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NBS

' PUBLICATIONS

NBS SPECIAL PUBLICATION 626

U.S. DEPARTMENT OF COMMERCE / National Bureau of Standards

Nuclear Data for the

Efficiency Calibration of

Germanium Spectrometer Systems:

Measurements from the Laboratories

of the International Committee

for Radionuclide Metrology

a-,/3-, and T -Ray Spectrometry Group
NATIONAL BUREAU OF STANDARDS

The National Bureau of Standards' was established by an act of Congress on March 3, 1901. The Bureau's overall goal is to strengthen and advance the Nation's science and technology

and facilitate their effective application for public benefit. To this end, the Bureau conducts

research and provides: (1) a basis for the Nation's physical measurement system, (2) scientific and technological services for industry and government, (3) a technical basis for equity in trade, and (4) technical services to promote public safety. The Bureau's technical work is per- formed by the National Measurement Laboratory, the National Engineering Laboratory, and

the Institute for Computer Sciences and Technology.

THE NATIONAL MEASUREMENT LABORATORY provides the national system of

physical and chemical and materials measurement; coordinates the system with measurement

systems of other nations and furnishes essential services leading to accurate and uniform

physical and chemical measurement throughout the Nation's scientific community, industry,

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standards, and data on the properties of materials needed by industry, commerce, educational

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Engineering and Process Technology 2 — Building Technology — Fire Research —

Consumer Product Technology — Field Methods.

THE INSTITUTE FOR COMPUTER SCIENCES AND TECHNOLOGY conducts

research and provides scientific and technical services to aid Federal agencies in the selection, acquisition, application, and use of computer technology to improve effectiveness and

economy in Government operations in accordance with Public Law 89-306 (40 U.S.C. 759), relevant Executive Orders, and other directives; carries out this mission by managing the Federal Information Processing Standards Program, developing Federal ADP standards

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'Headquarters and Laboratories at Gaithersburg, MD, unless otherwise noted; mailing address Washington, DC 20234. 'Some divisions within the center are located at Boulder, CO 80303.
D. D. Hoppes and F. J. Schima, Editors

Center for Radiation Research

National Measurement Laboratory

National Bureau of Standards

Washington, DC 20234

NATIONAL BUBBAU

09 8TANDAJPM

KlBBART

Nuclear Data for the F£B 3 1982

Efficiency Calibration of auTo

'

Germanium Spectrometer Systems:

Measurements from the Laboratories

of the International Committee

for Radionuclide Metrology

a-,/3-, and7-Ray Spectrometry Group

U.S. DEPARTMENT OF COMMERCE, Malcolm Baldrige, Secretary

NATIONAL BUREAU OF STANDARDS, Ernest Ambler, Director

Issued January 1 982
i*j.:.-s.':...) jtfotytAU,

Library of Congress Catalog Card Number: 81-600161

National Bureau of Standards Special Publication 626

Nat. Bur. Stand. (U.S.), Spec. Publ. 626, 151 pages (Jan. 1982) CODEN: XNBSAV

U.S. GOVERNMENT PRINTING OFFICE

WASHINGTON: 1982
ABSTRACT

Members of the Alpha-, Beta-, and Gamma-Ray Spectrometry Group

of the International Committee for Radionuclide Metrology agreed

in 1979 to collect the nuclear data from any measurements in their

laboratories that were pertinent to the calibration of the efficiency of germanium spectrometer systems. This report is composed

of the contributions from 14 laboratories, as listed in part II.

The contributions follow in part III. If a self-contained contribution was received, it has been incorporated without editing.

Less formal communications, or references to published articles,

are discussed in short comments prepared by the compilers. Part

IV is a compilation of a selected portion of the data, arranged

by radionuclide.

Key words: compilation; efficiency data; half lives; measurement

uncertainties; photon probabilities per decay; relative photonemission probabilities.

Papers in this volume, except those by National Bureau of Standards authors, have not been edited or altered by the National Bureau of Standards. Opinions expressed in non-NBS papers are those of the authors, and not necessarily those of the National Bureau of Standards. Non-NBS authors are solely responsible for the content and quality of their submissions.

The mention of trade names in the volume is in no sense an endorsement or recommendation by the National Bureau of

Standards.
CONTENTS

Abstract iii

I. Introduction 1

II. List of Contributors 2

III. Contributions 4

Atomic Energy of Canada Limited 5

Bureau International des Poids & Mesures* 32

Central Bureau of Nuclear Measurements 33

Georgia Institute of Technology* 38

Hiroshima, Nagoya, and Rikko Universities and Electrotechnical

Laboratory, Tanashi 39

International Atomic Energy Agency* 52

Institute d'Electrochimie et de Radiochimie; Ecole Polytechnique

Federal e* 5?

Idaho National Engineering Laboratory* 52

Lawrence Livermore Laboratory* 52

Laboratoire de Metrologie des Rayonnements Ionisants .... 53

National Bureau of Standards 85

National Physical Laboratory* 100

Physi kal i sch-Techni sche Bundesanstalt 101

University of Guelph* 116

IV. Table of Selected Calibration Data 117

*Comments by the compilers, based on information supplied by

the laboratory.

i v
NUCLEAR DATA FOR THE EFFICIENCY CALIBRATION OF GERMANIUM SPECTROMETER SYSTEMS:

MEASUREMENTS FROM THE LABORATORIES OF THE INTERNATIONAL COMMITTEE

FOR RADIONUCLIDE METROLOGY a-, 3-, AND Y-RAY SPECTROMETRY GROUP

D. D. Hoppes and F.J. Schima

National Bureau of Standards

I. Introduction

Members of the Alpha-, Beta-, and Gamma-Ray Spectrometry Group (SG) of the International Committee for Radionuclide Metrology (ICRM) agreed in 1979 to collect

the nuclear data from any measurements in their laboratories that were pertinent

to the calibration of the efficiency of germanium spectrometry systems. This re- port is composed of the contributions from 14 laboratories, as listed in part II. The contributions follow in part III. If a self-contained contribution was re- ceived, it has been incorporated without editing. Less formal communications, or references to published articles, are discussed in short comments by the compilers. Part IV is a compilation of a selected portion of the data, arranged by

radionucl ide.

The following suggestions were made regarding the data. Only pertinent values

obtained or published after 1968 were to be submitted. Any published data were

to be reconsidered in the light of subsequent knowledge, and re-evaluated where

required. Sufficient detail was to be presented, or referenced, for an evaluator

to appreciate the origin and probable validity of uncertainty statements. Uncertainties were to be estimated realistically, with those which could not be determined from a statistical analysis to be defined and combined in such a way that

the total uncertainty would correspond, in significance, to the standard deviation

of the mean. The methods whereby this considerable challenge was to be met were

felt to be of interest in themselves.

The data consist of half lives (T1/2), photon (gamma- or x-ray) probabilities

per decay (Py or Px), and relative photon-emission probabilities (Pr). The

last suffice when a radionuclide with multiple gamma rays is used to generate

a relative efficiency curve, or when a source with a known rate of gamma-ray

emission at a certain energy is used as an x-ray standard. Py or Px relates

photon-emission rate to activity, and T\/2 is required when a source of known

emission rate is to be used after significant decay.

The question of which radionuclides are useful for calibration depends in part on the intended use of the spectrometer system.

If an efficiency vs_ energy relation is to be as independent as possible of past

spectrometric results, the usual requirement is for the radionuclides used to

have a transition or transitions with almost complete branching and little internal conversion. For a few nuclides, members have better established probabilities by measuring competing branches or conversion electrons. For many nuclides,

better half lives are reported. Listings of these "primary calibration radionuclides," and remarks about their selection, appear in some contributions and ref- erences. In the region below 100 keV, the requirements for decay-scheme-derived

probabilities are seldom met, although methods such as careful photon-emissionrate measurements with def i ned-geometry detectors, or theoretical efficiency calI
dilations, can still give efficiencies independent of past measurements (of fluorescent yields, for example). Even so, measured values for Py or Px have added

significance in this region.

If past spectrometri c results are acceptable, almost any source with an accurate

activity calibration becomes useful if radiation probabilities are known for

suitable transitions. Thus the efficiency calibration of a laboratory spectrometer

system can be linked to national standards even with a short-lived nuclide calibrated primarily for another purpose. Finally, the summary table contains several

radionuclides with measured relative probabilities for photons of a ranqe of en- ergies. These can be used to better define, or check, the shape of an efficiency

curve.

One purpose foreseen for the summary table was a determination of the aqreement of

data from different laboratories, perhaps relative to the estimated accuracy. For

this reason, and to limit the size of the compilation, it was suqqested that

only radionuclides for which two or more SG laboratories submitted data were to

be included. In many cases, the data were of different types, but all data satisfying the original requirement were included, and other radionuclides were added

when requested by a laboratory.

No evaluation is made in this report, although it should serve as the basis for

evaluations. Only data from I CRM SG members have been included, and only values

for radiations with probabilities greater than 5 percent of the most probable have

been listed in the summary table, with a few exceptions. It obviously does not include all radi onul ci des suitable for efficiency calibrations, even in a narrow

sense, for some, such as 94|\jb s require no better measurements of the type reported

here to be useful

.

The uncertainties given in the summary table in general are believed to be total

uncertainties corresponding, in significance, to one standard deviation of the

mean, although this is not clear in a few instances. In some cases, labeled with

asterisks, the value corresponds to about three times this value. The computer

program that generated the table does not print significant final zeros, but

their absence is apparent when the accompanying uncertainty is considered.

II. List of contributors

Contributor Correspondent Label

1. Atomic Energy of Canada, Ltd. A.R. Rutledqe AECL

Chalk River, Ontario KOJ 1J0

Canada

2. Bureau International des Poids A. Rytz BIPM

et Mesures

Pavi 1 1 on de Breteui

1

Sevres, France

3. Central Bureau of Nuclear W. Bambynek CBNM

Measurements

Steenweg op Retie

2400 Geel , Belgium

2
Contributor Correspondent Label

4. Georgia Institute of Technology

Department of Chemistry

Atlanta, GA 30332, U.S.A.

