconcerned with problems related to monitoring neutron fluxes inside
reactors.

(a)

To solve these problems it is necessary to know:

The thermal and resonance activation cross-sections of elements
used as neutron detectors (Na, Mn, Cu, 1 0 3 Rh, V, Dy, 1 7 7 L u , W,
Ag, Ft, Au) and the lifetimes and decay schemes of product nuclei.
In order to estimate the background, the same data are necessary
for constructional materials (Ni, Al( 235 U f 2 3 8 ^ 2 3 9 ^ ) .

(b)

Fe, Cd) and nuclear fuelActivation cross-sections of elements used as threshold detectors(0, P, S, Al, Mg, Pe) and the lifetimes and decay schemes of
product nuclei.

One of the main tasks of the Center is to provide non-neutron
nuclear data for research on controlled thermonuclear reactions which
is being conducted intensively at institutes of the State Committee on
the Utilization of Atomic Energy.

For this research it is necessary tohave data on the interaction cross-sections of light nuclei at energies
of several MeV.

It is also necessary to have data on the gamma—ray

spectra and lifetimes of nuclei produced by interaction of the productsof thermonuclear reactions with construction materials, and materials
which can be used for breeding tritium (Li, Be, C, F, Fb, Mo, Zr).

An analysis of the nuclear data necessary for thermonuclear researchis given in Refs (3, 4 ) .
The above list of the principal applied fields of science andtechnology which need to be supplied with non-neutron nuclear data cannot,of course, be considered conclusive.

The present trend of applying toother fields methods devised to solve nuclear problems will undoubtedly

- 86-

present evaluators with. new, perhaps not just purely nuclear problems,

II.

WHAT NUCLEAR DATA ARE REQUIRED IN PRACTICE ?

The range of nuclear data needed for the widespread introductionof nuclear techniques to science and engineering was adequately describedat the 1973 Paris Symposium on Nuclear Data in Science and Technology.
One of the main conclusions of this symposium is that apart from data on
the structure of nuclei, their radioactive transformations and nuclearreaction cross-sections, it is also very necessary to have data on the
stopping power of various substances and the ways in which the energyof nuclear radiation is dissipated in various media.

On the whole, the practical requirements for nuclear and atomic data
are properly reflected in the draft questionnaire sent out by Mr.A.Lorenz
In our opinion this questionnaire needs to have only one thing added to it
and that is a line for "nuclear moments of excited states".

III.

THE STRUCTURE OF INTERNATIONAL COLLABORATION IN THE COLLECTIONf
EVALUATION AND DISSEMINATION OP NUCLEAR DATA

Considerable experience has now been gained in the operation of thefour neutron centers (Obninsk, Brookhaven, Saclay, Vienna).

Future inter-national collaboration in the field of non-neutron data should, or course,
be organized on the basis of the methods recommended for international
co-operation in the field of neutron data.

At the same time, however, these methods should not just be transferred mechanically since there is a much greater volume of non-neutron
nuclear data, having a wider sphere of application.

In our opinion, the establishment of an international network of
non-neutron nuclear data centers should be accomplished in several stages:

-87 -(1) Arranging the exchange of information on published nuclear-physics
research.
(2)

Organizing joint evaluation;exchanging evaluated data;(3)

Setting up a system for the collection and exchange of experimental
data (of the EXFOR type).
This point of view is based on the fact that sufficient experiencehas been gained in the preparation of keywords abstracts, and co-operation
can soon be commenced.

Our specific proposals relating to the establish-

ment of an exchange system are given below (Section N ) .

It is impossible to carry out joint work or co-ordinated work on
nuclear data evaluation without establishing accessible, comprehensive
libraries of abstracts, with easy automatic search for the material required.

The collection and exchange of experimental data, recorded in a definite
format, as is now done in the neutron centers, are problems demanding asolution - the format must be worked out and improved on the basis of theoperating experience gained by evaluators.

The volume and scope of theexperimental data to be compiled by the centers will have to be dictatedby the evaluators.

Publications on, non-neutron nuclear data contain alarge and continuously growing volume of information:

experimental

techniques are improving, the number of reaction channels studied simultaneously is increasing, etc.

Another important question is the proper balance between centralizationand de-centralization with regard to the collection, evaluation and distribution of nuclear data.

In principle, two systems can be envisaged.

The first system is based on a central "bank" of information, into
which material from regional centers is fed, and which reproduces thematerial and supplies it to all the centers.

The second system involves direct two-way connections between theregional centers similar to the procedure adopted for neutron data.

Since

-88-

the 4-center system has been proven to be satisfactory in practice, we
can see no reason for the adoption of any new system of inter-center
co-operation.

All that is necessary is to draw up common data-preparation

rules, depending only slightly on the type of computer technique, thus reducing the number of computer programmes required for the exchange procedure.

If the centers prepare the information according to a standard
pattern, not depending on the computer technique employed, no additional
programmes will be required generally.

With this type of information

preparation, a central "bank" is simply not necessary.

IV.

PROPOSALS FOB THE EXCHANGE OF IMFOBMATION ON NUCLEAR-PHYSICS P.ESBAP.CH

No significant development of work on the collection, evaluation anddistribution of non-neutron nuclear data is possible without joint efforts
by the centers in different countries.

Without a clearly defined system

of international collaboration it is not possible to perform satisfactorily
the evaluation of non-neutron nuclear data and the job of the national
centers may thus be rendered difficult.

In our opinion, the first step of international collaboration in thisfield is to agree on the exchange of information on nuclear physics fromwhich the major part of the non-neutron nuclear data derives.

We believethat the development of a future world-wide information system for data on
the structure of the atomic nucleus and nuclear reactions should startwith the exchange of bibliographic material (e.g. keyword abstracts).
These abstracts could be produced jointly, the work involved being divided
in some way between the physicists of many countries.

With the essentialcondition that all the information collected must be exchanged^ thisdivision of the work is convenient for the following two reasons:(l)

It increases the speed with which information on work performed
is supplied to the evaluators and this enables the latter to deal
with a wide range of initial data.

89"

(2)

It overcomes the language difficulties, which at the moment
sometimes result in annoying errors when the work of Soviet
scientists is abstracted abroad.

If the editors of nuclear-physics journals adopt the IWGNSRD recommendations (l) and the abstracting is done in keywords, data on theworks performed will be supplied to the information network more quickly
and language difficulties will be overcome.

At the same time, however,a complication arises which we think is worthy of attention.

If theabstracts are to be prepared by the authors of the works themselves,
their contents will strongly reflect the personal views of the authors
and the abstracts will thus be subiective.

This kind of subjectivity

may be particularly marked in the "comments" section (relating to theparameters of the experimental facility).
subsequent work of evaluation.

This greatly complicates the

In performing the evaluation, therefore-

the evaluator should without difficulty be able to establish" contact withthe author in order to seek clarification regarding the methods used.

As long as editors do not all publish keyword abstracts, theabstracting should be divided among a number of regional centers, dependingon the language and the place of publication.

With this kind of division,as soon as the abstracts of nuclear-physics works were published (or even
earlier), they could be added to the libraries of groups or organizations
requiring nuclear data.
The Soviet centers would themselves undertake the abstracting ofworks published in the Russian language.

V.

KEYWORD ABSTRACTS IN VARIOUS SYSTEMS (lNISf EXFORf NDP). RECOMMENDATIONS.
As has already been stated above, international collabiration in thecollection, evaluation and dissemination of non-neutron nuclear data should
start with +he exchange of abstracts, written in some system of "keywords",of nuclear-physics works which have either been published or are being prepared for publication.

-90-

Before proceeding to deal with specific recommendations on a common"keyword" system for all national centers and on the methods of preparing
abstracts on the basis of this system} we should like to deal in somewhat
greater detail with three already existing systems and to assess theadvantages and disadvantages of each of them.

Here, we shall consider

only that part of the keyword abstract in which the actual content of
the work is described.

THE NDP SYSTEM

To gain a better idea of the changes in the content of abstracts ofpapers in the keyword system adopted by the Nuclear Data Project group,
we must turn to the year 19&9.

In Nuclear Data Sheets Vol. 3, No. 1 (1969)

we find the following abstracts:
3

'S

37

C1

D

67Wil4:Eg, J* , E , J

E

67JeOl:36

S(p,y), E = 1.147, By, Jy, P, y (theta), sigma (By),widthThese abstracts give a definite idea of the content of the paper, but they
are not very satisfactory for an evaluator embarking on work with referencematerials.
guide.

Such an abstract can serve merely as a kind of useful reference

It was therefore quite natural that the NDP group itself found thistype of abstract unsatisfactory and that it went over to the type used in
1973, i.e.

37

C1 E

72A151!

NUCLEAE REACTION 3 4 S (a, py), E = 10, 12, 14 MeV;
measured sigma (E, Ey, theta), yy-coin.
duced levels, J, 1T* , mixing ratio.

35

P

D

72Go31:

RADIOACTIVITY 3 5 P ;Ci de-PHSTB 6 3O3

measured Ey, Py-coin, T i ;deduced J, IT, log ft, Q.

3^S deduced levels.

PRVCA C6 820(N.D. Sheets, Vol. 9, Ho. 6 (1973) and Vol. 9 No. 1 (1973) respectively.)

-91-

The advantage of the latter system of keyword abstracts over theearlier system is obvious and consists in the fact that the rules forcompiling the abstracts include appropriate grammatical and syntacticalrules.

Obviously there is no need here to speak in detail about therules for compiling the keyword abstracts which are applied at presentby the Nuclear Data Project group and which have been very fully describedby Dr. W.B. Ewbank.

Nevertheless, the introduction of the verbs "measured","deduced", etc. is of evident advantage.

These action words divide the(experimental) paper very exactly into two essentially different parts,
the "measured" and the "deduced", which is very important for the evaluator.
As a result, the content, and also the significance, of the abstract aremuch more complete and clear.

Placing a comment at the end of the abstract

adds greatly to the information concerning the nature of the experiment andthe methods used.

One other undoubted advantage of abstracts based on the

NDP system is the fact that, for all their laconicism and rigorous form,
they can be read satisfactorily by both human subjects and machines.

THE INIS SYSTEM

To make a better comparison of the various systems, we need topresent two abstracts for one and the same paper:
067619Coban, A.;

Lisle, J.C.;

Murray, G.; Willmott, J.C.

States of . Se observed following decay ofBr.

Particles Nucl. (1972) v. 4 P. 108-125
energy levels}
polarity;energy-levels transitions;parity, selenium 74;

spin,angular correlation;beta-plus decay;

ratio;

energy spectra;

bromine 74;

gamma radiation;

gamma spectra;

properties, parity;

q-value;multi-

branching
ft value;

K capture;

spin,(INIS Atomindex, Vol. 4, No, 15 (1973).
74

Br D

72Co32;

RADIOACTIVITY 7 4 Br measured E , I , YY-C<>in,

YY (theta), Ti, J(ce);deduced log ft. '^"Se deduced

levels, J,TT , T A > JCC.

PANUA 4 103(N.D. Sheets, Vol. 9, No. 1 (1973)).

nuclearApart from the disadvantage that the INIS abstract is longer
than the HDP one, it has what we consider to be a further drawbackin that it does not show very clearly what has been msasured by
the authors and what has been accomplished as a result of theirmeasurements and certain theoretical assumptions.

As mentioned

above, this is extremely important for the work of the evaluator.
Moreover, a comparison of these two abstracts demonstrates clearly
the advantages of the grammatical rules adopted by NDP, which afforda means of reducing the length of the abstract, it can be comprehended
quite easily by the human reader, but it is still at the level ofthe 1969-type NDP abstract.

- 93 ~THE EXPOR SYSTEM

This system is intended mainly for the exchange of all the information contained in a paper and it is therefore extremely cumbersome andvery difficult for the human subject to read. Since in the initial stageof getting international co-operation under way it is not worthwhile nor is it feasible, owing to the complexities and.uncertainties involved to consider the question of exchanging all information derived directlyfrom an experiment, we believe that the introduction of EXFOR as astandard system would be inappropriate.

Prom everything that has been said above it follows that, in our
opinion, the most suitable system for preparing abstracts is that adopted
by the Nuclear Data Project group and based on the use of key words. However, even that system requires a slight modification, which consists inthe following:

In our opinion, it is necessary to elaborate and issue rules for thecompilation of abstracts in key words, taking into account all of thecodes to be used in the exchange (see below); also, to make certain refinements in these ruels, .bearing in mind the need for mechanical searches ofabstracts containing useful information for work under consideration.

V.

PROPOSALS FOR THE EXCHANGE OF INFORMATION BETWEEN REGIOML CENTERS(NON-NEUTRON NUCLEAR DATA)
V.I

Information on the gradual compilation of data at each Centre ispublished by IAEA communications to this effect are sent from the individual
centres on the subject of non-neutron nuclear data.

- 94 -

V.2. Exchange channels
We believe that exchanges of material of the different centres shouldtake the form of a direct exchange between the centres, like that of thecentres concerned with neutron data. All that is required is to modify
the existing rules for the preparation of materials by the centres so as
to avoid complex processing.
V.3» Content of exchanged information
1.

Key-word abstracts of papers available to all users ofnational centres.
2.

Evaluated data: at present the most practical arrangement is theexchange of abstracts.

V.4« Technical conditions for the exchange of abstracts
prepared in keyword form
V.4«l»

Symbols

Capital letters of the Latin alphabet, Arabic numerals, special
symbols such as "space" or "" and the control symbols "carriage return"and "raise line" are employed as they are the most widely available to allusers. The special symbols used for dividing up the fields of the abstract
include »:»"•", "» and "&". If other symbols - for example, the lettersof national alphabets of lower-case Latin letters - it is essential to point
this out in the accompanying documentation.
Basis for the above instructions:
1.

GOST-13052-67» "Alphabetical-numerical codes for computers";2.

ISO recommendation 646-71, "Six- and seven-bit set of symbols for
information exchange and processing".

95 ~V.4.2. Machine codes
For the coding of these symbols in a form which could be adopted
for computer processing it is necessary to use the seven-bit code ASCII or
the BCD code. The code type (ASCII or BCD) must be indicated in theaccompanying documentation.
If the number of symbols is increased, a table with their codes
must be included in the accompanying documentation.
Basis for the above instructions:
1.

GOST-13052-67| "Alphabetical-numerical codes for computers";2.

ISO recommendation 646-71, "Six-and seven-bit set of symbols for
information exchange and processing", and ISO-2022, "Means of expanding
the seven-bit set of symbols".

V.4«3»

Machine-readable media for information exchange

These are nine-track 12.7 mm magnetic tapes with the standard
track arrangement (see GOST-12065-66, "Magnetic tape for computers", andISO recommendation I863, "Nine-track magnetic tape (32 bytes per mm)"), a
recording density of 800 bytes per inch (32 bytes per mm) and tape startand end markers (foil).
If the amount of information to be exchanged is not very great(not more than 100-200 kilobytes), one may use the eight-track standard
paper tape - either in the form of a roll or folded like a concertina(Leporello folding) - 25.4 mm wide and a step length of 2.54 nim (inaccordance with GOST-IO86O-68, "Perforated tapes for computers").

V.4«4 Arrangement of information on tapes
VJhen magnetic tapes are used for information exchange, thearrangement of theinformation bits and the parity byte (which is added

-96-

to any odd number of "units" in a transverse row) "by track number may
differ from ISO Recommendation 9^2, "Arrangement of a seven-bit code ofsymbols on a nine-track 12.7 mm tape", since the arrangement of information by magnetic tape track has not yet been standardized in the Soviet
Union (see GfOST-10265-66, "Magnetic tape for computers").
This also applies to the special longitudinal and parity
control symbols at the end of a record and to the size of the space
between records.
Whereever possible one should comply with the above-mentioned
ISO Recommendation $62 and ISO Recommmendation 1001, "Marking of magnetic
tape and file structure for information exchange".
If the recording method differs from these recommendations, onemust specify: the arrangement of the information bits by track number;whether there are control symbols at the end of a record, the size of theinterval between records and, whether there is any special record
denoting the end of a file.
In all cases one should indicate in the accompanying documentation the number of files, the number of records in a file, the record
length and the number of bytes in a record; if there is a record headingor a control sum obtained by means of a "mathematical guarantee", thisshould also be specified.
When perforated tape is used for information exchange, there
must be a label at the beginning of the perforated tape and the arrangement of the seven-bit code must correspond to GOST-15029-69, "Arrangement of a seven-element binary code on perforated tapes", and it is essential
to have in the eight track a check that the number of perforations in anytransverse row is even.