R.W. Fink GITSC

5. Hiroshima University

Department of Physics

Hiroshima, Japan

Nagoya University

Department of Nuclear Engineering

Nagoya, Japan

Rikko University

Department of Physics

Tokyo, Japan

El ectrotechnical Laboratory, Tanashi

Tokyo, Japan

6. International Atomic Energy Agency

P.O. Box 100

A-1400 Vienna, Austria

Y. Yoshizawa HNRE

K. Schaerf IAEA

7. Institut D

1 El ectrochimi

e

et Radiochimie

Ecole Polytechnique Federal

CHB-Ecublens

CH-1015 Lausanne, Switzerland

8. Idaho National Engineering Laboratory

EG&G Idaho, Inc.

Idaho Falls, ID 83415, U.S.A.

M. Decombaz

R. Helmer

IER

INEL

9. Lawrence Livermore Laboratory

University of California

Livermore, CA 94550, U.S.A.

10. Laboratoire de Metrologie des

Rayonnements Ionisants

Boite Postale No. 2 F-91190 Gif-sur-Yvette, France

11. National Bureau of Standards

C112 Radiation Physics

Washington, DC 20234, U.S.A.

12. National Physical Laboratory

Division of Radiation Science

Teddington Middlesex TW111 0LW

United Kingdom

R. A. Meyer

J. Legrand

D. Hoppes

P. Christmas

LLL

LMRI

NBS

NPL

3
Contri butor Correspondent Label

13. Physikal isch-Technische Bundesanstalt

Bundesallee 100

D-3300 Braunschweig, FRG

K. Debertin PTB

14. University of Guelph J.L. Campbell UGDP

Department of Physics

Guelph, Ontario NIG 2W1

Canada

III. Contributions

These follow in the same order as listed in part II, and vary in lenqth

from full articles to a remark about references.

4
ATOMIC ENERGY OF CANADA LIMITED

DECAY DATA FOR RADIONUCLIDES USED FOR

THE CALIBRATION OF X- AND y-RAY SPECTROMETERS

by

A. R. Rutledge, L.V. Smith and J.S. Merritt

ABSTRACT

Half-life values and y-ray emission probabilities are summarized

from results determined by the Radioisotope Standardization Group over

the past decade or so. Half-life values are given for thirty-three

7 X8 22 2 A A2 A 6 51 5 A radionuclides: these are Be, F, Na, Na, K, Sc, Cr, Mn

,

56.. 60p 64 _ 65... 82 85c95... 9% m 109 . 113 T m 113_

Mn, Co, Cu, Ni, Br, Sr, Nb, Tc , Pd , In , Sn,

115 T m 133 v 133^ 134 134 p m 137R m 137 r 139 n 141_ 152_

In , Xe, Ba, Cs , Cs , Ba , Cs , Ce, Ce, Eu,

169v, 198 A 203u , 233^ „ . . , Yb , Au, Hg, and Pa. Gamma-ray emission probabilities are

* u j . ... 7„ 42TT 65„. 75„ 85„ 99 m

given for the eleven radionuclides Be, K, Ni, Se, Kr, Tc , 113 T m 115 T m 137^ 139„ . 141^ „ . . . . , , , In , In , Cs , Ce, and Ce. Counting equipment included the

4tty ionization chamber, the 4tt3-Y coincidence system, and a Ge(Li) counter.

Each method of measurement is discussed. A statistical uncertainty of one standard deviation has been used throughout and detailed information is

given about the assessment of other uncertainties. The impurities found

or suspected in twenty-one of the reported samples of radionuclides are discussed in an appendix.

Chalk River Nuclear Laboratories

Chalk River, Ontario, Canada KOJ 1J0

March 1980

5 AECL-6692
1. INTRODUCTION

The a-, B-, and y-ray Spectrometry Working Group (SWG) of the

International Committee for Radionuclide Metrology (ICRM) has requested

information about measurements of y -ray emission probabilities and halflives for radionuclides that are issued as standards for calibration

purposes. Rather detailed information was requested, especially about the

assessment of uncertainties in the final values. The SWG plans to examine

critically the collected data to draw attention to discrepancies, and

to encourage further and more accurate measurements to resolve these

discrepancies. Ultimately this should allow Y~ ray spectrometers to be

calibrated more accurately.

This report is the contribution from the Radioisotope Standardization

Group of Atomic Energy of Canada Limited (AECL) to the SWG, and it summarizes

and reviews such measurements made in this laboratory during the past decade

or more.

2. GENERAL REMARKS AND LISTS OF DATA

The attempt by the AECL Radioisotope Standardization Group (RSG) to

summarize its data in a consistent manner has been complicated by the

fact that while the results of some measurements have been fully documented

others have appeared only as short paragraphs in Physics Division Progress

Reports. In the past the RSG has generally used a confidence interval of

3a for the statistical uncertainty and estimates of other sources of uncertainty usually were added linearly. To conform with the request of the SWG

for consistent statements about accuracy at a confidence level of 68%, in

order to facilitate recognition of discrepancies and a uniform evaluation

12) . of the data '

, considerable research and recalculation were required.

As a result, in most cases the uncertainties in the values tabulated in

this report differ from those in the referenced publications or reports.

The radionuclides for which half-life data are submitted are listed

in Table I. Column 2 gives the number of half-lives over which observations

have been made, followed by the number of observations in brackets. The

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43 o T3 9
counting equipment used is listed next. Then the completion status is

given: 'No' indicates that the experiment is ongoing> 'Yes' indicates

the converse. Most of the entries indicated as ongoing are for rather long

half-lives (>2 a) ; it is planned to continue these measurements for several

more years and to update the values at appropriate intervals.

The half-life values are given in the fifth column. The stated

uncertainties contain statistical and systematic components; Table IV gives

a breakdown of the contribution from various sources of uncertainties to

this overall uncertainty. For most of the measurements, the decay of the

radionuclide was followed for one or more samples prepared from the same batch of the radionuclide; the statistical uncertainty used here is one standard deviation in the least squares fit to the counting data. In other

cases half-life values from more than one preparation or supply of the

nuclide were obtained. These are identifiable where Table I, column 2,

shows a range in the number of half-lives followed. For these cases the

external error in the weighted mean value is used as the statistical *

uncertainty.

Details about our estimates of sources of systematic uncertainty

are given in sections 3 and A of this report. Column 5 of Table I lists

the overall uncertainties for each nuclide. Where there is only one known source of systematic uncertainty its estimate is added to the statistical

uncertainty to get the value shown in the table. Where more than one source

of a systematic nature is estimated, the individual estimates are combined

in quadrature and then added to the statistical uncertainty. Because the

number of known sources of systematic uncertainty is very small, other

2 3) published methods of combining statistical and systematic uncertainties '

seem less appropriate here; they would tend to give smaller overall

uncertainties

.

In the reference column the letters PRP indicate that the only

available account is in an AECL Physics Division Progress Report.

Table II lists the radionuclides for which we have determined

gamma- ray emission probabilities (P ) . The energy of the gamma ray

and the Y-count ln 8 equipment are also listed. P^ is given in percent

10
Table II

Radionuclide

Radionuclides Issued as Standards for which

Data are Submitted to SWG of ICRM

E (keV)

Y

y-counting

equipment

Py

(%) Reference

Be

42.

65Ni

75

85

Se

Kr

99

Tcm

113 T m

In

•115 T m

In

137

Cs

139

141

Ce

Ce

477

1530

1482

400.5

510

140 and 142

392

336

662

165

145.44

IC

IC

IC

Ge(Li)

10.32 ± 0.04

19.1 ± 0.6

23.5 ± 0.4

12.5 ± 0.3

scintillation 0.46 ± 0.03

spectrometer

4ttPC-Y

IC

IC

IC

4TTPC-Y

IC

88.75 ± 0.14

64.9 ± 0.2

45.9 ± 0.3

84. 7 ±0.6

79.95 ± 0.06

48.5 ± 0.4

27, 28 (PRP)

29 (PRP)

15

30 (PRP)

31

32 (PRP)

18 (PRP)

19 (PRP)

33

34

35

11
and the uncertainties are stated on the same basis as for Table I. Again, PRP in the Reference column indicates that the only available

account is in an AECL Physics Division Progress Report.

HALF-LIFE MEASUREMENTS WITH A 4 Try IONIZATION CHAMBER

A 4tty ionization chamber (IC) is the instrument that has been

used for most half-life measurements in this laboratory. Decay data

226 are taken relative to a Ra reference source in order to correct for

short-term fluctuations in the IC response. The decay usually is

followed for about ten half-lives. In computing the data, corrections

226 36) are made for Ra decay using a half- life value of 1600 ± 7 years

3 7 38

)

The ionization chamber is a TPA Mkll ' reentrant model

39) filled with twenty atmospheres of argon. A diagram of the chamber

and a discussion about the use of ionization chambers for high-precision

*. u • • i 39,40) measurements have been given in recent review articles

Table IV gives information about the contribution from various

sources of uncertainty toward the overall uncertainty given in Table I.

41) The experimental setup, described in an earlier report , allows

the charge built up on an integrating capacitor mounted across a vibrating reed electrometer to be read out with a digital voltmeter.

The standard deviation for a single observation is typically ±0.02 to

±0.04% for conditions of source strength and counting interval that are representative during the first few half-lives of a half-life measurement.

Systematic error from long-term instability of the response of the

ionization chamber has been investigated and found trivial. The same

41) ionization chamber was used m an earlier study , which showed no evidence of gas leakage during the 10- year period prior to 1967; our calibration data since that time confirm this finding and indicate that any

decrease in efficiency has been <0.1%. An example is the set of response

198 2 26 factors shown in Table III for Au calibrations versus a Ra reference

198 source. The Au activity was determined independently by the 4TT$-y

coincidence method. The statistical uncertainty since 1969 has been «0.03%,

but earlier measurements were less precise.

12
Table III

Ionization Chamber Response Factor

198 for Au over a Period of Time

Date IC Response

1978 - May 3.1940

1977 - Jan 3.1950

1974 - May 3.1947

1969 - Sept 3.1924

1966 - Sept 3.196

1966 - July 3.192

1965 3.188

1963 3.194

The source was a sample of solution sealed in an ampoule.

For most of the radionuclides studied these were glass ampoules,

95 233 but for hydrofluoric acid solutions (e.g. Nb and Pa) polyethylene

ampoules were used. The carrier solution is selected for stability and

42) usually is the same as that used for standards of radionuclides . No

evidence of solution instability has been observed and therefore no contribution to systematic error from it has been included. Nonreproducibility of the source position in the chamber contributes to the

statistical uncertainty in the half-life measurements. Tests with ^Co

41) have revealed that this effect is <^ 0.01% and arises largely from

41) anisotropy in the chamber response . The effect is greater for

lower energy y rays and correlates with the somewhat larger statistical

uncertainties in the half-life values of nuclides that emit only low

energy y rays.

13
9 9 f\ The Ra reference sources were obtained from Amersham Corporation

between 1964 and 1967. They are doubly encapsulated in iridium-platinum

14)

alloy. In 1972 the purity was investigated by Y~ray spectrometry to

22 8 assess the content of 6-year Ra. None was detected and a limit of

<0.01% was estimated at that time. Therefore, no correction was made for

2 28

Ra impurity when computing any of the half-lives reported here, but

the possibility of its presence contributes slightly to the systematic

uncertainty in some of the half-life values, as shown in Table IV. The

accuracy of the

226

Ra half-life (1600 ± 7 a) is sufficient to allow us

to neglect the effect of its uncertainty at this time, but if the decay

of some of the longer-lived samples is followed for many more years, this

miLght become significant. For example, it would contribute ~ ±0.02 d to

60

the uncertainty in the Co half-life value.

Saturation of the ionization chamber is another source of error

that has been investigated40^. Tests with a series of Co sources of

various activities have been done to demonstrate the source strength at

which saturation of the ion-current level gives a noticeable loss. Source

strengths have been selected to stay below this level and thus avoid

( the

difficulty.

Other systematic uncertainties in the measurements arise from

radioactive impurities in the source samples. For some radionuclides

chemical separations were performed prior to commencement of the measurement period, and these are indicated by CP in the first column of Table IV. The presence of impurities was investigated by two methods. One method was

the identification of impurities by y-ray spectrometry. If an impurity

was found, corrections were made to the decay data. The difference between

half-life values computed with and without these corrections was used to

deduce the systematic uncertainty caused by impurities. The other method

used to test for impurities was to divide the decay data into two or more sections, compute the half-life for each section separately, and examine

the results for a significant difference. The magnitude of the difference

found, if any, gave an indication of systematic uncertainty. Details

about the actual impurities found or suspected in specific radionuclides

are given in Appendix 1.

14
Table IV

Uncertainties in Half-Life Values Determined with

the 4tty Ionization Chamber

Radionuclide

7 Be CP*

18

F CP

22

Na CP

24

Na CP

46

Sc

51

Cr CP

54

Mn CP

5fkn

60,Co CP

64

85

Cu

Sr

95

Nb CP

99

Tcm

113

Sn

115

lnmCP

133

Xe SI*

133

Ba CP

Uncertainty in Half-Life Value from

2 26

(a) Statistical (1 a) (b) Purity of Ra (c) Impurities

Reference Source in Sample

134

Cs CP

0.004 d

0.013 min

0. 12 d

0.0005 h

0.011 d

0.003 d

0.017 d

0.0004 h

0. 77 d

0.001

0. 007

0.002

0.0007 h

0.032 d

0.005 h

0.0007 d

27. 1 d

0.26 d

nil

nil

0.1 d

nil

0.004 d

nil

0.01 d

nil

0.2 d

nil

0.002 d

nil

nil

0.005 d

nil

nil

0.1 d

0.04 d

nil

< 0. 01 min

0.11 d

nil

nil

nil

nil

<_ 0.0004 h

0.56 d

0.002 h

0.0005 d

0.018 d

± 0.003 h

0.10 d

0.005 h

0.0003 d

nil

nil

15
Table IV (Continued)

Uncertainty in Half -Life Value from

Radionuclide (a) Statistical (1 o) (b) Purity of

226

Ra (c)

Reference Source

Impurities

in Sample

13?

Cs CP 140.2 d 0.1 d nil

139^

Ce 0.024 d U . UU J d nil

i /. i 0.02 d nil 0.01 d

152

Eu 7.2 d 0.1 d 1.0 d

Yb 0.007 d nil 0.002 d

198 AAu 0.0002 d nil 0.0002 d

20 3UHg 0.005 d nil 0.002 d

233pPa 0.002 d nil nil

*CP indicates chemically purified; SI indicates separated isotope was irradiated to produce the radionuclide.

HALF-LIFE MEASUREMENTS WITH A 4tt PROPORTIONAL COUNTER

A 4tt proportional counter was used for most other half-life

measurements reported here. This instrument is less suitable than an ionization chamber because it is subject to many more sources of systematic

uncertainty. Chief among these are: 1) the dead time of the counting

system; 2) instability of the radioactive source over a prolonged period

of time; and 3) change in the voltage plateau.

Table V shows the contribution from individual sources of

uncertainty toward the overall uncertainty given in Table I.

The dead time of the counting system was measured with the two- source method or the source-pulser method, both of which have been

43) discussed by Taylor in a recent review . Typically, the dead time was 2 ys with a standard deviation of +0.12 ps for a single observation.

For the half-lives reported here the dead-time correction to the first

data point was <3%. To study the magnitude of uncertainty in the half16
life value from an erroneous dead-time value, the data from a run were corrected for a dead-time value different by one standard deviation; the

half-life was recomputed, and the difference in the half-life value was taken

as the systematic uncertainty contributed by dead time. This approach

gives an uncertainty estimate that is much lower than the maximum

conceivable limit of error, and seems consistent with the 68% confidence

level adopted here.

It is well-known that the thin sources required for 4tt counting

are susceptible to small gradual changes which affect the overall 4tt counting efficiency. One such change is in the source material itself.

An example is the sorption of water vapour, which frequently is encountered

with halides of rare earths, alkaline earths and alkali metals, and depending

upon circumstances, can change the self-absorption by ± 1% over a period of

several months.

Another type of change can occur in the metallic coating of the film

used as the source mount. A decrease in the electrical conductivity of the

film may alter the voltage plateau and hence the counting rates observed at

the selected counting voltages. For a typical plateau, with a slope of

~ 0.2% per 100 V, an effect of > 0.1% has been observed for sources of

long-lived nuclides over a period of a few months. It was impracticable

to make quantitative observations of this effect for the actual sources used

in the half-life determinations reported here because the counting

statistics were inadequate after the decay of several half-lives. Our only

estimate of the magnitude of this source of uncertainty is based upon our experience with longer-lived nuclides. The effect is trivial for shortlived nuclides.

Another source of systematic uncertainty has been considered and

found to be small. It is the effect from change in the counter response

that is not associated with the source material or source mount. We have

called this "instability of the counter" in Table V. It arises from

changes in the gain of the detector, such as those associated with source

17
3OU

4J

u c

•H CU c X c •H

fH 4-1

H X!

X

X •H e

•H

C e ro e X 3 rH rH '—s o <r CNI CNI CO O —i O o X> o o O m o O 4-1 <_> o o o < o o o o o O CO o o o C MH d o o d o 1—1 O V o o d d w cu CU 0) cu H 0) rH rH rH rH

CO

u

XX

cu •H

w •H

X

X •Hx

x •H •H 3 X) 3 60 60 60 rO 60

rH co

O •H rH rH •H rH •H

O •H

CO

n 4-1 CO rH

O

O rO rH o O rH

O rH > CU 0) 60 o o < 60 o O 60 o 60

4-1

C IW 0J 01 0) QJ

01

C i—i o C

d

d 2 c d o C o C >

0) rHXCD H

cO EC

CO

CU

CJU3O

CO

CO3O

•HM

CO >EOuc

•H

CO

4-J u

CU

CJ

iS

uoou

t=

4J•H3Xa

•HBH

CU

4-1 CD Q I X

COCU QH3

D-E

COU

-H

4-J CO •H

4J

CO c c X! c H

•H

X

x

xX •H

XB

B

X <f E

r-« <r o c^ <f rH i—i o o 00 o o o <r O o O o o m o o o o o o O o o o o o o o o o c

•HS

nooo ooo cHe

CNOo oo oo c X X c X •H H X X X •H B s X <r on £ on co en o <J rH o H

rH o o o o o o o o o o in o o o o o o o o o o o o o o o o

CU X

•HrH Pu CO Ph

CJ tO PU

U rH Ph rH CJ 3 Ph Pu CO CJ CO a CJ u o X B

B E

•H CO o •H

M XI c CO XI u P3 Ph rH CJ c

cfl oo <r CNI o CNI co -tf rH <r cO X 00 O

rH rH

rH rH rH

CU XI

CO 4-1 CU

CO

n

•H

•H j_j cu cw rj cx CO Q co o CU CU

4_l •H co

X o 4_l XJ

CO • H

Q rj •H ,—|

r; CU •H I i CU XI H CU

CU cO

g

4J 4J CU

cO co CU >

)_l pj cO

CO •H 1 1 CX

CU jr; CO

co o CJ C3

C4H *H o

CO r;

H

CU CO *> 4-1

4-1 CU CJ

cO 4J CU o CO o J-l • H co <H X1 rj o

rj CU XI CJ •H QJ Cu rj g CO 60

I—I •H o rj CO , :|

CJ

("J cM • A rr cu H

x) <— Cj 4J 1 i CU 1-1 <H *H r1 g m O rl

•H 03 CJ X co o r—|

cu

a CU

X CO •H

X 4-1 c 4J >\ 4J CU o C

rH

B •H •H rH at 4J CO • crj a CU >H 4J

CJ 3 CJ

O

M

•rH XI c a CU B o CU o a

0)

uX

u

X a. •H o. § a CJ o c t= MH

CO 4-1 •H •<r

O

CU

O

4J X) CJ X3 4-1 CO 01 c c

CJ 4J ?*- 1

CO 0) •H CO B

XI •H CO. CU CO c X) t= a CO •H CO <r 0) U 3 CO u >^ o CO •H CQ CO CO N ^ N

cfl X)

18
rate and the accumulation of a deposit on the counter wires over a period of time; these changes alter the voltage-plateau characteristics.