97

GENERAL COMMENT

These recommendations for the development of a standard for
information exchange within a system of non-neutron nuclear data
centres are based on those Soviet standards

and ISO recommendations

which do not contradict one another. The ISO recommendations wereprepared by the ISO technical committee TC/97 on "Computers andinformation processing", in which the Soviet Union has played an active
role.

VI.

ESTIMATE OF THE TRUE VALUE OF A MEASURED QUANTITY
Let us assume that one has the results of n independent measurementsof some quantity and that these results (x-,, x^, ... x ) are free of
crude and systematic errors (i.e. that incorrect results have been
discarded, and that corrections for systematic errors have already been
made ). Estimating the true value a of a measured quantity means:

1.

Indicating a function f(x,, Xp ... x ) of the measurement results
which gives a sufficiently good approximation to the value of a(such a function is called a point estimate, or simply an estimateof the value of a);2.

Indicating the boundaries of the interval which, with a specified
probability, covers the true value of a (such an estimate is calleda confidence estimate).

The following point and confidence estimates of the true value a ofa measured quantity are given on the assumption that random measurement
errors are subject to the normal law of probability distribution and that
only symmetrical confidence estimates having the form of the inequality

are considered.

-9.8 If one knov/s for the results x-,, X2 ... x

cf random measurements

the values of the weights or the ratios of these values

where o. is the dispersion of x-, then the confidence estimate of thetrue value a. of the measured quantity has the formla-*|< t(pjk) Ss
where the point estimate

and the empirical standard

In the formula for the confidence stimate, k = n-1 (the number of degrees
of freedom), P is the confidence coefficient and the value of the factort(P;k) is taken from tables compiled with the help of a Student distribution.

If, on the other hand, the mean square error of the independent measurements 0. is not known beforehand, one uses instead the empirical standard

which serves as an estimate oof the parameter 0.
In such a case the confidence estimate assumes the form

while the point estimate

t7 - iWe

finally have the following two expressions for point estimatesof the quantity a for known and unknown a•:a - 7 ± £.

- 99

The value of the empirical standard, like the actual measurement
results, is subject to random fluctuations. If we determine S

from avery laTge number of measurements, we obtain a value which may differ
by a small amount from its limiting value o. When n is not large, however,then S

is affected by random errors, these errors obviously being

smaller the greater the value of n. Exactly as with the measurement
results, there exists a distribution law which offers the possibilityof estimating a confidence coefficient relating to the probability thatthe value of S determined .from n measurements will differ from o by
a given factor.

If we define jL

in such a way thatthe distribution law for this quantity will be known as a /(. -distribution,
characterized by a definite assymetry which is particularly strong forlow values of n. For larger values of n this distribution becomes anormal one, with a dispersion

This formula makes it easy to estimate an error in the determinationof o. Generally speaking, the formula holds for n > 30, but for very roughestimates it may also be used for lower values of n.
If n = 25,(S* (SJ s S—G~i.e. 0 is determined to within about

15$. In this case there is obviously no sense in performing calculations ofSto more than two significant figures, i.e. one should write S n = 2.3

rather than 2.34 or S n = O.52 rather than O.5231.
If n = 50, the accuracy of the determination of S is about

- 100If n « 10, the error in the determination of S exceeds 25;J and one
should as a rule perform calculations to one significant figure if thatfigure i s greater than 3 and to two significant figures if the firsti s less than 3. If S^Q = 0.523, then we take one

significant

figurefigure- i . e . S10 = 0.5; if S1Q = 0.124, one should write S,Q = 0.12.
SYSTEMATIC ERRORS AND STATISTICAL -ViEIGHTIMGTaking account of systematic errors constitutes one of the most complex
problems facing the evaluator. Although it is assumed that, in publishing
their results, authors will take account of systematic errors and make theappropriate corrections, a simple analysis of the results neverthelessshows that this is not entirely the case.

An analysis of data on the measurement of a single gamma transition
with an energy of 5298 keV in theN(n,y)

N reaction shows the following.

In 10 publications in which the gamma spectrum for the above reactions wasmeasured, the following values are quoted for this transition: 5298.53.+O« 30;
5299.03+0.43; 5296.7* + 0.4; 5298.3+0.3; 5297.6+0.7; 5298.2+1.5;
5297.8+0.35; 5298+1; 5298.I+O.6 and 5298.25 +0.08. The mean valuB quoted
by us in reference- [6] is 5298.21 _+ 0.32. The gamma transition energy
value marked by an asterisk deviates rather sharply from the group ofvalues as a whole. However, to attribute this to an "aberration" on the partof the experimenters would appear to be incorrect, since another line intheir spectrum, 5267.8, a.lso deviates from the general block of data,
whereas two further gamma lines, 5561.5 and 5532.7, fit perfectly into it.
In our opinion this can be explained by the existence of a systematic error
in a particular sector of the spectrum. Unfortunately this is only ahypothesis, and it is therefore very difficult to propose something definite
as regards eliminating inaccuracies of this kind. In these cases the bestprocedure would seem to be to regard the value as an "aberration" and leave
it out of the evaluation.

Just as important, in the evaluator's work, as taking account ofsystematic errors, is allowance for the statistical weighting of a particularmeasurement result. In the above-quoted formulae for point evaluation andconfidence interval, the statistical weighting is determined only by scatter.
In actual fact the situation is not like this. In a way, the statisticalweighting assigned to a measured value obtained in a work should include
such factors as the quality of the instrument, the measurement method and-101 -

even the reputation of the erperiir.onter, i.e* the level of confidence
in his results. The development of generally accepted criteria governing
attribution of more objective statistical weighting to the results of eachwork is extremely complex and is a task for the future. At present wo can
only use the value o for introducing statistical weighting into the pointevaluation and the confidence interval.

VII.

THE CENTRE'S PLANS TO "SSTABLISU FILES C? EVALUATED DATA TC E 5 T
THE REQUIREMENTS FOR SUCK DATA
Analysis of

the requirements of scientists working both for theState Committee on the Utilization of Atomic Energy and in institutesof the USSR Academy of Sciences has shown that the primary requirements
for nuclear data for non-energy purposes are very wide and are as follows:1.

Decay schemes of radioactive isotopes (more accurately, knowledge 'of
all those radiations which accompany radioactive decay);

2.

Activation cross-sections for beams of charged particles and photons;

3. Energy losses on passage of charged particles and photons throughmatter-.

These are the requirements of' a wide circle of scientists representing
not only physics but also- medicine, oceanography, agriculture etc.

Prom "this list it is clear that the requirements of Soviet scientists
are practically the same as those of scientists in other countries.
To meet these requirements, we propose to establish files of evaluateddata on tape. Experience of operating centres shows that without anautomatic system of retrieving and disseminating evaluated data it isdifficultto meet the requirements of consumers.

- 102 -It is quite clear that even the stablishment of only three files
will require several years of intensive work by a very large group of
experimentalists and evaluation specialists.

We expect to complete first the file on radiations accompanying
radioactive decay, since the maximum amount of information exists in thisfield. We are not yet in a position to state the date of completion ofthis work, "because new experimental research makes it continuallynecessary to refine existing data.

VIII. GROUP CF EVALUATORS IN THE USSR

Apart from this Centre, there exist a number of groups of highlyqualified physicists engagen in compilation and evaluation work in the
USSR (see Ref. [l]).

IX.

FORMULATION OF GUIDE FOR AUTHORS
The preferences of the editors of nuclear physics publications arepresented in Ref. [l]. In this connection it is appropriate to raise thequestion of a guide for authors. A suitable basis for such a guide would
be the "Recommendations on methods of communicating results" by Taylor,
Parker and Langenberg

It should be noted that this "Guide" is in obvious contradiction
to the policy followed by the overwhelming majority of editors of nuclearphysics publications. The editors require results with descriptions of themethods involved kept to a minimum.

The only way out of this contradiction is to apply as widely as
possible the system of depositing articles at information centres andpublishing only the abstracts. However, authors will only do thisunwillingly, preferring to reduce their texts. This is obviously because
the authors fear that their deposited work will never be read by anybody.

- 103 -X.

AN INTERNATIONAL PUBLICATION ON COMPILATIONS AMD EVALUATIONSSuch a publication should be in the form of a small journal

appearing 2 - 3 times a year. It should contain information on newcompilations and evaluations appearing in print or in the form oftape files. This publication will help avoid duplication of effort
at information centres.

REFERENCES[l]

Conclusions and Recommendations 1st meeting of the Int. Working
Group on Nucl. Structure and Reaction Data, Vienna, 13 - 17 March 1972

[2]

KULAKOV, V.M., RUDAKOV, V.P., Paper presented to the 1st Meetingof the Int. Working Group on Nuclear Structure and Reaction Data,
Vienna, 13 - 17 March 1972.

[3]

CHERNILIN, Yu.P., YANKOV, G.B., - 2nd Int. Conference on Nuclear
Data for Reactors, Helsinki 1970, Conf. Proceedings, Vol. 1, p.49»
IAEA Vienna, (1970)[4]

YANKOV, G.B., Paper presented at the Conference on Neutron Physics,
Kiev, 1971.

[53

Memorandum and draft questionnaire prepared by A. Lorenz, 6 Feb. 1974*[6]

SOKOLOVSKIJ, L.L., IGNATOCHKIN, A.E., Energii i intensivnosti ydlya calibrovki Ge(Li) detektorov v diapozone 3 - 10 MeV (Gamma-ray
energies and intensities for calibrating Ge(Li) detectors in therange 3 - 1 0 MeV) in Nuclear Data in Science and Technology (Proc.
Symp. Paris, 1973) £, IAEA, Vienna (1973) 431.

[7]

TAYLOR, B., PARKER, V., LANGENBERG,D., Fundamental constants andquantum electrodynamics), page 21, Moscow, Atomizdat (1972).

- 104 -Computerized Libraries of Nuclear Data for Applications
S. Pearlstein
April 1, 1974

The Evaluated Nuclear Data File (ENDF) formats described in ENDF 102
Vol I (BNL 50274) vere primarily constructed for neutron cross section
data. The widespread acceptance of ENDF further demonstrated the advantagesof computerized libraries and led to extensions of the format to include
other data.
Two types of nuclear data useful in applications are radioactive
decay and capture gamma ray energy spectra. Although the basic data
might be compiled in considerable detail pertaining to nuclear structure,
it is often desirable to process the data into simpler forms for certain
applications consisting of such quantities as average radiation energies
and major intensities.
Formats and procedures for radioactive decay data in ENDF are describedin Appendix A. The information described is important to reactor fission
product burnup, decay heat, and other applications. These formats werelargely developed by 0. Ozer of BNL, C. W. Reich of Aerojet Nuclear, andR. E. Schenter of HEDL. Data for over 825 nuclides were supplied in the
ENDF format cooperatively by the Gamma Ray Spectrum Catalogue and the
Hanford Engineering Development Laboratory group. In the number relating
to fission products there were 57 delayed neutron precursors, 6 alphaemitters, 712 unstable nuclides, and 113 stable nuclides. There arebeta-ray spectra and/or gamma-ray spectra for 200 nuclides.
In response to suggestions that the 4 world neutron data centers
also exchange neutron capture gamma-ray spectra a draft proposal of
the information felt important enough to be included was preparedby M. R. Bhat of BNL. This is described in Appendix B. The reductionof experimental capture gamma-ray data to evaluated data sets supplemented
by theory where necessary has been performed for a number of nuclides.
One such report is ENDF-186 (BNL 50379) by M. R. Bhat et al. entitled"Neutron and Gamma Ray Production Cross Sections for Silicon". The
ENDF formats for photon production data are divided into four mainparts consisting of multiplicities and transition probability arrays,
photon production cross sections, photon angular distributions, andcontinuous photon energy spectra. The ENDF formats are describedin ENDF-102 Vol. 2 (LA-4549) and will not be presented here.
The cases discussed here are examples of nuclear structure data
reduced to forms suitable for reactor shielding and decay heat applications
but which have use in other applications as well. Other types of nuclear
data that are needed in the form of computerized libraries can probably be
developed along similar lines.

- 105 -Appendix A
Enclosure 1. ENDF Formats and Procedures forRadioactive Decay Data
Enclosure 2. Kr-85 Data in the ENDF Format
Enclosure 3. Kr-85 ENDF Data Processed by
Code LISTFC (Described in
ENDF-110)

Enclosure 1

6.7

Formats for Radioactive Decay Data

(MT=457)*

The spontaneous radioactive decay data is given in section 457.

This

section is given for materials that are single nuclides in their ground stateor an isomeric state (An isomeric state is defined as one having a larger
than 0.1 second half life.)

The main purpose of MT=457 is to describe

absolutely the energy spectra resulting from radioactive decay and give
average parameters useful for applications such as decay heat studies.

The

information in this section can be divided into three parts:
I.

General information about the material
ZA=

Designation of the original (radioactive) nuclide (= 1000*2+A)

LIS=

Isomeric state flag for original nuclide (LIS=O, ground state;
LIS = 1, first isomeric state; etc.)

T^=

Half-life of the original nuclide (seconds)

A Tv

=

Uncertainty in the half-life (should be treated as one
sigma variance)

NAV=

Total number of average decay energies given.

Ex»AEx=Average decay energy (eV) of x radiation and its uncertainty (eV)for decay heat applications.

The 3, y, and a energies are

given in that order with space reserved for zero 8 or y entries.
All non-y and non-a energies are presently included as P energy.
The a energy includes the recoil nucleus energy.
II.

Decay mode information - for each mode of decay:
NDK=

Total number of decay modes given

RTYP

=

indicates the mode of decay,
decay modes defined:
Variable

Mode of decay

0.0yGamma decay (not used for Mode of Decay)

1.0

S"

Beta decay

2.0

0*"

Positron and/or electron capture decay

3.0

IT

Isomeric transition(will in general bepresent only when the state being considered is an isomeric state)

4.0aAlpha decay

5.0

fT ,n

Neutron emission (generally given for
delayed neutrons)

6.0

SF

Spontaneous fission

- 107 -RFS=

Isomeric state flag for daughter nuclide.

Q=

Total decay energy (eV) available in the corresponding decay
process.

(Fixed point number)(This is not necessarily the same as the maximum

energy of the emitted radiation.

In the case of an isomerictransition Q will be the energy of the isomeric transition.
For both &and 0~, Q equals the energy corresponding to

the mass difference between the initial and final atoms.)

A Q=

Uncertainty in Q value (eV).

BR=

Fraction of the decay which proceeds by the corresponding
decay mode.

(Eg.

If only P~ occurs and no isomeric statesin the daughter nucleus are excited then BR = 1.0 for P~
decay)
A BR
III.

=

Uncertainty in BR

Resulting radiation spectra
STYP=

decay type (Use Mode of Decay variable list)

NSP=

total number of spectra.

E and A E=

energy (eV) or radiation produced (Eg-, Ep+, E y ,etc.)

I and A I=

intensity of radiation produced.

ICC andA ICC=

internal conversion coefficient

F and A F=

normalization factor (absolute intensity/relative intensity).

NE=

total number of energy points

6.7.1

Formats(NSP may be zero)(arbitrary units)

The structure of this section always starts with a HEAD recordand ends with a SEND record.