Although our normal practice in recording an individual half-life datum

is to average three observations taken at different voltages on the

plateau, a small shift in either the slope or the position of the plateau

might not be noticed and would bias the half-life value. In our judgment the limit of this shift gives ~ 0.2% in the relative counting

rate over the activity range and period usually followed. Assuming that

one-third of this limit is consistent with a confidence interval of

one, and taking into account the number of half-lives over which the decay was followed, the estimates listed in the last column of Table V were

deduced.

MEASUREMENT OF GAMMA-RAY EMISSION PROBABILITIES (P ) Y

Most of the P values listed in Table II were direct observations

Y

of the ratio of y-ray emission rate to activity. The counting methods

and instruments used were essentially the same as discussed in earlier

sections of this report. The accuracy, when applied to individual p

Y

measurements, is outlined in sections 6 and 7.

Determination of internal conversion data allowed P^ values to be

deduced for other radionuclides, namely ^Tcm

, "*"^Ce, "'""'"^In111 and ^"'lnm . 99 m 139 The data for Tc and Ce were determined with a method patterned on that published by Taylor for 203

Hg

45 ^ . The effect of variation in

efficiency of the 4tt(PC) upon 4TrPC-y coincidence results is analyzed to

derive the fraction of the Y-raY transitions that are internally converted,

usual techniques for efficiency variation (variation of self- and filmabsorption) were used here instead of the suspended foils described by

45) Taylor . Observations of the ratio, electron emission rate to "y-ray

emission rate, gave internal conversion coefficients for ^"^InTM and

115T m

In .

19
UNCERTAINTIES IN GAMMA-RAY MEASUREMENTS FOR P VALUES

• C

7

T> kl V Y65M- 113 T m 113 T m 137

Gamma-ray emission P rates for Be, K, Ni, In , In , Cs

141

and Ce were determined with the calibrated 47iy ionization chamber

(see section 3). Response versus energy curves, relative to the response

226

of the same Ra reference sources described in section 3, were determined

for three sample holders made from (1) 0.05-mm thick aluminum, (2) 0.4-mm

cadmium, and (3) 1.2-mm cadmium inside 0.12-mm tantalum. The 4ttB-Y coincidence method was used to calibrate samples of suitable radionuclides.

For data taken in recent years, the uncertainty in an individual calibration

point (the combined uncertainty in the coincidence counting and ion-chamber

44) 99 m

measurements) was typically ±0.3% . These data were for 140-keV Tc

139 203 198

Y rays, 165-keV Ce, 279-keV Hg, 411-keV Au, annihilation radiation

from 18

F, 514-keV 85

Sr, 766-keV 95

Nb, 835-keV 54

Mn, 889- and 1120-keV

46

Sc,

and 1173- and 1332-keV ^Co. The calibration data for the energy region

279 to 1332 keV were fitted to a second-order polynomial, and for the entire

energy range, to a third-order polynomial. To deduce the uncertainties in

the fitted calibration curves for the three sample holders, response data were compared for test y-ray energies, and the standard deviation among the

three results was taken as the uncertainty. Uncertainties in the calibration

are listed in Table VI. They are greatest for the low energy region and for

energies above 1.33 MeV. For example, the uncertainties in instrument

calibration in the cases of K and Ni are larger because the' response

curves had to be extrapolated beyond the highest energy calibration point.

42

A further contribution to the uncertainty for K is that at the time of

226 this P^ measurement, high-precision instrumentation and stable Ra

references were not yet available.

75 85 Gamma-ray emission rates for Se and Kr were obtained by

gamma- ray spectrometry with Ge(Li) and NaI(T£) detectors respectively. For

the 401-keV ^Se y ray, the most relevant energy calibration points were

^^ 8Au at 411 keV and ^Zn at 439 keV; the ^^Au data were obtained from

69 a 4TT3-Y coincidence standardization and the Zn from the calibrated ion

22

chamber. Na standardized by 4tt8-Y coincidence counting was used to

8 5 calibrate the NaI(T£) detector in the energy region of Kr; most of the

uncertainty shown for this calibration comes from uncertainty in the

31) source geometry used to simulate the Kr gas sample

20
Table VI

Breakdown of Uncertainty (%) in Values

Y-counting . Radionuclide Statistical Impurities Calibration Other

Curve

nil 0.16 0.18, 0.2

nil 2.5 0.5

nil 1.0 1.3, 0.2

nil 1.0 1.0, 1.0

nil 2.5 0.3, 0.3, 1.5

0.01 0.5 0.083

0.1 1.6 0.1, 0.2

* See text, page 21 - 22,

7Be 0.07

42

K 0. 2 65

Ni <0.1

"se 0.4

85

Kr 2.

A

137

Cs 0.15

141

Ce 0.05

UNCERTAINTIES IN ACTIVITY MEASUREMENTS FOR P VALUES

Y

The 4tt(PC)-Y coincidence method was used to determine the activity

, 7 D 27) 65...15) 75 c 30) 137^ 33) . 141„ 35) 42 29) , 85^ 31) of Be , Ni , Se , Cs and Ce ; K and Kr

activities were determined by 4tt proportional counting and internal gas

counting, respectively. For ^Be, the difference between results from two

different Y-cnannel gates was 0.18%, and uncertainty from spurious pulses

was estimated as + 0.2%. These are given in the last column of Table VI.

42

For K, the other uncertainty listed is the uncertainty in selfabsorption and source-mount absorption corrections.

The systematic uncertainty in 4tt3-Y coincidence counting ^^Ni was estimated as ± 0.2%. The other major source of uncertainty arises from

the correction to the ion chamber data for the response of other ^Ni

46)

Y rays, for which published values for relative gamma intensities were

used

.

21
The determination of the activity of Se by 4TT$-y coincidence

counting was complicated by uncertainties in the decay scheme. The

uncertainty in the correction for the decay to ^AsTM was taken to be

± 1.0%. In addition, the complexity of the decay scheme necessitated

higher-order polynomial fits to the efficiency data. Uncertainty here

was judged to contribute another ± 1.0%, by examining the differences

among results from two different ychannel gates and second- and thirdorder fits.

85

For Kr, the systematic uncertainties in internal gas counting were from wall effect (± 0.3%), uncertainty in counter volume (± 0.3%) and

slope of the differential voltage plateau (± 1.5%). The slope was 1% per

100 V for a 300 V long plateau, and the average counting rate along the

plateau was used as the result.

Sources of systematic uncertainty in an accurate measurement of the

137 activity of Cs determined by the 4tt(PC)-y efficiency-tracing method

1 3 33) with Cs as tracer have been reported in detail . They are from deadtime and resolving-time corrections (± 0.022%), decay-scheme corrections

134

(± 0.067%), sensitivity of the 4tt(PC) to y rays (± 0.024%), Cs

134 impurity (0.010%), and Cs decay corrections ( + 0.034%). Their combination in quadrature gives ± 0.083%.

141

The activity measurement of Ce was done with less attention to

35) minute details but has also been reported . Here the main sources of

systematic uncertainty were from dead-time and resolving-time corrections

(±0.1%), efficiency-dependent correction (±0.2%), and impurities of

46

Sc and 139Ce ( ± 0.1%).

UNCERTAINTIES IN P VALUES FOR "tcTM,

139

Ce,

113

Inm

and InTM

Y

We have not been able to break down the overall uncertainty value

99 m 32") given for Tc ' into its components. It was stated that the uncertainty

consisted principally of allowances for various sources of possible

systematic error. The final result was the mean value from five runs,

22
99 m which came from three different preparations of Tc ; thus it seems unlikely that impurities contributed significantly to the overall

uncertainty.

For

^ 3 ^Ce, other measurements^^ have been made from time to time since

34) the first determination in 1962 , and these have been in good agreement.

The statistical uncertainty, though not always the same, has been unimportant compared with other sources of uncertainty. Typically these were from

non-detection of conversion electrons in the 4tt(PC) (± 0.1%), uncertainty

in the correction for the sensitivity of the 4tt(PC) to y rays (± 0.1%),

uncertainty in other instrumental corrections for dead time and resolving

time (± 0.15%), and uncertainty in extrapolation of the efficiency function

(±0.2%). They are listed in Table VII.

Table VII

Breakdown of Uncertainty (%) in a^, Values

t Radionuclide Statistical Impurities Other

139

Ce 0.09 nil 0.1, 0.1, 0.15, 0.2

InTM 0.08 nil 0.15, 0.1, 0.4, 0.1, 0.1

115

Inm

0.23 .03 0.15, 0.1, 1.6, 0.6, 0.1

* ,P = l/(l+a^,), where is total internal conversion coefficient.

+ See text, page 23 - 24.

The electron emission rate from sources of "'""'"^In

111 was determined

by 4tt(PC) counting. Uncertainties in it were from the slope of the

plateau (± 0.15%), and from the correction for sensitivity of the 4tt(PC)

to y rays, E

ft (± 0.1%). Systematic uncertainty in the correction for

dead-time was considered negligible because results for different counting

rates were consistent. The Y _ray emission rate was determined for other

samples of 113

Inm with the 4tt ionization chamber, by using the three sample

23
holders. The uncertainty in calibration of the ionization chamber was

taken as the standard deviation in the results from the three holders

(+ 0.4%). The uncertainty in the y-ray energy was estimated to affect

the results by + 0.1%. Corrections for Bremsstrahlung contributed another

± 0.1% uncertainty.

Similar measurements were made to get electron and y-ray emission

r 115 T m _,, , c . - rates for In . The result of the experiment was a set of conversioncoefficient data. The same uncertainties were assigned for the 4tt(PC) counting

(± 0.15% for plateau and + 0.1% for e ). A correction was necessary for

115 m

the contribution to the 4tt(PC) rate from In 3 rays. At the time of the

measurement this was estimated as 6 + 1 % but it seems likely this was

48) in error. A recent evaluation gives 3.7+0.8% , and its uncertainty

contributes + 1.6% to a^. (This branching ratio gives = 1.096.) However,

it can be shown that P is unaffected by the 3-branching ratio. The

Y

experimental data revealed that the 4tt(PC) counting rate, N^, was equal

to 1.1768 times the y-ray emission rate, N . Thus we have

N, = 1.1768 N

4u y

But N . = N 0 + N + N e.