The section is divided into subsections as follows:[MAT,1/457/

ZA

AWR

LIS

b

b

NSP

[MAT, 1/457/

T^

AT^

b

b

2*NAV

NAV

Ep

A Ep

E.

AE

Ea

AEa

]

HEAD

]

LIST

- 108 -[MAT, 1/457/

ZA

AWR

RTYPX

[MAT,1,0/

6*NDK

NDK

AQX

BRj

A BRj

STYP

b

b

b

6*(NE+1)NE/

Repeat NSP times

F

AF

b

b

b

b

[omit if NSP=O]

E

AE

I

Al

ICC

A ICC

]

LIST

b

b

b

b

b

b

]

SEND

*The section MT=453 is renamed:

6.7.2

/

AQNDKBRNDKRFSN D K[MAT,1,457/bInduced reaction branching ratios.

Procedures
1. The initial state of the parent nucleus is designated by

LIS which equals 0 for the ground state and equals n for the nth isomericstate.

Only isomeric states are included in the count of LIS.

(In other

Files isomeric and non-isomeric states may be included in the count of levels.)Radioactive decay data need be given only for initial isomeric states withhalf-lives greater than 0.1 seconds.
2. The average energy 1" and its uncertainty A E is presently
given for three types of radiation although the format does not limit the
number.

The average decay energy and its uncertainty for beta, gamma, andalpha radiation must be specified in that order with space reserved forzero or unknown information.

The average alpha energy also includes therecoil energy but the alpha energy alone can be separated out by multiplying
by the usual

factor, where M
M R + MAR

and M. are the masses of theA

recoil nucleus and alpha particle respectively.

The beta radiation includes

the contribution from beta, positron, and conversion electron decay andpresently includes the average delayed neutron energy as well.

- 109 -3.

The symbol RTYP indicates the mode of decay as determinedby the initial event.

A nucleus undergoing beta decay to an excited stateof the daughter nucleus which subsequently decays by gamma emission is in
the beta decay mode.

In general an RTYP=0, indicating gamma mode of decay

will not be used since decay initiated by gamma emission is classified
as an isomeric transition requiring RTYP=3.

An isomeric state of thedaughter nuclide resulting from the decay of parent nuclides is designatedby RFS (fixed point number) following the procedures used for LIS.

Q

represents the total energy available in the decay process and is equal
to the energy difference between the initial and final states.

The

branching ratio BR for each decay mode is given as a fraction and thesum over all decay modes must equal unity.
4.

The energy spectra should be specified if known.

decay type STYP should be specified using the RTYP variable list.
spectra are described using STYP=0.

Gamma

Relative intensities can be specified

and normalized absolutely by multiplication by F.
are given, F must equal unity.

The

If absolute spectra

The intensity I should total the contribu-

tions from all decays leading to radiation within a particular decay type
STYP having an energy E A A E.

The internal conversion coefficient shouldbe the sum of all the partial conversion coefficients.

- 110 -Enclosure 2

ENOF/B-IV I•ISSION PRODUCT FILE (PRELIMINARY)

03.60850* 4 B.42691*
0.00000«
e.00008*
36-KR- 15 ANC

1
2

0 0 0
36 1451
0 j 38 1451e
38 1451
7/73
PREPARED FOR FILE
38 1451CM*]
REFERENCES Q - 1973 REVISION Of WAPSTRA-GOVE MASS TABLES,
38 1451
OTHER DATA NDS-1971
36 1451!
F I R S T - F C R B I C D E N I U K 1OUE SHAPE CORRECTION CONSIDERED IN DERIVING
38 1451<)E-BETA FOR GRCUND-STATE BETA TRANSITION
36 1451]
HALF-LIFE N.F..HOLDEN CHART OF THE NUCLIDES (1973)
38 1451
AND PRIVATE COMMUNICATION (SEPT. .1973).
,36 1451
1
38 1451491
12
1
1
38 1451457
ia{36 1 03.60850* 4 8.42696* 1
2 138 1457
0
0
0
0
0
4
3.38381* 8 6.3072e* 5
2 !38 1457
2.25190* 5 G.e000£* 0 2,23000* 3 0.00000* 0
138 1457
03.60850* 4 8.42698* 10
6
1 £38 1457<.00000* Z e.80002 + 0 6.87200+ 5 2.00000* 3 1.00000* 0 t. 00000* 0 138 1457
.00000* i 0.00002+ 000
2 138 1457
16
e.00002 + 0 0,00000* 0 0.00000+ 0 0.00000* 0 e, 00000* 0 138 1457
1,00000+z
1.73200* 5 2.000012 + 3 4.34000* 1 1.10000* 0 0.00000* 0 e, 00000* B j !38 14-57
6.87200* 5 2.00002+ 3 9,95660* 1 1.10000- 2 0.00000* 0 e.00000* 0 ! 38 1457
0.00000* 0 e.e000*+ 0
0
1 : 38 145712e1.00000* 0 e .00002 + 0 0,00000* 0 0.00000* 0 0.00000* 0 e.00000* 0 38 1457
9.13980* 9 3.00002* 1 4.34000* 1 1.10000* 0 0.00000* 0 e.00000* 0 ; 36 1457
36 1 038 0 00 0 0
03.60850* 4 8.42696+ 1
0
0
2 |39 1451
00.00000* 0 0.e000ii + 0060 £39 1451
EVAL-FEB74 C.W.REICH
36-KR- B5M ANC
DECAY DATA
139 1451
139 1451
CWR
PREPARED FOR FILE 7/73
REFERENCES >C - 1973 REVISI ON OF WAP8TRA-G0VE MASS TABLES.
139 1451
CTHER DATA F.K.HOHN ET AL. NUCL. PHYS. A152.961(1970)
139 1451
HALF-LIFE N.E.HOLOEN CHART OF THE NUCLIDES (1973)
139 1451
ANC PRIVATE COMMUNICATION (SEPT. .1973).
139 14511
491
139 1451
10
1
457
13
139 1451
39 1 0J.60850* 4 8,42696* 1
00
2 > 39 14571001.61280* 4 3.60002+ 1
2 ;1 !39 1457
4
39 1457
2.26080* 9 B.B0008+ 0 1.63220* 5 0.00000* 003.60850* 4 8.42696+ 1
2 139 14570121.00000* 0 0.20002+ 0 9.91700* 5 2.00000* 3 7.88000- 1 1.30000- 2 39 1457
3.00000* e 0.00002+ 0 3,04470* 5 5.00000* 1 2,12000- 1 1.30000- 2 39 145701.00000* 0 e.C000B* 0
1 ; 39 14970121.00000* 0 e.0B002 + 0 0,00000* 0 0.00000* 0 0,00000* 0 e,00000* 0 39 1457
6.40700* 9 2.00002+ 3 7,88000* 1 1.30000* 0 0.00000* 0 2.00000+ 0 39 145700.00000* I 2.00002* 00
16
2 39 1497
1.40000* 2 0.00002+ 0 0,00000* 0 0.00000* 0 0.00000* 0 e.00000* 0 ' 39 1457
1.50990* 9 9.00008* 1 5,38000* 1 1.80000* 0 4.99000- 2 9.00000- 4 : 39 1457
3.04470* 5 5.00002+ 1 1.00000* 1 4.00000- 1 5.09000- 1 2.40000- 2 :,39 1457
139 1 0139 0 00 0 0
-1 0 0
0
0
0
0
0
8
0
EVAL-FEB74 C.W.REICH DECAY DATA

1

i
i

i

3

4
5
6
7
8
9

10
11
12
13
14

15
16
17
18
19
2?
21

22
23
24
25
26
27
28
1
2
3

4
5
6
7
8
9
10

11
12
13

14
13
16
17
18
19
20

21
22
23
24
25
26
27
0

- Ill -Enclosure 3

36-KR- 85 ANC
EVAL-FEB74 C,W.REICH DECAY DATAPREPARED FOR FILE
7/73
CWR
REFERENCES Q - 1?73 REVISION OF WAPSTRA-60YE MASS TABLES.
OTHER DATA iKDS-19U
FIRST-FCR3JDDEN.UNIQUE S M P E CORRECTION CONSIDERED IN DERIVING>E-BETA FOR 8R0UND-STATE BETA TRANSITION
HALF-LIFE N.E.HCLDEN CHART OP THE MUCLIDES (1973)
AND PRIVATE COMMUNICATION (SEPT.i1973),

KRYPTCN-85

ENDF/B MATERIAL NO.

DECAY DATASTATE)
HALF-LIFEAVERAGE EETA ENERGYAVERAGE GAMMA ENCRCY
DECAY TYPEPRODUCT STATE

O-VALUEtEV),

6 .8720E*05 */-SETA
INTENSITIESENERGY
1.7320E*e5
6.fl720E*e5

ERROR

ENERGY •/- ERROR,/.

0,0000E*00

I-ABS/1-REL •1.0000E*00 */-0>0000E»e

I-ABS/K-REL •1.0000C*00 */-0.0000E*00

INTENSITY •/- ERROR

2.9000E+03
2.3000E+03

INTENSITIES

5.l3?8E*e5<EV)2.0000E-02 V
0.0000E*00 EV
0.0000E*00 EV

BRANCHING RATIO

2,PI000E*03

BETA
• /-

1.07J0E*01 */2,25l«E*05 */2.2300E*03 */-1.1000E-82
GAMMA
INTENSITY */' ERRORINTERNAL CONV. COEFF.

138

- 112 -36-KR- 85M ANC
EVAL-FEB74 C.W.REICH DECAY DATAPREPARED FOR FILE 7/73
CWR
REFERENCES 0 - 1973 REVISION Of WAPSTRA-GOVE MASS TABLES.
OTHER DATA F.K.WCHN ET AL. NUCL. PHYS. Al92,961(1970}
HALF.LIFE N.E.HCLOEN CHART OF THE NUCLIDEI (1973)
AND PRIVATE COMMUNICATION (SEPT.i1973).

ENOF/B MATERIAL NO,

OECAY DATAKRYPTCN-85( 1ST EXGITED STATE)

4.4800E+00 */'2.2608E«05 */1.8322E*09 */-HALF-LIFEAVERAGE EETA ENERGYAVERAGE GAMMA ENERCY
DECAY TYPEPRODUCT STATE

9.9170E*03 •/3.0447E+05 */-INTENSITIESBETAENERGY •/- ERROR
8.4070E*Z5
INTENSITIESENERGY •/- ERROR
1.5099E*Z5
3.tJ447E«?5(EV)

2.3000E*03

BRANCHING RATIOO-VALUE(EV)i

BETA
ISOM.TRNS.

1.0B00E-02 H
0.0000E*00 EV
0.0000E«00 EV

7.8BB0E-B1 •/2,1200E>01 */•2.0000E*03
5.0000E*01

I-ABS/I-REL •1.3000E-02
1.3000E-02

1,00001*00 */-0.0000E»00

1,40001*00 •/-0.0000E*00

INTENSITY */• ERROR
1

1.3000E*0t)

GAMMA

I-ABS/I-REL •INTENSITY •/• ERROR
5.3800E+01

1.8000E*00

INTERNAL CONV. COEFF.
4.5S00E-02
5,0900f-01

9.0000E-04
2i4000C-02

139

- 113 -Appendix B
Storage and Retrieval of
Neutron Capture Gamma-Ray Spectra
M. R. Bhat- 114 Storage and Retrieval of
Neutron Capture Gamma-Ray Spectra

M. R. Bhat
National Neutron Cross Section Center
Brookhaven National Laboratory
Upton, New York 11973

1.

Background
Recently, it has been suggested that neutron resonance capture gamma

ray data should be stored in the CSISRS data files along with the neutron
cross section data.

Such information is needed for studying nuclear

structure and for obtaining accurate values of neutron binding energies.
In addition, the data are necessary for shielding and energy deposition
calculations and "prompt" activation analysis.
the gamma spectra

It is necessary to record

with the best possible resolution and supplement itwith coincidence and angular correlation measurements and other data forthe basic physics needs. However, for shielding applications the gamma
spectraneed bfc given in broad bands 0.5 MeV or so wide. For activation

analysis a few of the more intense gamma rays are needed and it may not
be necessary to catalogue every gamma transition observed.

In storing thecapture gamma rays, one is immediately faced with the enormous volume ofthe data.

The data as recorded by a Ge(Li) detector may contain a few

hundred gamma rays measured at thermal neutron energy and a few neutron
resonances.

Lower energy gamma rays measured with a crystal diffraction

spectrometer have resolved thousands of gamma rays in a limited energy
region (E < 1.5 MeV) in the case of a few rare earth nuclei. A roughorder of magnitude estimate indicates that the total data will be of theorder of 5 x 106 data points. The size of the current CSISRS-2 library- 115 -is about 1.2 x 10 6 data points.

Therefore, the capture gamma library

could be handled by the existing programs and techniques.

The entry of

new data into the library could be further facilitated if the experimenter
sends his data on magnetic tape in a standard format.

However, one

cannot help asking the question:is it necessary to store all the capture

gamma ray data in all its detail?

The following are a few alternate

suggestions which should be considered.
One such suggestion is to leave out the weak gamma rays whose
intensities are below a certain value.
the data files.

This would reduce the size of

Besides, gamma rays which are very weak in all the resonances

may be due to background, impurities or quirks of the fitting program so thatno one would miss them.

The immediate reaction to this proposal is that this

implies an evaluation and that the data files should contain every bit of information the experimenter thought worth reporting.
Another suggestion that is usually put forth is to bunch the gamma rays
into bins a few hundred keV wide.

This proposal may be even more repugnent

than the first one because it implies loss of information by degrading theexperimental data to suit a particular application, e.g.:"ations.

shielding calcu-

Besides, this loss of information will be felt when more sophisticatedfuture applications need the details.
An easy way out is to propose that every bit of detail in the measured
data should be entered into the data files.

These are needed of course fornuclear structure studies though coincidence measurements and other data
are necessary to make use of them.

Besides, one always has the feeling that

if all such data are not available somewhere they are for ever lost to thescientific community and somehow the sum total of human endeavor would be
the lesser for it.

Besides, it is usually said that if thousands of gamma

-116 -

lines were worth measuring then they are worth storing though some of thesilent minority might wonder were they worth measuring?
Assuming that the proposal to store the detailed gamma spectra asreported by the experimenter is generally acceptable it appears necessary
to decide what kind of primary and auxiliary information should be stored
and the formats for doing it.
Some thoughts on the physics information of the data one should store
are discussed in the rest of this memorandum.

It seems more appropriate

to go into the details of the format and the mechanics of storage andretrieval after the physics content has been agreed upon.

Capture data

can be coded within existing formats and more efficient formats are underdevelopment.

Though one should mention again that it would very convenient

if the data is available on a magnetic tape directly from the experimenter.
This would obviate the need to code the data manually from the printed
page with its attendent errors and delay.
A few enquiries at likely places have shown that at present capture
data is not available on magnetic tape or any easily transmittable form.
The only exception seems to be the one data set of Rasmussen et al. on
thermal capture.

- 117 -2.

Introduction
This memorandum discusses the details involved in entering resonanceneutron capture gamma ray data in the CSISRS data files and the exchange
format.

Such data used to be measured with Nal(Ti) detectors or with one ofa group of magnetic spectrometers.

With the advent of Ge(Li) detectors,

the quality of the capture gamma ray data showed great improvement
because of better detector resolution and appreciable efficiency.

Inthe meantime, high resolution crystal diffraction spectrometers werealso developed, spurring further improvements in the different typesof magnetic spectrometers.

The result of all these advances in experi-mental techniques has been the collection of large amounts of capture
gamma ray data of excellent quality and very good energy resolution.
Thus, it is not unusual to find publications reporting hundreds ofwell-resolved gamma rays measured over quite a few neutron resonances.
With the development of more intense pulsed neutron sources and time-offlight arrangements capable of better energy resolution, it is to be
expected that one would be able to measure capture data in more resonances
up to quite high energies.