4it 3 e y 4tt,y

and N = N. + N

o 4tt y

where ND is the counting rate from the 3 - branch,

p N

g is the counting rate from conversion electrons, and

is the very small efficiency of the 4tt(PC) counter for 336 -keV y rays

(-0.1%). Since

P = N /N

y y o it is unaffected by the relative contributions from 3 particles and

conversion electrons to the 4tt counting rate.

The uncertainty in calibration of the ionization chamber for

115, m , , j. 113.,. m , , , , In y rays, by the same criterion as for In , was deduced to be

± 0.6%. Bremsstrahlung was estimated as ± 0.1% and uncertainty in

the y-ray energy was considered negligible.

24
9. ACKNOWLEDGEMENTS

This summary includes experimental data accumulated in this

laboratory over a long period of time by the authors and many other

workers. In particular, valuable contributions were made by

J.G.V. Taylor; others who contributed were P.J. Campion, S.C. Misra,

B . A. Risto, E.A. Ouelette, G. Frketich and F.H. Gibson. Their

careful records and reports made this summary possible.

25
REFERENCES

1. D.D. Hoppes, U.S. National Bureau of Standards, private communication

(1979).

2. S. Wagner, Physikalisch-Technische Bundesanstal t , report "How to Treat Systematic Errors in Order to State the Uncertainty of a Measurement", (1969).

3. J.W. Miiller, Nucl. Instr. & Methods _163, 241 (1979).

4. J.S. Merritt and J.G.V. Taylor, Atomic Energy of Canada Limited,

Report AECL-3668, p 50 (19 70).

5. J.S. Merritt and J.G.V. Taylor, Atomic Energy of Canada Limited,

Report AECL-4708, p 20 (1974).

6. A.R. Rutledge and J.S. Merritt, Atomic Energy of Canada Limited,

Report AECL-6788, p 45 (19 80).

7. J.S. Merritt and J.G.V. Taylor, Atomic Energy of Canada Limited,

Report AECL-3912, p 43 (1971).

8. P.J. Campion and J.S. Merritt, Can. J. Phys. 36, 983 (1958).

9. J.S. Merritt and J.G.V. Taylor, Can. J. Phys. 40, 1044 (1962).

10. A.R. Rutledge and J.S. Merritt, Atomic Energy of Canada Limited

Report AECL-6788, p 45 (19 80).

11. J.S. Merritt, A.R. Rutledge, L.V. Smith and F.H. Gibson, Atomic

Energy of Canada Limited, Report AECL-6530, p 44 (1979).

12. J.S. Merritt and J.G.V. Taylor, Atomic Energy of Canada Limited,

Report AECL-3333, p 32 (1969).

13. J.S. Merritt and A.R. Rutledge, Atomic Energy of Canada Limited,

Report AECL-6788, p 46 (1980).

14. J.S. Merritt and J.F.V. Taylor, Atomic Energy of Canada Limited,

Report AECL-4257, p 25 (1972).

15. J.S. Merritt and J.G.V. Taylor, Int. J. App. Rad. and Isotopes,

22, 783 (1971).

16. J.S. Merritt and F.H. Gibson, Atomic Energy of Canada Limited,

Report AECL-5315, p 37 (197 6).

17. J.S. Merritt and F.H. Gibson, Atomic Energy of Canada Limited,

Report AECL-6083, p 38 (1978).

26
18. S.C. Misra ? J,S. Merritt and J.G.V, Taylor, Atomic Energy

of Canada Limited,, Report AECL^-2256, p 23 (1965),

19. S.C. Misra and J.S. Merritt, Atomic Energy of Canada Limited,

Report AECL-2044, p 31 (1964),

20. J.S. Merritt, F.H. Gibson and J.G.V. Taylor, Atomic Energy of

Canada Limited, Report AECL-5032, p 34 (1975).

21. J.S. Merritt and J.G.V. Taylor, Atomic Energy of Canada Limited,

Report AECL-4205, p 21 (1972).

22. J.S. Merritt and J.G.V. Taylor, Anal. Chem. 37_, 351

(1965).

23. J.S. Merritt, J.G.V. Taylor and F.H. Gibson, Atomic Energy of

Canada Limited, Report AECL-5546, p 32 (1976).

24. J.S. Merritt and F.H. Gibson, Atomic Energy of Canada Limited,

Report-5032, p 35 (1975) .

25. J.S. Merritt and F.H. Gibson, Atomic Energy of Canada Limited,

Report AECL-5802, p 43 (1977).

26. A.R. Rutledge and J.S. Merritt, Atomic Energy of Canada Limited,

Report AECL-6582, p 40 (1979).

27. J.G.V. Taylor and J.S. Merritt, Can. J. Phys. 40, 926 (1962).

28. J.G.V. Taylor and J.S. Merritt, Atomic Energy of Canada Limited,

Report AECL-3512, p 29 (1969).

29. J.S. Merritt and J.G.V. Taylor, Atomic Energy of Canada Limited,

Report AECL-1142, p 25 (1960).

30. J.S. Merritt and J.G.V. Taylor, Atomic Energy of Canada Limited,

Report AECL-3666, p 46 (19 7-0).

31. K.W. Geiger, J.S, Merritt and J.G.V. Taylor, Nucleonics 19_, 97 (1961).

32. J.G.V. Taylor and J.S. Merritt, Atomic Energy of Canada Limited,

Report AECL-3157, p 30 (1968).

33. J.S. Merritt and F.H. Gibson, Atomic Energy of Canada Limited,

Report AECL-6203 (1978).

34. J.G.V. Taylor and J.S. Merritt , Bull . Am. Phys. Soc. ]_, 352 (1962)

35. J.S. Merritt and F.H. Gibson, Atomic Energy of Canada Limited,

Report AECL-5909 (ICRM-LS-1) (1977).

27
36. Nuclear Data Sheets, Vol. 20 No. 2, p 127 (1977).

37. J. Sharpe and F. Wade, AERE E/R 806 (1951).

38. H. Carmichael, Atomic Energy of Canada Limited, Report AECL-293

(1946)

39. National Council on Radiation Protection and Measurements,

NCRP-58, p 189 (1979).

40. H.M. Weiss, Nucl. Instr. & Meth. 112, 291 (1973).

41. J.S. Merritt and J.G.V. Taylor, Atomic Energy of Canada Limited,

Report AECL-2679 (1967).

42. National Council on Radiation Protection and Measurements,

NCRP-58, p 198 (1979)

43. National Council on Radiation Protection and Measurements,

NCRP-58, p 61 (1979).

44. F.H. Gibson, L.V. Smith, A.R. Rutledge and J.S. Merritt, Atomic

Energy of Canada Limited, Report AECL-5562 (1979).

45. J.G.V. Taylor, Can. J. Phys. 40,383 (1962).

46. J.E. Cline and R.L. Heath, Phys. Rev. 131 , 296 (1963).

47. A. Rytz, Bureau International des Poids et Mesures, BIPM-77/4 (1977).

48. Nucl. Data Sheets 16, 216 (1975).

23
APPENDIX 1

IMPURITIES FOUND OR SUSPECTED IN SAMPLES OF RADIONUCLIDES

3 24 38 Chemical separation removed H and traces of Na, CI and

198 187

Au. The only residual activity was W which was detected

in all 7 preparations. The impurity varied between 0.002 and

0.015% at the start of a run. Its effect on the half-life

value from the Att(PC) results was 0.015 min but was negligible

for the ionization chamber results.

42 Chemical separation effectively removed K.

24 Chemical separation effectively removed Na.

65 Possibly a small impurity of 2.5-h Ni. This would have a negligible effect on the result because the half-lives are nearly equal.

Gamma-ray spectrometry detected no impurities. ~^Mn is the

56

most suspected impurity; 0.2% Mn would cause an error of

0.004 h in the

64

Cu half-life.

24

An impurity of 0.03% Na was typical at the start of a run.

Impurities of

5?

Co (0.61%),

65

Zn (0.12%) and

133

Ba (0.24%) were estimated at the end of the measurement period. Corrections

-4

for these amounted to 3. 7 x 10 % at the beginning and

0.9% at the end of the measurement period. If the impurities

are not taken into account, the half-life value would be in error by 0.001 day.

29
9 5 An impurity of Zr was detected. The correction for it was

0.1% at the start and 10% at the end of the period followed.

95

If the Nb half-life is computed without making a correction

95 for the presence of Zr, the result is longer by 0.09 d. It

is assumed that the accuracy of the correction is ± 20% of

this 0.09-d difference.

For the sample used for the half-life measurement, an impurity

99

of Mo was detected. This was 0.1% at the beginning and 90%

at the end of the measurement period.

Different samples were used for the measurement. Specific

information about their purity is not available.

113 Impurities of Sn were present in most samples, and the amounts

varied between 0 . 001 and 0 . 003% at the start of the measurement period

. . _ 12501_ 60„ , 114 m . L 125 OL Impurities of Sb, Co and In were detected, with Sb

predominant. The total correction at the start of the run

was 0. 76% and at the end it was 50%.

115T m .. , , , . . _ 11A„ , In samples were prepared by neutron irradiation of Cd,

followed by a 1-day waiting period, before chemical separation.

The 1-day waiting period reduces the content of In impurity.

No long-lived impurities were detected, and it is estimated

that short-lived impurities were < 0.005% at the start of a run.

An impurity of "^"Sce

111 was detected. This was 0.009% at the

start and 2% at the end of the run. If the correction for

this impurity is not made, the half-life value would be longer

by 0.0006 day.

30
134 m . . , 24 J 134„

Cs - Impurities or Na and Cs were detected; these were ~ 0.5%

at the start of a run.

137 1 3

A

Cs - An impurity of 0.03± 0.01% Cs was present.

"'"^Ba

111 - An impurity of "'^Cs was present (0.003 % at the start).

Ce - Impurities of Ce, Eu and Eu were present in the

sample used for the half-life measurement. The correction for

these was 0.04% at the beginning and 0.23% at the end of the

measurement period.

139 46 Impurities of Ce (0.11%) and Sc (0.01%) were present in

the sample used for P determination.

Y

^"^Eu - An impurity of "*"^Eu (~ 0.5%) was detected.

^"^Yb - An impurity of "'"^Tm was detected. This was 0.01% at the start

of the run and 7.3% at the end. If the correction is neglected,

the half-life value would be 0.010 day longer.

198

Au - It was calculated that the irradiation which produced this

199 material should have produced 0.02% Au. The effect of this

198 on the Au half-life value is 0.0001 day. Two separate

irradiations gave values that differed by 0.0004 day.

203„ _ . . , 60„ . 110. m , , Hg - Impurities of Co and Ag were detected. These were

< 0.01% at the beginning and 3.6% at the end of the run.

31
Bureau I international des Poids & Mesures

Sevres, France

A. Rytz

The half lives reported by BIPM consist of the following:

a) Published measurements

A. Rytz, J.W. Muller and C. Veyradier, Mesures de periodes radioactives,

Comite International des Poids et Mesures, Proces-Verbaux 2 e serie, 62 e session, 41, 68 (1973)

54 Mn T1/2 = (312.19 + 0.13) d 38 mesures, duree 2.22 T 1/2

60Co T 1/2 = (46195 + 24) h 24 "

" 1.11 T 1/2

ibid. 2 e serie, 63e session, 42, 64 (1974)

54 Mn T 1/2 = (312.15 + 0.23) d 3 T 1/2

(random 0.17, systematic 0.2)

b) Unpublished result

14 electrolytical deposits (Feb. 1974) of ^Co were measured four times

a year by 4pi beta(PC)-gamma counting. The results showed a considerable

dependence on the coincidence formula used, due to incomplete compensation

for losses at high rates with the Campion formulation.

Date of last ^l/2» Campion formula T\/2> Cox-Isham formula

measurement used

Jan 1976 46 170 h Nov 1976 46 129

Feb 1977 46 124

Oct/Nov 1977 46 132 (11) 46 213 (8)

Jul 1978 46 212 (6)

Oct 1978 (0.88 T 1/2 ) 46 212 (6) = (1925.5 + 0.3)

days

best value

32
CBNM/RN/15/81

1 July 1931

CENTRAL BUREAU OF NUCLEAR MEASUREMENTS

DECAY DATA MEASURED AT CBNM SINCE 1968

compiled by W. BAMBYNEK

The following list contains half-lives, 7-rays and KX-ray emission probabilities measured at CBNM since 1968. Only radiations with a probability

greater than 5% per decay are included. The uncertainty statements have

the following meaning :

st(f,o) 1 + - s 5

1 a corresponds to

^

st(f,3<r)

3 a corresponds to +26

where s = standard deviation of the single result

t(f,o) = student-t deviate for the number of deqrees of freedom f and

the chosen confidence level a

n = number of independent results

5.. = (residual) component systematic uncertainty which is an estimated

limit of the uncertainty that remains after the correction of the

results for the systematic effect.

57

Co T 1/2

= 271.90 + 0.09 days 1 a

R. Vaninbroukx, G. Grosse, W. Zehner

Int. J. Appl .Radiat. Isotopes, in press

58

Co T 17 „ = 70.81 + 0.10 days 3 a

60

Co

1/2

both see :

R. Vaninbroukx, G.. Grosse

Int. J. Appl. Radiat. Isotopes 27, 727 (1976)

33
65

Zn Tj

2

= 244.0 + 0.2 days 1 a

P (1115) = 0.5075 + 0.0010 1 a

E. De Roost, E. Funck, A. Spernol , R. Vaninbroukx

Z.Physik 250, 395 (1972)

93

Nbm

T

1/2

= 16.0+0.8 years 1 a

D. Reher, R. Vaninbroukx

CEC - JRC, CBNM, Nuclear Measurements, Programme Progress Report,

January - June 1981

= 0.116 + 0.004 1 a

W. Bambynek, D. Reher, R. Vaninbroukx

Proc. Int.Conf . on Neutron Physics and Nuclear Data for

Reactor and Other Applied Purposes

Harwell, Sept. 1978 (OECD Nucl . Energy Agency, Paris 1978), p. 778

95

Zr T

l/2 = 64.05 + 0.06 days 3 a

95

Nb T

1/2

= 34.97 + 0.03 days 3 a both see : H.H. Hansen, G. Grosse, D. Mouchel , R. Vaninbroukx

Z.Physik A 278, 317 (1976)

103

Ru T 1 /0 = 39.260 + 0.020 days 1 a 1/2

R. Vaninbroukx, G. Grosse, W. Zehner

Int. J. Appl .Radiat. Isotopes, in press

103

Rhm

T

1/2

= 56.114 + 0.020 min. 1 a

R. Vaninbroukx, G. Grosse, W. Zehner

Int. J. Appl .Radiat. Isotopes, in press

P KX = 0.0843 + 0.0013 1 a

R. Vaninbroukx, W. Zehner

Int. J. Appl. Radiat. Isotopes, in press

34
103Pd T

1/2

= 16.991 + 0.019 days 1 a

R. Vaninbroukx, G. Grosse, W. Zehner

Int. J. Appl .Radiat. Isotopes, in press

109

Cd T

1/2

= 461.90 + 0.30 days 1 a

R. Vaninbroukx, G. Grosse, W. Zehner

Int. J. Appl .Radiat. Isotopes, in press

113

Inm

T, ,„ = 99.47 + 0.07 rain. 1 o 1/2

H.H. Hansen, E. De Roost, D. Mouchel, R. Vaninbroukx

Int. J. Appl .Radiat. Isotopes 22, 1 (1971)

115

InmT

1/2

= 4.436 + 0.004 hours 1 a

Py

(336) = 0.459 + 0.001 1 a H.H. Hansen, E. De Roost, W. van der Eijk, R. Vaninbroukx

Z.Physik 269, 155 (1974)

137

Cs P (662)= 0.851 + 0.004 la

PKX

/P

7 = 0.0813 + 0.0010 1 a H.H. Hansen, G. Lowenthal, A. Spernol , W. van der Eijk,

R. Vaninbroukx

Z.Physik 215, 25 (1969)

139

Ce T

1/2

= 137.66 +0.13 days 3 a

R. Vaninbroukx, G. Grosse

Int. J. Appl. Radiat. Isotopes 27, 727 (1976)

141

Ce T

1/2

= 32.50 + 0.04 days 3 a

R. Vaninbroukx, G. Grosse

Int. J. Appl. Radiat. Isotopes 27, 727 (1976)

P (145)= 0.482 + 0.003 1 a

P KX= 0.168 + 0.0Q2 l a H.H. Hansen, E. Celen, G. Grosse, D. Mouchel, A.Nylandsted Larsen

Z.Physik A 290, 113 (1979)

35
196

Au T

1/2

= 6.13+0.02 days 1 a

R. Vaninbroukx

Progress Report on Nuclear Data Research in the European

Community, 1973 NEANDC(E)161"U" , page 219 (1974)

204

T1 T

1/2

= 3.774 + 0.005 years 1 a

G. Bortels

Int.J.Appl .Radiat. Isotopes 20, 612 (1969)

231

Th P (25.65) = 0.145 + 0.003 la

7

V

' ~

Py

(84.16) = 0.066 + 0.003 1 a

R. Vaninbroukx, B. Denecke

Proceedings of the 5th Symposium on X- and Gamma-Ray Sources

and Applications, Ann Arbor, June 10-12, 1981

Nucl .Instr. Methods, in press

233

U T

1/2

= (1.5925 + 0.0040)105 years 3 a

R. Vaninbroukx, P. De Bievre, Y. Le Duigou, A. Spernol

,

W. van oer Eijk, V. Verdingh

Phys. Rev. C _13, 315 (1976)

234

(J T

1/2

= (2.446 + 0.007)105 years 3 a

P. De Bievre, K.F. Lauer, Y. Le Duigou, H. Moret,

G. MUschenborn, J. Spaepen, A. Spernol, R. Vaninbroukx.

V. Verdingh

in M.L. Hurrell (ed.) Chemical Nuclear Data

(The British Nuclear Energy Soc, London, 1971) p. 221

py

(143.8) = 0.109 + 0 .002 1 a

PT

(163.4) = 0.050 + 0 .001 1 0

P7

(185.7) = 0.575 + 0 .009 1 a

PJ

(205.3) = 0.050 + 0 .002 1 o

R. Vaninbroukx, B. Denecke

Proceedings of the 5th Symposium on X- and Gamma-Ray Sources

and Applications, Ann Arbor, June 10-12, 1981

Nucl. Instr. Methods, in press

36
238

Pu P, v = 0.1141 + 0.0034 lo

LX

R. Vaninbroukx

INDC(NDS)-105/N (1979) p. 45

239

Pu T

1/2

= (2.4100 + 0.0030)10

4

years lo

R. Vaninbroukx

INDC(NDS)-105/N (1979), p. 45

241

Pu T1/5 = 14.60 + 0.10 years lo

' " 241

by Am ingrowth

14.30 + 0.14 years lo

by mass spectrometry

T

1/2 (°) = (6.04 + 0.05)10 5 years lo

R. Vaninbroukx >

in: Neutron Physics and Nuclear Data for Reactor and Other

Applied Purposes, Harwell, Sept. 1978 (0ECD Nuclear Energy

Agency, Paris, 1978) p. 235

37
Georgia Institute of Technology

School of Chemistry

Atlanta, Georgia, USA

R.W. Fink

Several reprints were supplied concerning the measurement of the ratio of x-ray

components for diferent atomic numbers. These data, while pertinent to the cali

bration of spectrometers at low energy, were considered as best reserved for

separate consideration by the SG at a later time. However, an article by W.D.

Schmidt-Ott and R.W. Fink published in Z. Physik 249 , 286 (1972) gives P

R data

for Professor Fink notes that the ICRM intercornparison results for that

radionuclide should also be of interest for the present compilation.