With such an enormous increase in the quantityof experimental data, it is very important to decide at the outset what
different types of data are to be entered in the data files, at whatstage of the analysis the experimental data is to be considered as
primary data, and other related problems.

Some of these questions are

discussed in the following pages and a few answers

suggested.

-118 3.

Experimental Data
The first question one should try to answer is whether the data enteredin the files be in the form of say the pulse-height spectrum as recorded
by a multi-channel analyzer.
reasons.

The answer is a definite no for the following

Apart from the fact that such data tend to be very voluminous,(4096 channel analyzers are common these days) the main objection against
such a procedure is that the raw data are very dependent on a particularexperimental arrangement, and it would be very difficult to find a common
basis for comparison between data from different sources.

Thus, the raw

data from Ge(Li) detectors is very dependent on all the different instrumental variables like the detector resolution, efficiency, background,
scattering from the surroundings, data collection time, counting rate corrections,detector size and configuration, to name only a few.

It would be almost

impossible to list all the characteristics of the apparatus needed to analyze
the data by suitable unfolding procedures.

This confusion could be further

compounded by the fact that data from different types of apparatus areavailable in different gamma energy regions and would have to be combined togive a composite picture of the whole gamma spectrum.

Hence, it is evident

that the data that are entered into the files should not be the raw data but
the end product of a type of unfolding best done by the experimenter who ismost familiar with his apparatus.
The result of such preliminary analysis is usually given as gamma rayenergies and their intensities (photons/100 neutron captures) either forincident thermal neutrons or for capture in a specific neutron resonance.
In addition, other auxiliary data like the spins of neutron resonances,-. 119 -spin-parity of bound nuclear states, polarization data, (n,y) and (d,p)
correlations and a number of different pieces of information are reported
in the published literature.

Therefore, the next question to be answeredis which of these should be coded into the data files and which should beleft out.
4•

Specific Data Quantities
T e choice of quantities for coding into the data files should perhaps

be governed by their use in practical applications.

This pragmatic view

point does not make such a choice very easy because apart from a few obvious
examples the data needed for practical use is limited only by the fruitfulness
of ones imagination and how sophisticated the applications are.
of these quantities is given below as a starting point.

A listThis choice wassuggested by present applications or those expected in the near future.
This list could be enlarged at a future date as dictated by new applications
and the experience gained by entering the capture gamma data into thedata files.

It may be that the list is too long as it is.

For convenience, these quantities have been divided into two broadgroups viz:

those that belong to the DATA or C0MM0N subsections of EXFOR

and those that correspond to auxiliary or supplementary information andshould be given in the BIBLIOGRAPHIC section.

They are listed on theleft-hand side column of these tables and on the right-hand side are given
comments either explaining or justifying their choice.

I. DATA or C(ftt«fa Sections
Quantity
E
R

Comments
Resonance energy.

"R
J

Resonance spin-parity. Independently known ordetermined from capture y angular distribution data,
multiplicity or ratio of low energy secondary v rays,or polarization experiments.

- 120 Comments

Quantity

Resonance angular momentum.

T
T r'YR F R R
En

Neutron, gamma, fission and total widths of theresonance.

E

Energy limits of the neutron beam. This would
specify the range of neutron resonances covered
as in the average capture measurements with aninternal target. This could also define a
filtered beam, e.g., the 24 keV beam with an
Fe filter.

E .

Energy of the i-th gamma-ray.

I

Intensity of the discrete gamma-ray, given as
number of photons/neutron capture.
Energy limits of a group of unresolved gamma
rays.
Number of y-rays per capture per unit energy
interval in the continuum.
Individual Y" r a y width in eV.

(En,e>

Differential cross section for producing a
gamma-ray E ^ at neutron energy E at angle Q.

n

Differential cross-section for producing a
gamma continuum E to E + ^ E by neutron ofenergy E to E + ^ E
at angle Q. This quantity
could also contain a mixture of discrete andcontinuum Y" r a y s «nrNormalized energy distribution of the whole yspectrum where v has been defined before and U
is an upper limit of integration, usually U = Bn(B = binding energy).

l/(E)dE

II.

EL, ML

BIBLIOGRAPHIC INFORMATION Section
Multipolarity of the y * a y .
Mixing ratios of different multipoles.

- 121 -Quantity

Comments

Spin-parity of initial state, which may be abound state or a neutron resonance.

J.
1Spin-parity of final state.

Ll/2

Half-life of a bound state if It is an isomerlc
state.

T

if

Transition probability for a y transition frominitial state i to final state f.

pairInternal pair formation coefficient (usuallydenoted by T) , if experimentally determined.
etc-

Internal conversion coefficients for K, L, M, etc.
shells if experimentally determined, for:(a) Primary y r a y s : These are of theoreticalinterest and are used to assign multipolarities
for these transitions.
(b) Low Energy Secondary y-rays: These areimportant in practical applications involving
calculations of energy deposition in moderately
thin aggregates of matter. Because of thisprocess, there is a decrease in intensity of
the low-energy y-rays as some of them areinternally converted, depending on their multipolarity, etc., with the appearance of intense
peaks of the characteristic x-rays. Such asoftening of the y-spectrum and a change in
its energy distribution materially affects theamount of energy absorbed in a shield or asample.
Flourescence yields of K, L, M, etc. shells.
These define the ratio of the number of photons
emitted when vacancies in an atomic shell arefilled to the number of primary vacancies inthe shell. T>ese are important as they determine
the actual number of x-ray quanta emitted.

r
Photon strength function.

YDirect

Direct capture cross section, i.e., the capture
cross section between resonances as calculated
from off-resonance capture (valid for well separated
resonances).

- 122 -Quantity

Comments

Binding energy of the neutron in the nucleus(Z.A+1) where (Z,A) is the target.
/Ba. a Bci ni
Effective binding energy of an element containing
more than one isotope where a is the fractional
abundance of the i-th isotope, a c i its thermal
capture cross section, and B n i its binding energy.

n =
'ci

v(E )dE

This quantity, formed by summing over the discrete
Y-rays and integrating over the continuum (after
allowing for internal conversion etc.), may becalled the "observed total Y~ ra y energy." It issometimes called "observed binding energy," butthis is not a good choice because B is theobserved binding energy determined, e.g., bymeasuring the energy of a primary transition
to the ground state of the nucleus (Z,A+1) inthermal capture. The ratio S n /B n gives a measureof the total Y~ ra y yield observed in an experiment.
Because of missed Y" ra ys o r because of the finite
low-level bias of the measuring apparatus, thisratio may not be equal to one. In this case,the intensities are sometimes arbitrarily renormalized
to make this ratio equal to one so as to have energybalance.

Polarization data

Results of measurements of either the circularor linear polarization of individual Y~*ays,and the nuclear structure information derived
from them.

Coincidence measurements

Results of such measurements on members of acascade and information derived from them.
For fissile nuclei, capture Y-rays are detectedby measuring them in anti-coincidence withfission neutrons.

Ratios of low-energy
secondary Y-

Resonance spins or nuclear level density parameterslike a, a, etc. determined from such data.

Angular correlation
measurements

Perturbed or unperturbed angular correlation
data and the nuclear structure information
derived from them.

Conversion factor from
intensities to widths

It this information is given by the author, it
should be included. Usually it is based onthermal capture data.

- 123 -Quantity

Comments

Neutron source

Type of neutron source, e.g., filtered beam,with its width and intenssity distribution, or
whether the target is inside a reactor as in
the average capture technique, crystal spectrometer,
etc. Also state of polarization of the neutron
beam.

TargetState of polarization or of alignment of thetarget.

Detectors

Nal(Tjfc), Ge(Li) detectors.
Crystal diffraction spectrometers: (a) curved
crystal, (b) flat crystal.
Magnetic spectrometers of various types.

5.

Example of Coded Article
In this section an example of a coded article is given and some thoughtson the experience are expressed.

The article is on thermal and resonanceneutron capture in natural antimony.

The experiment described in thisarticle is a two parameter experiment, i.e., with the neutron and the gammaray energies as being independent variables.

The exchange format isbasically suited for accommodating the results of a one parameter experiment.
Therefore, in coding the data of this experiment in the exchange format,
one is immediately faced with its limitations and the tedium of repetition
it imposes.

In addition, a concise two dimensional table conveying a lotof information is broken into a number of disjointed columns of numbers.
Therefore, it appears desirable to find a more efficient coding procedure.
There are two possible solutions to this problem.

The first solution

is to leave the exchange format unchanged and to strip the data tables tosuit it.

This could be done by a computer program which acts as a "compiler"

and makes the coding of an article as it appears in the literature into
the exchange format less painful.

This has already been done at the NNCSC

-124 -

by D. I. Garber who has a working program which does the conversion(private communication).

The second solution is to change the exchange

format so that it can contain a two dimensional table in a sensible,
efficient fashion.

If the coded information bears a one-to-one correspon-

dence to the published data tables, it would be desirable but not necessary.
There have been many suggestions as to how to implement these changes.
A concentrated effort in this direction in the near future is indicated.
In concluding this section, an attempt is made to estimate the sizeof the capture gamma data library assuming the neutron and gamma-ray
resolutions available now.

Looking at some of the BNL fast chopper data

the number of high energy primary gamma-rays observed per resonance varies
from about 50 to 130.

Let's assume an average of 100 for this number anda similar number for the low energy secondary gamma-rays.

Further, if

it is assumed that one can measure capture spectra in about 100 resonances
per isotope with the best possible time-of-flight arrangement, for all
the 300 or so stable isotopes available, one gets a grand total of 6 x 10
data points.

This is perhaps an upper limit to such a number and as suchmay be considered to include more than one set of measurements available
on an isotope.

-125 ENTRY
SUBENTBIB
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AUTHOR
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PART-DETSTATUSHISTORY
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- 126 -COMMONcv
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ENDSUBENTOne S ubentry/Neutron Resonance

ENDENTAY- 127 -Paper submitted to the meetingof the IWGNSRD (.March 19727"
by
D. HOREN,
Nuclear Data Project
29 April 1974

- 128 -Mr. Chairman, following a pleasant walk in the sun and some timespent reading and contemplating I now-feel that an elaboration of
my remarks of yesterday is possible.

Although what I propose topresent is still not completely to my liking, I offer it for yourconsideration.

First, it now appears as though a number of countries have made or
are on the verge of making sorae sort of committment to fostering
nuclear data compilations for either or both basic and applied uses.
In particular, I would refer to the papers presented here by ourcolleague from the USSR (i.e., documents 9, 13), from France (doc.

),

and possibly some others (please forgive me as I did not take all the
documents with me when I left), as well as some verbal comments fromthe representativdfrcm Japan and others.

Now

I certainly feel that this working group should do everything

possible to encourage these proposed committments 1

If you are alsoof this opinion, then we must examine the numerous proposals thathave been made to see how best we can do this.

After having read a number of the documents presented at this meeting,it is rather apparent that much has been proposed.

This ranges fromvery simple proposals all the way to extremely elaborate ones.
the situation is much too complicated for a rational being.

Obviously

However,since I consider man basically to be an irrational being, I will try topresent a rational proposal which I would hope each of you will consider
irrational and thereby maximize

the probability that it will be

acceptable.

I start with the following assumptions:a)This working group will certainly not be able to change thevhole field of compilations and effect an ideal situation(if it could ever agree as to what that would be) in a fir.ite time.

b)This working group might suggest, recommend or whatever you willthat a]l present day compilers henceforth cooperate and maximize
the total efficiency.

However, I thir.k the best we could do here- 129"is recommend that the USA and USSR cooperate and provide
sufficient rocketry to remove all the present compilers
from their reference system so they could ponder thesituation in a purely subjective manner.
c)

There already exists a solid foundation of compilers and aids
(such as reference systems, etc.) which could be expanded if
one could specify the degree to which this is needed.

References-

Now let us get down to be specific.

There presently exist a number of indexing systems to theliterature.

Each of these apparently is not completely satis-

factory to all users.

Now we (as well as others) have foundcertain deficiencies with some systems and were not able tohave these sufficiently resolved to suit our purpose.

Hence,

we are presently committed to continuing our system of Recent
Beferences, with the intention of modifying the keywording tocorrect a number of constructive criticisms (for example, those"by E.G. Fuller).

In addition, we plan to modify our format so

as to make the published references more useful.

This will takethe form of indexing papers under more headings, including papers
which pertain to reaction mechanisms and theory.
Hence, in the area of indexing of references I recommend thefollowing:
Immediate Action

References:1.

We try to expand the usage of keywords to all journals.

2.

We try to improve the keyword system.

3.

We try to get authors to seriously .keyword their papers(as they presently do for Nuclear Physics) and educate
them if necessary as to needs and benefits for them.

4.

We do not worry about possible duplication at this time.

-130-

5,

We delegate a committee to "begin a detailed
examination of all indexing systems to determine
whether there is a need to develop a completely
new system.

This must "be done not only from thepoint of view of trying to obtain a system thatwould satisfy every possible usage, but, as Fuller
points out, bearing in mind the Wtf-*<a«~*<-

questionof cost and funding, as well as the time it would
take to produce same.

Compilations:Here, we must recognize that there presently exist a

number of different compilations which are being done in differentways.

In addition, there apparently exist a number of situations

for which either new compilations are needed or at least specificevaluated data are required.
recommended 5*'^5

Now a number of people have apparently

ahead and developing super computer systems

which they assume will satisfy all these requests for information.
Personally, I feel that if you first take the time to examine manyof these so-called pressing needs you might finda) that a number of them can easily be satisfied"b) that it may not be too time-consuming to answer a number ofothers, and this could probably be done much more efficiently
without the use of super computer programs,c)and finally if you are not careful the needs will disappear"beforeVou even begin to start programming 1

Now before making my recommendations in' this area, I would justlike to note that

we at the Data Project are working on a com-puterized data system for "selective" quantities.

Most of the<S>tae>5 we will include have a very high usage rate, and many ofthem we will have to reproduce in future compilations.

Immediate Action:
In this area, I recommend the following:1.

We do not concern ourselves with the detailed manner in which

-131-

the present groups are doing their compilations,2,

We recommend the establishment of a world-wide list ofcompilers and their tabulations.

3«

We recommend that the different compilation groups indicate
to what extent they are willing to respond to user requests.
Try to set up a system whereby specific requests would be
handled by that group which is best "suited" to do so.

Forinstance, requests for radioactive decay data where the parameters are desired to an accuracy of better Jkhan 2$ would besubmitted to the Euratom group} etc.
4.

We recommend the establishment of national nuclear data centres
and encourage people to send their data to same} after having
defined "data".

5.

Establish a means by which such centres can communicate.

6.

Encourage the international exchange of compilers.
In this regard, let me say the following.

I certainly would

try to encourage any nation that is interested in supportingin whole or to a "reasonable" degree one of its compilers for
six months to a year at the Nuclear Data Project, and would beinterested in hearing any informal comment in this regard.

It

has been suggested, that such a stay might possibly be arranged
on a direct basis, or possibly by using the IAEA as an intermediary.
7.

Set up a committee to examine the real needs for a super data
file.

If it is concluded that such is warranted, then thecommittee must examine the potential costs and possible fundingfor earae.

Applied Uses

Immediate Action:

1.

Establish a committee to collect, tabulate and examine theuses of non-neutron nuclear data.

-132-

2.

Develop a request list for users of applied nuclear data.

3.

Encourage existing compiling groups to respond to such arequest list as indicated under compilations.

4.

Encourage new people who are interested in entering thecompilation field to consider doing compilations that are
not already "being donej "but have been established to benecessary as the basis of the request lists.

- 133 -NON-NEUTRON NUCLEAR DATA:A PROPOSAL FOR INTERNATIONAL COOPERATION

A. Lorenz
Nuclear Data Section
IAEA, Vienna, 29 April 1974

FOREWORD

In context of this presentation the term
"nuclear data" is used primarily as an abbreviation
for nuclear structure and decay data.

-134 -In order to help the discussions which will ensue inthe course of this meeting, it is important to recognize
from the start the diverse and separable aspects of thesubject of our meeting. If one considers the title "Nuclear
Data for Applications", one recognizes three distinct groupsof people involved, namely the experimental and theoreticalphysicists, the producers of nuclear data, the evaluators ofthese data, and the users of these data. Although thissimplified picture is not applicable in all cases, by andlarge, these groups have operated independently of each other,where the main means of communication between these groups
has been the medium of publication.

Perhaps, this existing situation and a possible resulting future situation can best be represented in the form of adiagram, shown in Figure 1, which illustrates the data flowfrom the data producers to the data users.
The current situation, shown on the left-hand side of the
diagram, i s characterized mainly by a flow of data through themedium of publications (e.g. Physical Review articles byauthors, Nuclear Data Sheets and Tables by evaluators). In
certain isolated situations cooperation between individuals
or groups of experimental physicists and evaluators exist,
as for instance in the case of Dr. Endt's group in Utrecht.
Also, some personalized service i s provided mostly on anational basis to nuclear data users by evaluation centres,
as in the case of the Nuclear Data Project aX Oak Ridge.

The future situation, as shown in the right-hand sideof the diagram, i s not suggested to replace the current situation,
but to complement i t . Basically i t suggests the formalizationof the links between data producers and evaluators, and between
data evaluators and data users, in the form of international
cooperation agreements. Even though the arrows indicate a one-way

-135 -

flow of data, it does not imply any exclusion of feedback
from users to evaluators and experimentersin the form ofdata requests. The omission of any other possible links (suchas direct links between the given boxes) has been done forthe sake of simplicity.
To summarize then, the object of this meeting, and of thesubsequent cooperation in the field of nuclear data is toimprove the existing situation and achieve a more coordinatedcooperative system aimed at an improved service to data users.
As indicated on the far-right of the diagram of Figure 1,
this effort would require:- Coming to an international agreement to create a coordinatedand systematic method to exchange and compile experimental
nuclear data.
- Coming to an international cooperative agreement to coordinate
and share the nuclear data evaluation task, and- Evaluating the possible extension of the scope of theactivity of existing neutron data centers to form aninternational network of nuclear data dissemination
centers.
The implication of these three considerations must be
viewed in context of the existing data centers and evaluationgroups, and the current information exchange practices.
First,

since we are starting with an existing framework,

any new system of international cooperation in the field of
nuclear data should take advantage of existing working practices.

Second, because of the existence of basically two separate
sets of nuclear data organizations, one consisting of a numberof centres or groups dealing primarily with the compilationand evaluation of nuclear data, and the other, consisting of

- 136 -the four internationally coordinated neutron data centres, alreadyactive in the dissemination of neutron data information, it would
be of advantage to consider the questions of coordination ofcompilation and evaluation of nuclear data separately from those ofdissemination.

Thus, on one hand we have a potential network of compilation andevaluation centres, which would coordinate the compilation, distribution
and evaluation of experimental nuclear data, and on the other, an existing
network of dissemination centres which would coordinate the distributionof evaluated nuclear data to users.
With regard to the compilation and evaluation of nuclear data,
it would be highly desirable to maintain the functions of the existinggroups and centres within the framework of the proposed cooperation.
Furthermore, in order to alleviate the workload of the systematic
evaluation of nuclear structure and decay data performed currently
only by a few groups, all existing evaluation groups and possibly
new groups of interested physicists, should be encouraged to sharein the compilation and evaluation task within the framework of aninternationally coordinated programme.

Two basic questions to be resolved in this context are:l) how to divide the workload, and 2) how to coordinate this effort
in order to achieve an efficient exchange and distribution of thebasic experimental data

and their bibliographies among the cooperating

centres.

With regard to the dissemination of evaluated nuclear data, it
would seem to be highly logical to entrust this function to theexisting four regional neutron data centres. These centres are
already recognized and known by a large fraction of the scientificuser community for the services they perform in the field of neutron
data. Also, these centres and associated facilities exist, and already-137 -

have a mechanism for the international exchange and dissemination of
nuclear data information. It would therefore be considerably more
economical and efficient, both from financial as well as time considerations, to utilize the existing network to disseminate thesedata.

The main question which arises in this context is the extent towhich the existing neutron data centres are prepared to shoulder theburden of disseminating the non-neutron nuclear data generated by
the compilation and evaluation centres. The question of the actual
volume and diversity of data involved, and estimates of the man-power
needed to perform this task would have to be discussed to help theneutron data centres assess the effect of such an extension within
the context of their individual programmes.
The coordination aspect of the dissemination of nuclear datasuggested above could be undertaken by the IAEA Nuclear Data Section.
This center has a unique international vantage point as well as
connections with a wide variety of applied nuclear data users associatedwith in-house as well as external IAEA programmes.
Clearly, it would have beendifficult and laborious to in-clude at this stage all aspects and details, implicit or even selfevident, of this suggested international collaboration. This proposal
reflects the views of the Nuclear Data Section and is suggested to beconsidered as a basis for further discussion.

Future Situation(Extension of current situation)

Current Situat ion

I

DATA PRODUCERSPUBLICATIONS
1IInternational
agreement toexchange
experimental
datat
Organized Compilation

Informal cooperation

1
1
1

1

International
agreement tocoordinate
evaluation
effortDATA EVALUATORSPUBLICATIONS

|

if

1

Local personalized
service to applied
users

Organized
Dissemination

1
1
1
1

I—.
DATA USERS

Figure 1:

Nuclear Data Flow from Producers to Users.

^

International
network of data
dissemination
centers1

- 139 A p r i l 26, 1974

TO

Participants of Specialists Meeting on Nuclear
Data for Applications

FROM

G.A. Bartholomew

INFORMATION CENTER FOR APPLIED USERS(Agenda Item VIII)

It is recognized that one difficulty encounteredby the nuclear data user particularly in applied fields far
removed from nuclear science is that he doesn't know what
information is available and where to go to find it; inextreme cases he may not even completely understand what
data he needs. To aid this user, and ipso facto all othermore informed users as well, an "information center" (ornetwork of information centers) is envisaged.
The information centers' function would be tomaintain a compilation of compilations, a list of data
centers, compilers, and experts in nuclear data, a rosterof compilation or repackaging projects in progress. It
might also issue a newsletter to all data centers and otherrelevant laboratories and possibly also maintain a request
list. The activities of the center or centers are seen as
entirely passive in the sense that no direct attempt would
be made to organize or influence any data program but merely
to publicize what is in fact going on and what is available
in the data field. The center would expect to be kept fully
informed of all compiling activities, cooperative links, etc.
in order to maximize its effectiveness.

-140It would seem that such an activity, once set up,
would be a much smaller operation than data collection or
evaluation itself and might be an activity taken on by anexisting data center or centers in addition to normal
activities.

Indeed, data centers already perform many ofthese functions quite naturally, all that is needed is to set up
a formal system and publicize the existence of the service tousers.
It would seem logical that the system should becentered at IAEA with possibly other centers in each country
or region. It seems possible that in many instances a casualuser is more likely to become aware of a local (national)
nuclear information center than of an international center andmay feel it easier to contact the local center. Thus theidea of a network of centers, with "headquarters" in Vienna,
seems an ultimate goal. Rather than attempt to set this up
at once, it would perhaps be more logical to begin with theVienna center and add others as convenient to do so. All
centers could have duplicate information files but coordinatedand updated from Vienna.
A major problem for the success of the center would
be to publicize its existence and availability for the casual,
uninformed user from distant fields.

For this purpose all of

the publicity channels open to the Agency and other modes ofcommunication, e.g. by advertisements in various scientificand trade journals etc. would have to be used extensively
until the existence of the service became widely known.

-141 "As an extension of the service for applied users
the information center could also supply a service to the
nuclear data field, for example by informing someone planninga new compilation whether such a compilation was not alreadyunderway by another group or similarly, through the request
list, to keep scientists fully informed on measurements
needed or underway.

- 142 Sixth Meeting of IHDC
Vienna. 8-12 October 1973
Formal recommendations to the Director General

1.

International Working Group on Nuclear Structure andReaction Data

One of the major decisions taken "by INDC at this meeting was toassume responsibility for the international coordination of non-neutron
nuclear data programmes. This was in particular demonstrated by thecreation of a standing subcommittee on non—energy applications of
nuclear data. In arriving at this decision the activities of theInternational Working Group on Nuclear Structure and Reaction Data
(IWGN3BD) convened by the Agency in March 1972 at its Headquarters
were essential. IWGNSRD was successful for example ina)helping to assess the requirements for non-neutron nuclear data
in various fields of application, and exploring ways in whichthese needs could be metj"b) reviewing the existing compilation and evaluation activities;c)"bringing to the attention of major journals the need for
improved nuclear data presentation, andd)assisting the Agency in planning the programme for the Symposium
on Applications of Nuclear Data in Soience and Technology heldin Paris in liarch 1973.

With the above decision INDC endorses the wish of the IAEA totransfer the responsibilities of IWGNSRD to INDC. Certain operational
functions will be delegated to a Study Group on Nuclear Data for
Applications (see recommendation in Appendix III.2.), It asks the
Director General to bring to the attention of the IWGNSRD its appreciation
for the substantial and successful contributions of the participants in
the IWGNSRD to the Agency's nuclear data programme.

2.

Study Grout) Meeting on Nuclear Data for Applications

Following the Symposium on Applications of Nuclear Data heldin Paris in March 1973, a joint meeting of members of INDC and IWGNSBD
recommended that detailed suggestions should be sent as soon as possible
to the IAEA/NDS on the technical agenda of a so-called "X-centres Meeting"to be convened early in 1974, and that the topic "International Enquiry
on Long Term Data needs of IAEA member states" be placed on the agendaof the next I5DC meeting.
These actions were carried out and following the discussion on
12 October 1973, "the INDC recommends to the Director General that an
IAEA Study Group Meeting entitled "Nuclear Data for Applications" beheld in Vienna on 29 April - 3 May 1974* This meeting ia supposed to- 143 -start the international coordination of compilation and exchange of
nuclear level schemes and decay data for applied purposes. Further
meetings should "be envisaged to implement in detail this coordinationand to extend to further topics in this general area.

- 144 -Report of Ad-hoc Sub-Committee on
the roles of the standing sub-committees of INDC
Members:
Rose (Chairman)
BerenyiCierjacks

Divatia
Grinberg
RogosaRowlands
Schmidt
Usachev

This ad-hoc sub-committee was set up to reconsider the roles ofthe standing sub-committees in view of the INDC decision to set up
a fourth standing sub-committee on "non-energy" applications. The
recommendations are as follows.

1.

Nuclear standard reference data

The role of this sub-committee is unchanged though a change inmembership will probably be required to reflect the varying technical
topics likely to be considered. We wish to emphasize that theaccuracy of standards at which we are aiming in any particular casemust be of direct relevance to some practical problem - i.e., wehave no specific interest in improved accuracy for its own sake.

2.

Discrepancies in important nuclear data and evaluations

The role of this sub-committee is also unchanged, though again
a change in membership will probably be required.

3.

Energy applications of nuclear data

The role of this sub-committee is to make recommendations on policy
concerning the assessment and satisfaction of nuclear data requirementsin the whole area of the nuclear energy industry and to monitor interfaces between producers and users of nuclear data.
It is suggested that the nuclear energy area be divided into a
number of fields, e.g.
Reactor cores
Shielding
Fuel processing
Safeguards

Waste disposal
Inpile radiation measurements
Fusionand that the sub-committee's major attention be given to only one
or two fields at any one time.

- 145 -4.

Non-energy applications of nuclear data

The role of this sub-committee is to make recommendations on
policy concerning the assessment and satisfaction of nuclear datarequirements and to monitor the interfaces between producers andusers of nuclear data in all applications relevant to the businessof the IAEA except the nuclear energy area.
To accomplish these ends it will need, for example, to decide on
a workable breakdown into user areas, to identify the existing national
and international organizations in the various fields and find appropriate methods of working with them to produce carefully consideredlists of nuclear data requests and to decide on methods whereby thesatisfaction of these requests will be achieved. It will need toconsider the demand for suitable repackaged data at the crucial
technical level for the users. It should encourage the cooperation
between the neutron and non-neutron nuclear data centres whereverthis could be helpful to the objectives of the INDC.
An example of a possible breakdown into applied subject areas is
the following.
Biology and Medicine
neutron dosimetryelectron dosimetry
radioisotope dosimetry
Eadioisotope application
biology
agriculturematerials
medicine

Activation analysis
neutroncharged particle
photonIndustrial application
X-ray fluorescence data
activation techniques/ N o t e that this list illustrates that the division could
be by technique or subject area or both._7
Since this sub-committee is a policy recommending body on nuclear
data production and compilation, complete technical expertise on alluser-topics is not essential provided that the necessary specialist
advice is available to it.
The same philosophy would ensure that INDC itself would not needto expand from its present size.

- 146 -Members of the four standing subcommittees of INBC

1.

Subcommittee on nuclear standard reference data
Liskien, BCMN Geel, CEC,
Grinberg, Prance
Michaudon, Prance
Hose, UK
Smith, USA
Yankov, USSR
Lemley, IASA/NDS

2,

acting chairman

ex-officio member

Subcommittee on discrepancies in important nuclear dataand evaluations
Joly, Prance
Cierjacks, PRG
Motz, USA
Nishimura, Japan
Rowlands, UK
Sukhoruchkin, USSH
Goldstein, USA,
Lemmel, IAEA/NDS

chairmancorresponding member
ex-officio member

Subcommittee on energy applications of nuclear data
Motz, USA
Benzi, Italy
Cierjacks, PRG
Cond6, Sweden
Gemmell, Australia
Nishimura, Japan
Ricabarra, Argentina
Rowlands, UK
Yankov, USSR
Dunford, IAEA/lTOS

chairmanex-officio member- cont'd.

- 147 -4.

Subcommittee on non-energy applications of nuclear data
Rogosa, USA
Berenyi HungaryCross, Canada
Divatia India
Frohner, 5EA/CCDN
Grinberg, Prance
Rose, UK
Slaus, Yugoslavia
Usachev, USSR
Zelenkov, USSR
Lorenz, IABA/NDS

chairmancorresponding member
ex-officio member

- 148 Sixth Meeting of INPC
Vienna. 8-12 October 1973

Recuiremsnts and arralicationsof "border-line iruclear and atonic data

(D.

1.

Berenyi)

One of the nain conclusions of the IAEA Symposium on Applicationsof Euclear late, in Science and 'Technology held in Paris in March
this year was the great need for data on the "border-line "between
nuclear ar.d atomic data.
The fact is that thore are several fields of application -rhich areconnoted ,c} c~ ...va i.s. o^ljin. in tha nuolc-r techr.iru?s, partly
already mentioned during this meeting, especially in tha report of
the ad-hoc sub-conmittee headed "by Dr. Rosa (see Appendix IV).
Such fields are e.g.
X-ray data (energy and relative intensity, absorption
coefficient, electron and charged particle crosssections, etc.)
in radioisotope X-ray fluorescence analysis,
analysis "by X-rays excited 'oy electrons and charged
particles in accelerators
ECSA (electron spectroscopy concerned with applications)
X-ray microprobe analysis, etc.
Absorption and scattering data for different radiations(cross sections for absorption and scattering angular
distributions, effective atomic numbers, etc.)
in dosinetry, medical and biological applications, industrial
applications, etc.

2.

The task is similar as it was in the case of the non-neutron or"non-energy" nuclear data in general, partly carried out lastyear in IWGK833;
to survey and summarize the tabulations available to discuss
whether the tables above meet the claims and needs
to initiate compiling now tabulations (as e.g. the excellent
rocont table on X-ray fluorescence yieldo made by Bambynek
and numerous other scientists in an international collaboration) and measuresients.

149 -

3.