38
PRECISION MEASUREMENTS OF GAMMA-RAY INTENSITIES

52 Mn, 56 Co, 88 Y, 90 Nb, llomAg, 12 *Sb, 133 Ba

131t Cs, 152 Eu, 154 Eu, 192 Ir, 198 Au and 20 7 Bi

Yasukazu Yoshizawa, Yosei Iwata

Department of Physics, Faculty of Science

Hiroshima University, Hiroshima, Japan

Toshio Katoh

Department of Nuclear Engineering, Faculty of Engineering

Nagoya University, Nagoya, Japan

Jian-Zhi Ruan, Toshiyuki Kojima

Department of Physics, Faculty of Science

Rikkyo University, Tokyo, Japan

and

Yasushi Kawada

Electrotechnical Laboratory, Tsukuba, Ibaragi, Japan

Abstract

Relative intensities of gamma rays from thirteen nuclides were measured

with Ge(Li) detectors in the region from 280 to 2750 keV. The detectors

were calibrated with standard sources specially prepared and cascade

gamma-ray sources. The relative intensities were determined within accuracies

of about 0.5 %. Intensities per decays were obtained from the relative

intensities and internal conversion coefficients for most of the nuclides.

39
Precision measurements of gamma-ray intensities have been requested for

the non -destructive nuclear fuel investigation. Recently Debertin et al. , Gehrke et al . ^ and Meyer ^ have performed precision measurements of relative

intensities. Purpose of our experiments is to determine relative gamma-ray

intensities of various nuclides with errors less than 1 % in the energy region

28CK2750 keV. Standard sources were prepared at Electrotechnical Laboratory

in Tokyo, and gamma-ray measurements were performed at Hiroshima University and

Nagoya University.

Calibration sources. Standard sources were made from eight nuclides 22 Na,

" 6 Sc, 5 "Mn, 60 Co, 85 Sr, 88 Y, 13t*Cs and 2 0 3 Hg, and cascade gamma-ray sources were from four nuclides 2I*Na, 52 Mn, 90 Nb and 108m

Ag. These calibration sources

are listed in Table 1. Ten standard sources were made for each nuclide, and

cascade gamma-ray sources of 1%4 were also made. All the samples of about

1 yCi were mounted on plastic capsules. The standard sources were made from

solution (2Ov30 yCi/g) , and density of solution was determined by means of the

4tt3~y or 4itX-y coincidence method. Four parts of solution were diluted by 3^4

times and about 10 samples were made from each diluted solution. These samples

were measured with the coincidence system of a box type 4tt counter and two

3"x3" Nal(Tl) detectors at Electrotechnical Laboratory.

Evaluated values of intensities per decays for the calibration sources are listed in Table 1. These values were obtained from decay schemes, internal

8 9) conversion coefficients and relative intensities of weak gamma rays

'

Most of these gamma rays are more than 99 % per decay, and others are more than

80 %.

Gamma-ray measurements. In Hiroshima and also in Nagoya, measurements were performed with Ge(Li) spectrometers. The distance from the detector case to

the source was always 20 cm. The detector was shielded by lead in Nagoya, and

most of the measurements were done without shield in Hiroshima.

Following points were taken care of for measurements:

a) Absorption effect. Absorption of the plastic cover of the source capsule is about 0.8 % for 279 keV gamma rays and covers of the detectors are thicker. But the same capsules were used for gamma-ray sources and the measurements were done under the same condition.

b) Source position effect. In our efficiency measurements four sources

40
(three for one case) were used at the same time. Sources were placed at 3 cm

(Hiroshima) or 2 cm (Nagoya) from the detector axis on a plastic plate which

was at 20 cm from the surface of the detector case. Really counting rates were different for source positions on the plate. Since the source positions were changed by cyclic order, this effect was canceled in our measurements.

c) Source to detector distance. Accuracy of the distance is within 0.2 mm,

and ambiguity of the average position of source material in the capsule is also

within 0.2 mm. Therefore, the error of the counting rate originated from the

ambiguity of the distance is within 0.2 %.

d) Dead time and counting loss. To compensate this effect, four sources

were measured at the same time. Two or three common gamma rays were measured

for different energy range. Integrated peak counts were normalized by integrated

peak counts of these common gamma rays. This effect is negligible (<0.3 %)

The detector efficiencies were measured by using 12 kinds of the calibration

sources in Hiroshima and by 9 kinds of ones in Nagoya. For each measurement

four sources (three for some cases) were placed at four source positions.

Spectra were taken three times in Hiroshima and once in Nagoya in the same condition. The sources were changed by cyclic order for four positions and five

standard sources were used for each nuclide. Therefore, measurements of one kind of spectrum were 60 times in Hiroshima and 20 times in Nagoya. Total

integrated peak counts were about 6xl0 6 in Hiroshima and 2xl0 6 in Nagoya.

Relative gamma-ray intensities of 88 Y and 207 Bi were measured in Hiroshima

and Nagoya, and others were in Hiroshima. Gamma-ray spectra were analyzed by

PDP 11/05 in Hiroshima and spectra taken in Nagoya were by a computer FACOM 230-25

at Rikkyo University. Data analyses were performed as follows:

a) Background subtraction. First, several gamma-ray peaks with low background were measured and ratios of tail heights to the peak height were

determined. Background subtraction was done by a straight line or a quadratic

curve and the shape of the response function was reproduced.

b) Subtraction of close-lying peak. Weaker gamma-ray peak was subtracted

by using the shape of a stronger close-lying gamma-ray peak.

c) Integration of peak area. After background subtraction, channel counts

higher than 1/50 of the peak center counts were integrated. The, peak center

counts were determined by Gaussian fitting.

d) Sum effect. Though the source to detector distance was 20 cm, the sum

effect was not negligibly small. To correct this effect, the spectra of single

41
gamma rays of

5I*Mn, 85 Sr and 20 3 Hg were measured and total efficiencies were

obtained. The sum effect of cascade gamma rays was corrected for the cross over gamma rays. In addition, the sum effect with X rays was tested. For

108m

Ag the sum peak with the X rays was not observed at the source to detector distance of

20 cm, but the sum peak was observed at about 1 cm. For

1

3

3 Ba the sum peak with

the X rays was observed at 20 cm. Therefore the correction is necessary to

heavier elements.

Efficiency curves. Ratios of efficiencies in Hiroshima to those in Nagoya

are almost constant except 203Hg. Many efficiency curves were examined.

However these curves are not satisfactory for precision measurement. Curves

given by exponential functions were also examined. The final efficiency curves were determined with the errors of less than 0.5 %.

Experimental results. Experimental results of relative intensity measurements

for 88Y and 207Bi in Hiroshima agree with those in Nagoya within experimental

errors. The average values are obtained from the weighted mean, where the

weights are given by the number of measurements. In addition, relative intensities of 52Mn, 56 Co,

90Nb, llom

Ag,

12 "Sb, 133

Ba,

13 "Cs,

152

Eu,

15ltEuand 192

Ir were measured in Hiroshima. All experimental results are listed in Table 2.

Intensity balances between feeding transitions and outgoing transitions

were calculated for five levels, in order to examine reliability of our measurements. The largest deviation is 0.6 % and the average is 0.32 %. Therefore our errors are reasonable. Our results are compared with previous measurements.

Deviations are seen at 1038 keV and 2599 keV in

56

Co, at 1038 keV in

131

*Cs and

at 411 keV and 1086 keV in 152Eu. However, our results agree with the most of

values of Debertin et al . and Gehrke et al . within their experimental errors. Gamma-ray intensities per decays are evaluated from our results of relative

intensities and internal conversion coefficients by using the well established

decay schemes. These values are shown in Table 2. In conclusion we succeeded

in determining relative intensities with errors of about 0.5% for strong gamma

10M21

rays. Most of our results shown here will be published

42
Re ferences

1) U. SchBtzig, K. Debertin and H. M. Weiss, PTB-Mitteilungen 83 (1973) 307

2) K. Debertin, U. SchBtzig, K. F. Walz and H. M. Weiss, Ann. Nucl . Energy 2 (1974) 37

3) K. Debertin, U. SchBtzig and H. M. Weiss, PTB-Mitteilungen 85 (1975) 187

4) K. Debertin, U. SchBtzig and K. F. Walz, PTB-Jahresberich (1976) 160

5) U. SchBtzig, K. Debertin and K. F. Walz, Int. J. Appl. Rad. Isotopes 28

(1977) 503

6) R. J. Gehrke, R. G. Helmer and R. C. Greenwood, Nucl. Inst. Meth. 147 (1977)

405

7) R. A. Meyer in Table of Isotopes, 7th edition, Appendices compiled by

C. M. Lederer et al . (1978); Lawrence Livermore Laboratory (1978) M-100

8) Y. Yoshizawa, H. Inoue , M. Hoshi, K. Shizuma and Y. Iwata, Japan Atomic

Energy Research Institute JAERI-M7567 (1978)

9) Y. Yoshizawa, H. Inoue, M. Hoshi, K. Shizuma and Y. Iwata, Japan Atomic

Energy Research Institute JAERI-M8811 (1980)

10) Y. Yoshizawa, Y. Iwata, T. Kaku, T. Katoh, J. Ruan, T. Kojima and Y. Kawada,

Nucl. Inst. Meth. 174 (1980) 109

11) Y. Yoshizawa, Y. Iwata and Y. Iinuma, Nucl. Inst. Meth. 174 (1980) 133

12) Y. Iwata and Y. Yoshizawa, Nucl. Inst. Meth. to be published

43
TABLE 1

Evaluated values of calibration gamma rays.