Several "energy" and "non-energy" fields are concernedwith the data topics in question but it seems to be mostadequate that the problems of "border—line nuclear andatomic data should be covered by the future fourth "nonenergy" s-ab-coK:nittee. Consultationst request lists are,however, necessary with and from experts of the fields
concerned.

- 150 -NOTES ON A COMPUTERIZED DECAY-DATA FILE*
C M . Lederer and A. Shihab-Eldin
April 22, 1974

INTRODUCTION
S. Pearlstein recently described a format for data on radioactive decay t1]
to be included in the Evaluated Nuclear Data File (ENDF). In these notes,
we would like to expand on his comments, and to suggest some modificationsof the content, and general procedures for revision and for applicationof the file. The restriction to decay data is intended only to focus on themost important type of data for a broad range of applications, not to exclude
other types of data.
II.

CONTENT OF THE DATA FILEA.

The objective is to create the simplest file that will provide best values
for each radioactive-decay property; half-lives; decay modes and branchingratios, masses and Q-values, natural abundances, and the energies and intensities (absolute whenever possible) of all radiations (a, 3, y, x-ray, conversion electron, Auger, neutron, photon, spontaneous fission).
All such quantities need not be tabulated, but should be derivable from thedata in the file. ~ ~ — — — — ~——B.

The suggested content of the file would be similar to that proposed by
Pearlsteint11, except as follows:1.

For electromagnetic (y) transitions, the intensity normalization
factor, energies, (relative) photon intensities, and multipolarities(+admixture) would be tabulated. Multipolarities could then be used
to compute conversion-electron intensities with the help of theoreticalinternal conversion coefficients. (For the rare, anomalous transitions
measured conversion coefficients would be given in addition to themultipolarity.)* Presented to the IAEA Specialists Meeting on Nuclear Data, April 29 - May 3, 1974,
Vienna.

-151 -The multipolarity should be included whenever possible, with a"type code", such, as:Type
0Multipolarity determined experimentally (from conversion
and/or angular distribution, polarization data)

1

Multipolarity inferred from level assignment (spin,parity, etc.)

2

Multipolarity is a rough estimate, based on half-life(or limit), uncertain level assignments, etc.

3

Anomalous transition; specific measured conversion coefficients given.

The multipolarities and electron capture branching (see II.B.2 below)
can be used to derive Auger intensities and (where not explicitly
tabulated) x-ray intensitiesMeasured x-ray and y± intensities would also be included in the y-ray
listings.
2.

Electron-capture, as well as B" and 8 + transitions would be includedin the tabulated data (daughter-level energy, transition intensity,"lu" or "2u" unique-transition indicator). For EC/B+ transitions,the total (EC+B+) intensity would most commonly be tabulated; however,a separate B + intensity would also be included if measured (withreasonable accuracy).

3.

Some minor revisions of format seem desirable, such as:
given as measured, with units, rather than in seconds
Beta transitions should be tabulated as E.
not E , . ., I, ...
endpomt* '7,

I, IMlu" or "2u"],

Energies in MeV or keV, not eV.
In general, the "rigidity" of the ENDF format should be avoided topermit more natural, error-free data entry. Where this is not possible,
data may be keypunched in another format and converted before entry into
the data file (by a program).

- 152 -III.

CRITERIA FOR THE EVALUATION OF DATAA.

The best value, whether measured or "derived", should be tabulated foreach quantity-. Specific examples of derived data are: ,1.

B~ endpoint energies (the- final level energy + Q-value) and intensities will almost always be derived from the decay scheme.

2.

The best 8 + intensities are often obtained using theoretical 3+/EC
ratios and the level scheme.

3.

In some cases, y-ray intensities are best obtained from conversion
data and/or the level scheme, plus theoretical conversion coefficients.
For example:a)

The best intensities of the transition in 1 8 0 m H f decay arederived from known transition intensities and theoretical
total conversion coefficients[2Jb)

The intensity of the 48 keV 2+ ->• 0+ transition in the decay
236 P u a p 232y i s b e s t e s t i m a ted as:
y - 2 + , 4 + states)/ U+(The measured value is low by a factor of 2, and is undoubtedly
wrong.)

4.

B.

The best (or only) x-ray intensities may be those derived from thecalculated K-vacancies (from conversion + electron capture). Thisis almost always true of Auger intensities.

The proposed use of derived data suggests the importance of guidelines
regarding the accuracy of theoretical quantities. It would be desirable
to adopt general guidelines that could be revised from time to time.
For example:
Theoretical Quantity

Assumed Uncertanty

ICC (Hager $ Seltzer)
ICC (other)
EC/B + and EC subshell ratios(Oak-Ridge, Berkeley computer codes)

Fluorescence Yields!3]

allowedtransitions
forbidden ,or unique I
KL

- 153 -C.

Systematic Data
It would be both wise and expedient to accept certain types of data from"horizontal" compilations - masses and Q-valuesI1*] , isotopic abundancest5],
etc. When such compilations are revised periodically, theidata could betransferred automatically into the file; it need not be included in thecompilation of individual isotopes.

D.

Other policies on evaluation may be established as desired. Such policies
should serve the goal described in section II.A. They should be helpful
in obtaining quality and uniformity, but not unnecessarily time-consuming
for the compiler.

E.

Citations, Notes
The policy of giving only general reference notes, as exemplified inreference!!1], is not very satisfying in a scholarly sense; but it would
seem to be the only viable way to deal with data that is often highly"derived" or "evaluated". We concur with the examples in referenceP]
that references and explanatory comments should be kept to a minimumin the data file. The primary responsibility for the quality of thedata must be with the compiler-evaluator.

IV.

MECHANISM FOR REVISION OF THE DATA FILE
The following procedures are suggested in order to facilitate establishment
and revision of the data file with a minimum of effort, but in such a way
as to encourage improvement of the data whenever possible.
A.

Accept the current decay-data section of ENDF as an initial starting point.

B.

Establish a "passive review" procedure, whereby data for new isotopes orrevisions of existing data can be proposed, reviewed, and entered into
the data file.
1.

Proposed revisions would be submitted at any time by compilationevaluation groups or other qualified scientists. [A "revision"
would (preferably) consist of a complete set of data for one ormore isotopes.]2.

A review committee would have responsibility for judging whether
the proposed revision is of adequate quality (or, in the case of
isotopes already on file, if the new data is a sufficient improvement)
Individual committee members would review proposed changes in or
additions to the data and recommend acceptance or rejection to thecommittee periodically.

- 154 -

3.

C.

V.

Committee members could also accept from data users or themselves
initiate requests for the revision or addition of data in the file.
A request list could be established and distributed to compilationevaluation groups and other potential compilers.

In general, the procedures for revision of the data file should be similar
to those used for neutron data (£SWEG committee). However, we would
prefer them to be less formal and simpler, with more reliance placed on
reputable compilers.

APPLICATIONS
The proposed content of the data file will, as described above, permit theuser to obtain a complete set of decay data (all radiations, etc.) for agiven isotope or isotopes. Certain quantities Ceg. conversion-electron energies
and intensities) would require the use of programs in addition to tabulated
data in the file. Some such "computed" quantities could also be pre-computed
and tabulated in the file - for example, average energies (I E^ x 1^) for
each radiation type, which are already being compiledt1]
Many programs of the type required already exist. For example, the Table of
Isotopes Project has programs for computing internal conversion coefficientsand beta-decay properties (log ft, EC/6+ and EC subshell ratios, average beta
energies). These and other programs (a-decay hindrance factors, Clebsch-Gordan
coefficients, etc.) are available as an on-line program package, accessible froma standard teletype connected to our computer center via a telephone. In the
future, we plan to add programs to this package that will permit access to adata file and provide both tabulated data and calculated quantities based on
the data. We also provide magnetic tapes containing the Hager-Seltzer TablesL J
upon request.
Further development and dissemination of programs can procede along the linesof programs used with ENDF.

- 155 REFERENCES

1.

S. Pearlstein "Computerized Libraries of Nuclear Data for Applications",(April 1, 1974).

2.

L.J. Jardine and C M . Lederer, Lawrence Berkeley Laboratory Report 208,
(submitted to Nucl. Instr. Methods), (February, 1974).

3.

W. Bambynek et al., Revs. Modern Phys. 4£, 716 (1972).

4.

N.B. Gove and A.H. Wapstra, Atomic Mass Tables; the most recent is
Nuclear Data Tables All, no. 2,3 (1972).

5.

N.E. Holden, "G.E. Charts" and unpublished data.

6.

R.S. Hager and E.C. Seltzer, Nuclear Data Tables A4_, 1 (1968); reprinted
in Atomic and Nuclear Data Reprints l_, 1 (1973).

- 156 -NUSPEC*(Nuclear Spectroscopy Interactive Program Package)
Table of Isotopes ProjectLawrence Berkeley Laboratory

I.

Introduction
This is a brief "how to use it" write-up for off-site use of the NUSPEC program
package. Section II explains how to connect a teletype to the LBL computer
center via telephone lines; section III explains how to call up and run the
programs.
NUSPEC consists of a group of programs callable from an executive monitor
routine. Programs currently available include:
ICC

Interpolated internal conversion coefficients and subshell ratios(Hager and Seltzer)

LOGFT

Calculated log ft values, EC/g+ ratios, EC shell ratios, and averagebeta energies.

HF

Hindrance factors for alpha decay (One-body model, Preston equations)

CLEB

Clebsch-Gordan coefficients

AVG

Number-averaging program (weighted or unweighted).

FSM"The suggestion box" This allows you to send messages on problems
encountered in your use of NUSPEC programs, or other thoughts you
wish to convey- to us. (Compliments will be accepted graciously.)More programs will be added in the future.
C M . Lederer
A. Shihab-Eldin
L.J. Jardine

Programs developed under the auspices of the U.S. Atomic Energy Commission
and the U.S. National Bureau of Standards.

- 157 -II.

How to Connect to the Computer Via a Dial-Up Line.
Note: The LBL telephone number (central switchboard) is: (415) 843-2740
In case of problems, the following extensions may be useful:Computer center (for problems withthe teletype connect system or
the B-machine)

ext. 6211(FTS - dial
(415) 843-6211)

C M . Lederer, Table of Isotopes
Project (for problems with the
NUSPEC programs)

ext. 5995(FTS - dial
(415) 843-5995)

Steps 1-6 below are the normal sequence for accessing LBL computers witha teletype and modem. Step 7 is required only if phone contact is broken
after a job has begun.
1.

Set the full-half duplex switch on the modem to full duplex.
Turn the modem on.

2.

Phone to one of the following teletype-port extensions at LBL:
6351
(for normal, 10 CPS teletypes)
5752(for 30 CPS teletypes)3.

As soon as the carrier signal (high-pitched whistle) is heard,
place the phone quickly on the modem cradle. Set the teletype"off-line-local" switch to line.

4.

To test the connection, type:>T(|)(Q?) stands for the "RETURN" key)

The computer should respond with the time and date. You are now
connected, and can skip to step 5. If the computer fails toreturn the time and date:a) If the teletype is "frozen", strike the "break" key.
b) If there is no "echo", or print of typed characters, typea colon (:); if this doesn't cure the problem try step "e"below.
c)

If the computer responds to > T ® with a question mark, try>T(j£) again. If this still fails, type > B ® to check thestatus of the B-machine. (If the computer returns B DISCONNECTEDFROM RECC, the computer is down.) Try <§(?£> to get the latest"broadcast message" on the computer status. As a last resort,call ext. 6211 and gripe.

-158 -d) Type >DC(§) , in the case that the last dialer hung up before
disconnecting from a job.
e) Type >PF(K) to insure that the teletype is not in paper-tapemode.
f) Try > T @ again.
5.

Now begin the NUSPEC job, as described in the following section (III).

6.

When done, make sure the job has concluded (the last teletype response
should be JOB ENDED - DISCONNECTED) before hanging up!

7.

If phone contact is broken while a job is running (after the "jobcard"
has been entered), the program may continue to run (and use up connect
time!), but cannot be reliably accessed. If this happens:a) Call the computer center (ext. 6211)b) Ask for the "I/O desk"c) Ask the I/O person to have the B-machine operator kill the job.
Be sure to identify the job by job name (returned when you enter
the jobcard - NUSPEC04 in the example on the next page); your name(the last thing on the jobcard); and the fact that the job is in
the B-machine.
d) Re-dial to the computer (steps 1-4 above), and check the job
status by typing:»NUSPC04®

C»job name© )The computer should respond:
NUSPC04 JOB CONCLUDEDorNUSPC04 IN OUTPUT QUEUES...
If the job is still running, wait a few minutes and check again.
e) Then start a new job, as in the following section

- 159 -III. How to Run a NUSPEC Job.
The following example of an acutal job shows how to
1.

start a NUSPEC job, and2.

call and use two of the programs:a) CLEB, to obtain one C-G coefficientb) ICC, to obtain one conversion coefficient

LINES YOU TYPE ARE UNDERLINED TO DISTINGUISH THEM FROM THE COMPUTER'S RESPONSES.
READ THE FOLLOWING NOTES 1, 2 AND 7 BEFORE BEGINNING.
useful, but less essential.)(The other notes are.(The computer prints "!" when return key is struck.)See note 1 below)>LOG!
LOGIN CP-S5 TTY-071
12.46.52.**BKY56B*B*02/25/74.
ENTER JOB CARD OR »END_*_(See note 2)
4
NUSPC* 12*40*20000. account, jiameI
NUSPC04' LOGGED I N ^ SESAME 1 . 0 ENTERING tEDIT(wait
for OK before
proceeding)OK - »EDIT
1 LI BCOPY#BDG»CONTROL/XR*NUSPEC. I-(This line must be correct.
tRUNl
If you notice a mistake after
TOI EXECUTIVE MONITOR. PROGRAMS ARE striking return, retype the
ICCline before typing +RUN!)
LOG FT
HF
CLEB
AVG

FSM
LIST
STOP
PROGRAM-

-160-At this point, enter the program you want. A sample sequence for obtaining
one Clebsch-Gordan coefficient and one internal conversion coefficient is:
PROGRAM*CLEB!
PROGRAM CLEB I S IN
DO YOU WANT GENERAL I N S T R U C T I O N S ? ^DO YOU WANT I-K<DEFORMED NOTATION)?^!
SPHERI CAL NOTATI ON. OPTI ON? J l , J2# J3*M 1,M2,M3
DO YOU WANT DETAILED INSTRUCTIONS FOR J-M?N f
J l * J2,J3*M1>M2*M3=1> 1 * 2 , 0 , 1, 1 !
RESULTS

—Jl
J2
J3
Ml
M2
M3CLEBCOEFF
1.0 1.0 2.0 0.
1.0 1.0.7071068
DO YOU WANT MORE J-M CLEB COEFF7N t
DO YOU WANT I-K CLEB?(CLEB EXITS IF NO)N I
CLEBTY STOP* CONTROL BACK TO MONITOR
MONITOR RETURNING NEXT PROG RAM* I_CC_!
ICC HAGER-SELTZER INTERPOLATION PROGRAM
DO YOU WANT INSTRUCTIONS?^
Z=HG_!
ENTER UP TO 10 SHELLS OR RATIOS.
ENTER OK TO END LIST
1. SHELL°TOTAL!
2. SHELL" OK!
ENTER UP TO 25 ENERGIES.
ENTER OK TO END LIST
1. E«411.8j
2. E«OK!
ALL MULTIPOLARITIES?N1
ENTER UP TO 7 MULTIPOLARITIES.
ENTER OK TO END LIST
1 . MULTIP."E2t
2 . MULTIP.«OK I
Z« 8 0 INTERPOLATED ICC
E

E2

TOTAL
411.80

4.43« -2)
MORE ICC7NI
MONITOR RETURNING NEXT PROGRAM*STOP!
JOB ENDED - DISCONNECTED

CLEBSCUARE.5000000

-161 -

Notes:
1.

If the computer responds to >LOG(R) with ALREADY CONNECTED, type >DC(R) ,and then try >LOG(§) again.

2.

The "jobcard" must be entered quickly.
mation that you must provide:

It includes the following infor-"account11, which must be your account number,"name" - your name
NUSPC is the job name. The computer appends a 2-digit sequence number.
The job name with sequence number (NUSPC04 in the example) must be used
when reconnecting to a job (see note 9b below), or when requesting thatan operator kill the job (see II.6.c).
3.

All programs offer instructions for use when called from the monitor.
These instructions and subsequent requests for user input should makeit easy to use the programs without additional instructions.

4.

Some general notes on data entry are:a) All "yes-or-no" questions may be answered Y ( ^ or N Q ^ .
b) "Real" quantities (eg. energies, intensities) may be entered aseither decimal numbers, integers, or exponential numbers. Examples
are:105.030.9999105
11.05E29.999E-1"Integer" quantities (eg. mass number) must be integers.
c) Z (atomic number) may be either the atomic number, or the element
symbol (without capitalization) - eg. NA for sodium (Z=ll).
d) Energies are in keV in program ICC, in MeV in LOGFT and HF.
e) Strike the RUBOUT
key to delete the last character typed,
the LINEFEED key to delete the entire line,
the RETURN
key to send anything to the computer.
(Once RETURNed, a line cannot be rescinded.)-162 -

5.

All programs ask MORE_? after printing the results of each computation
If you answer no, the program stops, and execution returns to the monitor.
(The job does not end.)

6.

If you don't understand how to answer any program's request for input,
type f D R O P Q ^ . The program will abort, and execution returns to themonitor. (The job does not end.) You can request the same program again
and accept its offer of instructions, if you wish.

7.

To end a job, when the monitor routine asks:
NEXT PROGRAM=
answerBe sure to do this when you are finished. After the computer responds:
JOB ENDED - DISCONNECTED
you can hang up.

8.

There are several ways to interrupt long printouts of results. To stop
the current line of printout, strike the LINEFEED key. The computer will
skip the rest of the line and continue with the printing of the next line.
To terminate long printouts:a) while the teletype is printing, strike any character, followed by
the return key. The teletype should stop after finishing the currentline.
b) When the teletype has stopped, again type any character*, followed by
the return key. The program may print several more lines of output,
and then asks:
END TTY PRINT?
If you answer yes, the remainder of the printout will be skipped.

9.

Any user input line that begins with > or @ is a special system command.
The input line is completely ignored by NUSPEC programs.
Some system commands have already been described (>T, >LOG, >B, >DC, @ ) .
A further explanation of some useful ones is given here in brief:

Avoid (or use advisedly) the characters Y or N; if the printout is alreadynear completion, this character may be taken as the answer to the next
request for data input, rather than as a signal to end print. The next
request for input will be the yes-or-no continuation request, eg. MORE LOGFT?

-163 -

a)>BVg)

returns the status of the B-machine, in which you
are running.

b)>DC(g)

will disconnect from the job*. This is a good idea
if you must leave a teletype that is awaiting input
for more than a few minutes**, since it avoids
some connect~time charges. The job is reconnectedby typing>RC.NUSPCnn

where nn is the correct sequence number for yourjob (>RC. NUSPCJ34(R) in the above example). Then type>N©

to avoid receiving unwanted "dayfile" messages in
the middle of the program output, and answer thequestion the program asked before you disconnected.

»NUSPCnn ®

returns the status of the job. If the nn is omitted,
the status of the job with the highest sequencenumber is returned. Possible status for an active
job could bec)

XEQ - 66B (executing)
WAIT TTY ACTIVITY
WAIT MEMORYWAIT FOR PSS Ohen first calling a program)
JOB CONCLUDED
or(indicates the NUSPC job was
stopped or failed; a new one
must be started.)

IN OUTPUT QUEUES..
JOB STATUS UNKNOWN
CNote:
d)e(indicates a major computer
failure is in progress.)

Be sure you have asked about the correct
job name + sequence number before you panic.)

returns the last "broadcast message" on the statusof the computers. (It is a good idea to check thisbefore trying to begin a job.)sends a one-line "Message..." to teletype number nnn.
nnn must be a 3-digit number - use leading zeros ifnecessary. (Your own teletype number is returned
when you LOG in to start a job.) The message will be
printed only if the receiving teletype is connected
to a line and turned on.

)@nnn Message.

*

Disconnect only after input has been requested, not while waiting for a
program to begin, or for the monitor to return.

** Warning: Jobs inactive for longer than about 2 hours will be killedautomatically by the system.

- 164 -10.

Don't leave idle jobs running:=$4.00/hour.

the teletype connect-time charge is(All computing charges,except connect-time, are limited by the 40 CU tii
limit on your jobcard [40 CU's -S2.00]. Most jobs should require lessthan this amount.)- 165 -Draft Statement by D. Horen, 30 April 1974

1.

Compilation of General Nuclear Structure, properties bymass chain
The major groups which appear to be foremost at the present time

as regards the compilation of general nuclear structure properties
by mass chain are: Meyerhof and Tombrello (A<£5), P. Selove (5^»A^.2O),
P.M. Endt and L. van der Leun (21<:A^44)t "the Nuclear Data Project at
ORNL (A^-45) and Dzhelepov and Peher and coworkers (all A ) . As has
been noted previously, there has already begun to be some efforts tocommunicate and collaborate among these groups.
a)Since it has been clearly documented that the compilations

produced by these groups are used extensively by basic researchers,
applied workers and those who prepare their types of compilations,the participants strongly feel that it is essential that these groups
continue to be supported and strengthened to ensure continuity of theirefforts.
b)

In view-of the fact that a number of the participants haveexpressed a concern as to whether the present groups have, or will
have, adequate means to maintain the compilations for which they have"assumed" responsibility on a reasonable basis (e.g. within about a
4-yr. cycle), it is recommended that a study group (possibly the INDC)
be set up to query the relevant groups involved.
c)

At the same time, it is strongly recommended that other groups

which evolve interests in these areas be encouraged to do so in close
consultation with the already existing groups.

- 166 -2.

Regarding the question (i.e., either philosophical or practical)of establishing an international division of the compilationof general nuclear structure properties by mass chain, theparticipants note the following:a)Historically, the existing groups have evolved in their own

ways and have developed their own particular methodsb)and expertise.

One might offer scientific, political and possibly economic

reasons for recommending a more international participation (e.g., theestablishment of many groups each of which would assume responsibility
for a specified number of mass chain compilations).
c)

One should, however, recognize that in the process of carryingout such a possible program as indicated in b ) , certain problems would
undoubtedly arise (e.g. logistics, evolution of systematic procedures,etc.).
Since the present meeting is supposed to consider recommendations which
will result in the maximum benefit, to the users of such compilations,the participants are extremely concerned that if a new order of things
does materialize such thata)the existing groups are forced to obtain outside assistance due tolack of direct support, or thatb)some formal international agreement develops to distribute the

load,
c)

every effort be made to assure that the broadening compilationbase be effected in a manner which will maximize the output and qualityof these type compilations.

3.

More Specialized Compilations of Structure Properties.

Here, the participants note a variety of compilation efforts ranging
over a broad spectrum.
two major categories.

In particular, they devote their attention to- 167 -a)Specific Decay Scheme compilations such as those prepared by the

Euratom Group.
b)

Nuclear Decay Scheme at Properties compilations which draw

heavily upon the General Nuclear Structure Properties by Mass Chain
type compilations as mentioned above. Here one notes the Table of
Isotopes, the various Charts of the Nuclides, etc. The participants
recommend that support also be continued for these necessary and provencompilation efforts. The participants see an existing and potentiallyunique role associated with the precision-type compilations of theEuratom group in the areas of radioactivity, possible questions whichmight aiise in a legal sense involving the use and specification of
nuclear radiations, and specialized applications,.
The extensive use of the Table of Isotopes and Charts of the Nuclides
by applied users has been extensively documented. Again, theparticipants recommend that workers interested in participating inthese type compilations be encouraged to do so, and to communicate
with the presently leading groups in these fields, i.e., the Euratom
Group for the precision type decay scheme compilations and the Tableof Isotopes for the broadly based user type in an attempt to coordinate
their efforts and draw upon existing expertise.

4.

Dissemination of Compiled Data

The dissemination of compiled data is presently accomplished by avariety of means, some of which are as follows:a)Publication in primary research journalsb)

Publication in commercial journal of booksc)

Private communicationsd)Computerized formatse)Data or Information centers

- 168The participants recognize the merrits and needs for all of thesemethods, but in view of the expansion in the general usage of muchof the compiled data, they recommend that computerization efforts
be speeded up, with particular emphasis given to facilitatingexchange.

- 169 -April 26, 1974

TO

Participants of Specialists Meeting on Nuclear
Data for Applications

FROM

G.A. Bartholomew

STATUS OF AUTHOR'S GUIDE
Following distribution on 18 August, 1972 toeditors of some 50 nuclear physics journals (a list suppliedby A. Wapstra) of the recommendations drawn up by IWGNSRD(attached), journal responses were obtained as follows:
1.

Phys. Rev. Letters 2_9_ (Oct. 72) 9

editorial note2.

Nuclear Instr. and Meth. 105_ (1972) 395

3.

Nuclear Physics A202 (197 3) No.3 and several
subsequent issues - back cover spread

4.

Phys. Rev. C7_ (1973) No. 3 Additional Information
for Contributors (appears periodically in journals)

5.

Can. J. Physics - recommendations to be sent to authorsof poorly organized manuscripts

6.

Dissertation Abstracts - recommendations sent to Deansand Librarians of schools using the abstracts

7.

Indian J. Phys. - editors stated journal already follows
reconunendations
Following a recommendation of the joint meeting of

INDC and IWGNSRD members March 17, 1973 (after the Paris
Symposium) a letter was written to the Secretary General IUPAP
to acquaint him of these efforts and to suggest IUPAP may wish
to support the activity in whatever way it felt appropriate.

- 170 -Recommendation to Editors of .journals

1.

While brevity is a cardinal virtue, the description of theexperiment should be in sufficient detail to enable thereader to judge the reliability of the data presented andof the precision claimed. Naturally a reference to such a
description in an earlier publication would be equallyacceptable.

2.

A clear statement of the errors (systematic or statistical)of the result and how they are derived is essential.

3.

If the results are relative to or depend on some othermeasured or calculated quantity this should be clearly
indicated, its value(s) and its error given and its origin
stated.

4.

a) Data should clearly stand out from the text, e.g. intables.
b) Within tables, the authors1 new measurements should be
kept separate from values derived from other sources.
c) Experimental data should be distinguished from results
derived using,theoretical Nuclear Models.

5.

If an extensive tabular presentation of the data does notform part of the published paper but is available in alaboratory report or from a data centre this should be
explicitly brought out.

6.

Previously published material, e.g. abstracts, laboratory
reports, conference reports, etc., which are supersededby the paper presented should be explicitly indicated.

7.

It would be desirable if the abstract would be supplemented
by the use of the keyword system following the practice of"Nuclear Physics".

- 171 -B.

Statements from participantsin the Specialists' Meeting, concerning their home programme on nuclear data- 172 -1. Present compilational activities in The Netherlands

P.M. Endt

1.

Atomic masses (instituut voor Kernfysisch Qnderzoek, Amsterdam).

The last compilation in this series, by A.H. Wapstra and N. Gove,appeared in Nuclear Data Tables (1972).

2.

a) Mass-chain compilations covering the A = 21-44 region "byP.M. Endt and C. van der Leun (Utrecht University). The lastissue in this series (No. V) appeared in Nucl.Phys. A214 (1973) 1.
b) Compilations of the strengths of gamma-ray transitions
between bound states (by the same authors).

One paper appearedin Atomic Data and Nuclear Data Tables 1_ (1974) 67; a second isscheduled to appear in Nucl.Phys.

None of these activities is subsidized. For the authors they area part-time occupation. There is no paid staff or full-time secretarialhelp.

- 173 -2. Remarks on the dissemination of non-neutron nuclear data
D. Horen, Nuclear Data Project * ORNL

1.

Since the neutron 4-centers already have a system forinternational exchange of nuclear data J. recommend that this network be utilized in the following ways:
The centers learn of non-neutron data needs for applied
areas.

(Suppose from internal data committees e.g.) but also

see below. They would then consult within their respective areas
with compilers, etc. and try to get information into a format for
exchange. That is, assuming information is available.

If not,of course they will have to convince (in conj. with compilers) the
funding agents to support. I believe if governments agree to anunrestricted exchange of whatever gets compiled, then the "system"
essentially exists. The pressures for what gets into the files fromthe compilers will come from a very natural source, i.e, essentiallyinternally generated. The IAEA. NDS would have a natural positionin the scheme of things without having to get bogged down in politics,
entering to individual wishes of countries, etc. It is already apart of the system and it would continue its already existing roleof holding meetings etc. to determine needs.

Of course if these seem

clearly defined and should result inrecommendation to put data into the "system1*, I think the decision
should be either through, say the IKDC or agreement of the 4 centres.

Of course, this should be discussed with 4-centers involved andallow them to consult with their funding agents.

- 174 -3» Current Status of the Table of Isotope Project. Berkeley, USA
A. Shihab-Eldin
Progress:
As of April, 1974, the first compilation of 220 mass chains has "beencompleted. The total compiler effort since the project began in 1971
i s 15-5 compiler-years. Computer processing of the tabular data is
now in routine use; the data are keyboarded and edited with a special
on-line terminal system ("IRATE"). Proofreading of tabular data is
well underway and will continue concurrently with compilation effort.
Computer-produced level schemes are now being made and proof-readingof the level schemes i s beginning.
Projection:
July 1976 i s the target date for publication of the seventh edition of
the Table of Ijotop_es. In order to maintain the present quality of effort
without delaying the completion of the Table, i t

was decided to adopt

a variable literature cut-off date for both the decay data and thereaction data of each mass chain. The cut-off date for the decay dataof a particular mass chain will be the date of the first compilation
if that i s after July 1973; otherwise i t will be the date of recompilation,i . e . updating. The cut-off date for reaction data will be the date of
the first compilation with only very selective updating.

Automation:
Automation of the processing of both tabular and level-scheme data is
progressing well. A major breakthrough last year was the completionof programs that check level-scheme data (input on punched cards) andproduce plots of the data. These programs require l i t t l e or no graphic
input information, and also store the input data on the MSS (chipstore)system at Berkeley in a form suitable for editing.
We are currently entering data from a substantial backlog at a rateof about 1 mass chain per day; about 100 mass chains have been entered todate. The data are stored on the IBM data cell with magnetic tape backup.

- 175 -4. The state of non-neutron nuclear data:
in France and within the Euratom evaluation group
J. Blachot, B. Grinberg, J. Legrand (France), and
W. Barribynek (Euratom).
I.

Evaluation of Decay scheme parameters

The need for decay scheme data, evaluated with precision, becomes more
and more evident in various fields. What is required for each data isa unique recommended value and a stated associated accuracy. Some
examples can be given. The users of radioactivity standards are numerous
and belong to very varied fields; what they require is the best possible
standard. This implies for the radiometrologieis, who prepare and deliver
these standards, that they could rely upon very good and indisputable
data. In the field of nuclear energy there is a need for evaluated decay
scheme data of, for example, the following radionuclides: ^52cf, 237Np,^opuj 241AJII. The reactor people are interested in good data for longlived fission products. They are also interested in those radionuclides
which can be used as monitoring detectors. These examples are only some,among others, which could be given.
Euratom GroupThe so-called Euratom Group was started for the reasons given above.
The critically evaluated decay properties of *^Co, 5°Co and 51cr andthe evaluation rules adopted by the group have been published.* For
the moment, the activity of the group has been interrupted for exclusively
practical reasons. It is strongly hoped that evaluators from as many
countries as possible, will join and reinforce the group - so as to allow
a reasonable amount of radionuclides to be evaluated within a reasonabletime.
French table of evaluated radionuclide decay scheme parameters
Due to the temporary interruption of the Euratom evaluation group, andalso because of the requests from numerous users, it was decided to
publish a table of evaluated radionuclide data under the auspices of
the French Atomic Energy Commission. The evaluation was based on the
Euratom group rules, but is not as exhaustive as mentioned above: foreach nuclide the nubmer of evaluated data is smaller. The evaluationof 200 radionuclides is planned. The first publication (second semesterof 1974) will contain about 30 radionuclides; it is envisaged to bring the work
to an end within 5 years. The accomplishment of this work is greatly
facilitated by the existence of the Nuclear Data Sheets and the Recent
References of Nuclear Data Project. It is evident that when the Euratom
Group will resume its activity, the data evaluated by the Euratom groupwill be incorporated in the French table. This table is established under
the scientific responsibility of J. Legrand.

* Atomic Energy Review, H., 3 (1973)

- 176 II»

Library of Nuclear Data for the "Fission Products'*

1.

Neutron rich isotopes are classified by A-chain from 71 (Zn) to
170 (Tin), with the following data?
- Half life and uncertainty,- Decay mode (QB , QB , Alpha) with the energy uncertainty andintensity,- (3 energies and intensities, and- y-ray energies and intensities with uncertainties.

An indication is given whether the intensities are absolute or relative,
and all data are referenced. Other information or comments are given at
the end of each isotope. Seventy to eighty, percent of the data have beentaken from the "Nuclear Data Sheet".
2.
The main users of this library are people working in fission reactor
technology. The 1972 - 1973 version of the library was written in an" E N D P / B I I I format on magnetic tape [l], and can be obtained from CCDN (Saclay).
3.
The library is being continuously revised and extended. A new editionis scheduled to be released this summer as a CEA Report. We have chosen touse a simpler format for updating the library. Later on the new librarywill be converted to the ENDF format by using a program.
4.
A sample of a computer listing for two isotopes is enclosed herewith.
This library is established under the scientific responsibility of J. Blachot(CENG).

[1] C. Devillers et al Meeting IAEA March 1973

5 С SN3 27M- 177 -

4 . 4 0 0 + / - 0 . 1 0 0 *>CPF-

ENERGIE • / - ERREUR
3?00.C00
0.0BÊTAS-KEV
7 ¿NOS% A

7 2ND S

N3- =F:-N"R6ÏE +/- ERREUR K S V
27CC.CC0
ICC.CCONG = 3

INTENSITE •/- ERREUR
0.0
0.0% ABSOLU

INT5NSÏTE • / - ERREUR
100.000
C.O
5.300
1.400
A.400
1.800

% RELATIF

7CHES

EMERG1E +/- ERREUR
491.200
C.100
1343.C00
0.100
1564-.CC0

BRANCHEMENT + / - ERREUR
ICO.000
0.0

0.200

CO4F\'TAIRES
CVu piDSITIÛN ISOMERE INCCNNuO

7/2/74J.«.

52 TE127F

T= 109.CCC + / -C8FE1T

72NDS

2.000 J

ENERGIE • / - ERREUR KEV
781.260
5.000 71WAP
Ê8.26C
0.0
72NCS•• BETAS-• • GAMMAS

% A

72N0S

NB-'

ENERGIE +/- ERREUR
64.0000.0
130.000
0.0
152.000
0.0
723.000
0.0

BRANCHEMENT •/- ERREUR
?.4OO
0.0
97.600
0.0

KÊV

NG

ENERGIE +/- ERREUR KEV
57.6300.080
593.3C00.1C0628.600
0.300
6 51.000
2.000
658.Í00
0.1C0
COMMENTAIRES
CVN AUT REF 73K4L1 72KAI IGA

INTENSITE •/- ERREUR
0.010
0.0
0.002
0.0
0.001
0.0
2.400
0.0

% ABSOLU

INTENSITE +/- ERREUR
56.000
5.000
C.240
2.000
0.090
2.0C0
0.030
1.000
1.300
10.000% ABSOLU

67APS• F = 0.0099

- 178 5.

Sammary of Nuclear Data Evaluation at ECMN, GEEL
W. Bambynek

In the Joint Research Centers of the European Community little work
is done on compilation and evaluation of nuclear non-neutron data.
There is the European working group on evaluation of radionuclide
decay data. The philosophy and the rules are published (Atomic Energy
Review _11, 515 (1973)» and have been explained by Dr. Grinberg at
this meeting.
At the CBNM (Geel) 4 physicists are working part time on evaluationsin addition to their experimental work. It belongs to the principles ofour evaluation group that the evaluators are experimenters working
actively in the field.
The "Euratom group" is not limited to members of the European Community.
Every laboratory or group that has an interest "to join our effort is invited.

- 179 -6. Status Report of the NEA Neutron Data Compilation Centre,
Saclay* FranceF.

Froehner

The Centre de Compilation de Donnees Neutroniques (CCDN)
operated by the Nuclear Energy Agency (NEA) of the OECD at
Saclay (France) is part of the world-wide 4-centre network ofneutron data centres, servicing Western Europe and Japan. It
has its own small computer and a permanent staff of 17(8 physicists, 2 programmers, computer and clerical staff).
Regular data exchange with the sister centres (NNCSC Brookhaven,
IAEA/NDS Vienna, CJD Obninsk) ensures that the same data are
available at all centres. The CCDN data base consists ofessentially four computer files, namely(1)

the bibliographic file CINEA with about 110 000 entries for
20 000 publications}(2)the numeric file NEUBABA with about 2 000 000 measured data
points and associated non-numeric information;(3)

evaluated files in various formats (ENDF, UKNDL, KEDAK etc)with about 600 000 evaluated data points;(4)

the international request file WRENDA with more than 1000
official requests for neutron data measurements.

These files contain mostly neutron data, but in response touser needs more and more other nuclear data are beooming available,
e.g. photon interaction data, nuclear structure and decay data forfission products etc.

- 180 The services of the CCDN consist of(1) data dissemination service: all data users can orderretrievals from the computer files - either directly ifthey work in the CCDN service area^or indirectly throughtheir regional centre. During the last year the CCDN-

56O requests for measured data,-

I50 requests for evaluated data,-

20 requests for CUJDA retrievals.

received

These requests were often quite complicated so that on the
average 5-6 computer searches of the files had to be made.
In addition, about 35 requests for plots were satisfied.
The normal time delay between receipt of a request anddispatch of the answer (listing, tapes, plots...) is 2-3 days.

(2) publications: The contents of the CINDA file are publishedannually in book form. CCDN produces the tape which is used tosteer the printing. The CCDN Newsletter announces recent
additions to the files, whereas the Neutron Nuclear Data
Evaluation Newsletter (NNDEN) informs on neutron data evaluation
activities.

Special-purpose tabulations are produced directlyfrom the computer files, e.g. EANDC 95 "U"* a tabulation of neutron
threshold reaction cross sections for dosimetry and other applications.

- 181 -7. Remarks on Computerized Nuclear Data Files
S. Pearlstein

On the subject of nuclear data for applications I am more
optimistic than ever "before. The sophistication of the user
has advanced to the point where the transport of neutrons andphotons^and fission product burnup and decay are calculated fromfirst principles with encouraging results. This good-turn of
events has made the user, measurer, compiler and evaluator of
nuclear data more dependent on each other. The entry of thelarge scale user of data has also made computerized files more
important. I have submitted some examples to this Meeting (seepapers H

and 12

given in section A ofthis report) andwould be pleased to receive comments on the material.

- 182 -8. Compiling Projects at Chalk River Nuclear Laboratories (CRNL)

G.A. Bartholomew

CRNL does not have an ongoing formal datacompilation program. Various compilations have been
produced in the natural course of activities at thelaboratory, for example in neutron capture 7-rays, fission
product yield data, nuclear g-factors, 7-rays ordered byenergy, and others.
Physics Division (CRNL) is willing to aid innuclear data compilation activities originating elsewhere
to a degree compatible with existing research programs
and objectives but there is no present plan to allocate
staff permanently to compilation activities. We welcome
requests for help or collaboration in compiling; we would
take all such approaches seriously but would treat them on
an individual basis.
Coordinated programmatic nuclear data activities in
Canada have, till now, been limited to neutron cross section
and related data for the reactor program; these activities
were under the surveillance of the Nuclear Data Committee,
Chalk River. Steps are now being taken in an effort to broaden
this coordination to other types of nuclear data and to take innuclear activities at more laboratories. This reorganization
may eventually result in greater scope for cooperative
compiling programs in Canada.

- 183 -9.

SUMMARY OF NUCLEAR DATA ACTIVITIES AT THE AAEC ESTABLISHMENTAT LUCAS HEIGHTS, AUSTRALIA
B.J. Allen

Our interests are in applications rather than nuclear physics,
the main ones being properties of fission productst and new methodsof analysis.
The level scheme and decay data have teen punched on cards for all
nuclei up to zinc. However} this activity has stopped in view of the
US task force efforts on fission product libraries. These libraries
are in a format called ENDF/B4, and we would hope to receive any such
additions to ENDP files when available. Some work could be done here
if it was not just duplication of overseas work.
Bibliographic References
A bibliography of "Prompt Nuclear Analysis'* (papers up to mid-1973)
has been completed, and is scheduled for publication in the Atomic
Energy Review. Copies are available. This could be updated on an annual
basis and computerised.
Note: This is a bibliography of applications, not of data.

Experimental Data
1. (a) "keV Neutron Capture Gamma Rays" has been published(Nuclear Data 11 (6) (1973) and there are no plans forrevising this Inhere is little activity in this field at
the moment).
(b) Thermal Neutron Capture Gamma Rays. This consists primarilyof the data of Rasmussen et al., HFCRL-69-071 as listed byDuffey et al. NIM 80 (1970) 149? Sentfle et al. NIM 93 (1971)
425). The data have been included in a computer file for use inn
Neutron Capture Analysis'*. It is planned to replace the sensitivity values (S = o c Iy/A) by a more complete listing ofOc» IV/A) by a more complete listing of oCf lyi detector efficiency,
etc. It would not be difficult to use an alternative format or
to up-date this compilation periodically with new results. However,insufficient manpower is available to carry out an evaluationof such data except perhaps for one or two cases as part of acooperative program.
(c) Proton Induced Gamma Rays. We have plans to begin listing thesein a format compatible with (b) for use in analysis using (preactions. Presumably the parameters needed will be: protonenergy (resonance), angle of observation, total gamma yield,
Ey, Iy (branching ratios). Once again, insufficient manpoweris available for evaluations.
(d) Charged Particle Reactions. Reactions such as (d,p) etc. arealso useful in analysis and suitable compilation of protonenergy groups (etc.) will be needed eventually (for example,
all proton energies and intensities for a particular incident
particle energy).

- 184 (e) A-chain Evaluations. We are not interested in becoming involved in this work, but could bring the requirements tothe notice of other nuclear physics laboratories in Australia
and New Zealand.

2. A unified format would be desirable for y-decay data whether fromradioactivity, (n,y), or charged particle reactions. This could thenbe used in automated search and attributor techniques (see l(a) above).
3. There would be no point in the exchange of raw Ge(Li) data, but only
derived gamma ray intensities.
Evaluated Data
There is no evaluation in progress, but we would be willing to consider
work on one or two cases of (n,y) reactions as part of a cooperative
program.

- 185-10.

Statement of the Liverpool University Position

J.P. Sharpey-Schafer

The Liverpool University has for many years been producing
nuclear structure data as part of its programme to improve theunderstanding of nuclear properties. Our emphasis in the last
few years, has been on level spins, parities, lifetimes,
branching ratios and multipolarities. We would like to see
evaluated compilations, of the type produced by P.M. Endt andC. Van der Leun for 21^A^44» extended to A-^45 a s we find thepresent compilations very inadequate. We would also like to see
the turn -round time for these compilations reduced from thepresent 4 to 5 years to 2 to 3 years.

As a contribution to sharing the burden of this work it isconceivable that we would be able to organize the production of
a compilation of evaluated data, for instance for 45^A^6O or_
6l^.A <74>

We would not however wish to do this if others would

prefer to make this contribution themselves and we would not want
to tread on any toes in this direction. However, if others agreewith this need and if some international delegation of areas of
responsibility can be made, we would be most willing to make an
attempt to pull our weight.

- 186 11-

Report from Sweden on activities in the field of evaluation andcompilation of nuclear data»
L. Stroemberg

In Sweden there is no permanent group set up to perform compilation
or evaluation work within the non-neutron nuclear data area.

Since about a year there exists however a National Nuclear Data
Committee consisting of people from the reactor industry, universities
and other institutions involved in basic and applied nuclear research.
The Committee's main purpose is to coordinate the activities in thefield and to disseminate information regarding ongoing and planned
activities. The Committee also annually distributes a Progress Reporton the activities in the country.
In the past, groups of specialists have taken part in evaluation
activities as a part of an international cooperation as, for instance,
the contributions by Brune and Lorenzen on the excitation functions
for charged particle reactions for activation analysis purposes andthe one by Forkman and Biilow on photonuclear reactions,

A similar situation is expected to exist even in the future, that isevaluation of data only on a rather limited scale might be possible.
For many years research groups at different institutes have beenworking on problems associated with nuclear structure and decay data.
Thus, the experience and the expertise exist and many groups could beconsidered as potential contributors. At the present time two groups
have pronounced their interest in joining an international cooperation
effort in the following areas a) Nuclear structure data, level schemes,
spins etc. in the region Z = 20 - 28 and b) Decay data for short-lived
fission products.

The first group is the one headed by Professor Bergqvist at Lund whichhave been doing an extensive study of nuclei in the f7/2 shell withdifferent particle reactions and the second group the one at Studsvik
working under Professor Rudstam. These groups are however pure researchgroups which normally do not have funds for this type of work. It istherefore our hope that this specialist's meeting come out with such
recommendations that would facilitate the financing of such projects.

- 187 -12. "The National Nuclear Data Libraries" at the I n s t i t u t u l de
Fizica Atomica, Bucarest
Al. I . Badescu-Singureanu, N. Deciu, D. Gheorghe,
N. Mateescu, Silvia Mateescu, S. Rapeanu*
Summary of a report on the Romanian National Nuclear Data Libraries:
The main problem of the organization of the evaluated nuclear data forreactors computerized libraries, the solutions adopted by the mostimportant national libraries: ENDP (USA), UKNDL (OB), KEDAK (FRG),
and the general organization of the Romanian evaluated microscopic nuclear
data library "DANEM-I" from the I.A.P., are presented.
The content of this report is:
1. The nuclear data for reactors and their evaluation
2. The evaluated nuclear data computerized library
3* The main national evaluated nuclear data computerized libraries
4. Comparison between the computerized libraries ENDP, UKNDL and
KEDAK.
4.1

The library contents

4.2

The classifications principle of the stored informations

4.3. The recorded data identification
4.4

The stored data processing

4.5

The physical medium on which the information is stored

5. The IAEA (Vienna) recommendations concerning the evaluated nuclear
data library formats.
6. The evaluated microscopic nuclear data library nDANEM-In fromthe I.A.P.
6.1

The library contents

6.2

The library structures

6.3

The stored data processing. References* Studii Cercetari de Fizica,
26, 9 (1974, to be published)- 188 -13.

REPORT ON THE YUGOSLAVNUCLEAR DATA ACTIVITIESG. Paic

The increasing usage of nuclear methods (the building of a nuclear
power plant, two betatrons and a linac for medical treatment, radiopharmaceutical production, etc.) in Yugoslavia has brought up thenecessity to consider some nuclear data evaluation in the fields
in which the need has been recognized. We are for the moment involved in some evaluation work on the Ka/Kp ratios of X-ray emission
for some nuclei.
We are therefore interested in the development of some work in specificareas and horizontal compilation work.