Gamma-ray Intensity

Nuclide Half-life energy per decay Remarks

(keV) (%)

2U Na 14 .987±0.020 h 2754.0

1368.6

99.881

99.994

±0

±0

.008

.003

c

,0 Nb 14 .6 h 2319.1

1129.1

81.81

94.22

±0

±0

.08

.09

c

8 8y 106 .61 ±0.21 d 1836.1 99.24 ±0 .07 s

52 Mn 5 .67 d 1434.3

935.5

99.9871±0

94.89 ±0

.0014

.03

c

60 Co 5 .272±0.002 y 1332.5

1173.2

99.9816±0

99.89 ±0

.0015

.02

s

22 Na 2 .603+0.004 y 1274.5 99.94 ±0 .02 s

- 6 Sc 84 .34 ±0.13 d 1120.5

889.3

99.9871±0

99.9836±0

.0012

.0016

s

5U Mn 312 .16 ±0.11 d 834.8 99.9746 ±0 .0025 s

13 *Cs 2 .061±0.005 y 795.8

604.7

85.51

97.64

±0

±0

.05

.06

s

ioemAg 127 ±21 y 722.9

614.3

434.0

99 .7

100.00

99 .48

±0

±0

±0

4 b)

03 b)

09 b)

c

65 Sr 64 .68 ±0.24 d 514.0 98.4 ±0 .4 s

2 0 3 Hg 46 .60 ±0.02 d 279.2 81.48 ±0 .08 s

a) Symbols c and s indicate cascade gamma-ray sources and standard

sources, respectively.

b) Relative intensity.

44
TABLE 2 Relative intensities and intensities per decays of gamma rays.

Gamma ray

Nuclide

Energy Relative intensity Intensity per decay

(keV) (%) (%)

346 .0 1.032 ±0.026 1.032 ±0 .026

398.1 0.088 ±0 .011 0.088 ±0.011

399 .6 0 .170 ±0.017 0.170 ±0 .017

502.1 0.218 ±0.026 0.218 ±0 .026

600 .1 0.387 ±0 .026 0.387 ±0.026

647 5 0 . 43 ±0.03 0.43 ±0 .03

744.2 90 '.8 ±0.3 90.35 ±0.07

848.2 3.39 ±0.03 3.39 ±0.03

935.5 95.0 ±0.3 94.89 ±0 .03

1246 .2 4.32 ±0.09 4.32 ±0.09

1 2 4 7 8 0 37 ±0.09 0.37 ±0 .09

1333.6 5.07 ±o!<)3 5.07 ±0.04

1434.1 100 .0 ±0.3 99 .9871±0 .0014

1645.8 0 .056 ±0.004 0.056 ±0.004

1981.1 0 .036 ±0.003 0 .036 ±0 .004

HOD i J \J . \J u X + 0 010 0 .061 ±0.010

733 .6 0 . 193 ±0 . 012 0.193 ±0.012

787.8 0 .305 ±0.013 0.305 ±0.013

846 .8 100 .0 ±0.3 99 . 920 ±0.007

896 .6 0 .095 ±0 .018 0.095 ±0 .018

977.4 1.435 ±0 .016 1.434 ±0 .016

996 .9 0.129 ±0.014 0 .129 ±0.014

1037.8 14.16 ±0 .05 14.15 ±0.07

1089 .1 0 .05 ±0.03 0 .05 ±0.03

1140.3 0.131 ±0.021 0 .131 ±0 .021

1160 .0 0.095 ±0 .014 0.095 ±0 .014

1175.1 2.241 ±0.012 2.239 ±0 .014

1198.8 0.051 ±0.009 0 .051 ±0.009

1238.3 66.06 ±0.21 66.0 ±0.3

1272 .0 0 .025 ±0 .008 0 .025 ±0.008

1335.5 0.130 ±0.006 0.130 ±0.006

1360.2 4.265 ±0.017 4.262 ±0 .022

1442.7 0 .172 ±0.007 0.172 ±0.007

1462.3 0.084 ±0.006 0 .084 ±0.006

1640.4 0 .070 ±0.011 0.070 ±0.011

45
Nuclide

Gamma ray

Energy Relative intensity Intensity per decay

(keV) (%) (%)

1 "7 "7 1 A i U . Ud 1 C AO -0 .07

1810 .7 0.657 ±0.023 0 .656 ±0 .023

1963.8 0.707 ±0.011 0.706 ±0.011

2015.4 3.026 ±0.014 3.024 ±0.017

2034.9 7.766 ±0.028 7.76 ±0.04

2113.3 0.363 ±0.007 0.363 ±0.007

2213.0 0.389 ±0.008 0.389 ±0.008

2276 .1 0.124 ±0.007 0.124 ±0.007

2373.5 0.083 ±0.011 0.083 ±0.011

2523.8 0 .068 ±0.011 0 .068 ±0 .011

2598.6 16.96 ±0.06 16.95 ±0.08

2657.4 0 .021 ±0.006 0 .021 ±0.006

898.0 94 4 ±0.3 93 .

7

±0.4

1836.1 100.0 + 0 3 99.24 ±0.07

o o r\ t 329.1 A TO 0 . 12 ±0.07 0 . 12 X A A C ±0.06

371 3 2 14 + 0 04 2 02 ±0.04

-JSIX fto 0 6u o 59 + 0 09 0 56 + 0 09

J u x « u

+ 0 024 0\J 0 X117X / + 0 02"}

7R 7 9 u « U O 3/ — VJ 0 v/ £ *± 0 065 ±0 02"}

827 .

7

1 . 30 ±0.06 1.22 X A A /- ±0.06

R90 6 2 OS + 0 06 1 93 ±0 05

X1051 "5 W —» X 9 ~J 0 25 + 0 03 0 23 ±0.03

1 1 S>Q ? ion o + 0 T 94 22 ±0 09

X19 70/ U * 4*i X1 • 9o*3 -J J — U ( UlU 1 181 ±0 019

1470 „

5

a c A 0.50 _l a AO ±0.03 0.471 ± u . uzy

1575 0 0.531 ±0.025 0 . 499 ±0 .024

X1611 U X X # 8o 2.54 ±o!o3 2.40 ±0.03

1658.1 0.302 ±0.023 0.294 ±0.022

1716.3 0.561 ±0.025 0 .528 ±0.023

l fid "3 "3 0.73 ±0.03 0 .69 ±0.03

1 Q1 o 9 1.41 ±0 .03 1.33 ±0.03

iUDD J 0.13 ±0 .05 0.12 ±0 .04

2186 .

2

19.19 ±0.08 18.11 ±0.08

2222.3 0.67 ±0.03 0 .630 ±0.029

2319.0 86 .68 ±0.28 81.82 ±0.08

2741.0 0.0102±0.0026 0.0096±0.0025

2747.8 0.0081±0.0026 0.0076,±0.0025

365.4 0.091 ±0.019 0 .086 ±0.018

387.1 0.08 ±0.04 0.07 ±0 .03

396 .9 0.06 ±0.03 0.06 ±0 .03

446.8 3.955 ±0.028 3.739 ±0 .027

620.4 2.965 ±0.019 2.803 ±0.019

46
Nuclide Gamma ray

Energy Relative intensity

(keV) (%)

Intensity per decay

(%)

1 2 it Sb

626 .3

657. 8 676 .6

677.6

687.0

706.7

70 8.3

744.3

763.9

818.0

884.7

937.5

997.2

1085.4

1117.5

1125.7

1163.2

1164.9

1251.0

1300.0

1334.4

1384.3

1421.0

1475.8

1505.0

1562.3

1592.6

1629.6

1775.4

1783.4

1903.5

370.4

400.0

444.0

468.6

525.5

602.7

632.4

645.8

662.5

709.3

0.228 ±0.014

100.0 ±0.4

11.09 ±0.08

6.80 ±0.06

17.66 ±0.10

5.000 ±0.027

23.55 ±0.09

7.76 ±0.04

76.76 ±0.26

36.31 ±0.12

0.142 ±0.005

0.066 ±0.012

0.041 ±0.006

0.038 ±0.008

0.079 ±0.012

0.024 ±0.007

0.025 ±0.008

0.149 ±0.006

25.66 ±0.08

0.039 ±0.003

4.222 ±0.017

13.78 ±0.05

1.087 ±0.007

0.022l±0.0013

0.0061±0.0011

0.0067±0.0011

0.0103±0.0011

0.0158±0.0015

0.051 ±0.009

0.129 ±0.016

0.205 ±0.010

0.058 ±0.008

0.117 ±0.012

100.0 ±0.4

0.114 ±0.006

7.61 ±0.03

0.016 ±0.005

1.399 ±0.011

0.216 ±0.013

94.54 ±0.20

10.48 ±0.09

6.43 ±0.06

16.70 ±0.12

4.73 ±0.03

22.26 ±0.13

7.33 ±0.05

72.6 ±0.4

34.33 ±0.20

0.134 ±0.005

0.062 ±0.012

0.039 ±0.005

0.036 ±0.007

0.075 ±0.011

0.023 ±0.007

0.024 ±0.008

0.141 ±0.005

24.25 ±0.14

0.037 ±0.003

3.992 ±0.024

13.03 ±0.07

1.028 ±0.008

0.0209±0.0012

0.0058±0.0010

0.0063±0 .0010

0.0097±0.0010

0 ,0149±0 .0014

0 .050

0 .127

0.201

0.057

0.115

97.83

0.111

7.44

0.015

1.368

±0.009

±0.015

±0.009

±0.008

±0 .012

±0.05

±0 .006

±0.04

±0.005

±0.012

47
Nuclide Gamma ray

Energy Relative intensity Intensity per decay

\ JVC V /

713.82 2.338 ±0.012 2.288 ±0.015

722. 8 11.02 ±0.04 10.78 ±0.06

735.9 0.133 ±0.009 0.130 ±0.008

790.8 0.758 ±0.009 0.741 ±0.009

816.8 0,079 ±0.006 0.077 ±0.006

856.9 0.029 ±0.007 0 .029 ±0 .007

899.8 0.016 ±0.009 0.016 ±0 .009

968.3 1.919 ±0.013 1.877 ±0.014

976 .4 0.088 ±0.008 0.086 ±0.008

1045.2 1.864 ±0.017 1.824 ±0.018

1086.3 0.038 ±0.009 0.037 ±0.009

1263.1 0.046 ±0.015 0.045 ±0.014

1301.2 0.041 ±0.015 0.040 ±0.015

1325.5 1.584 ±0.022 1.549 ±0.022

1355.2 1.042 ±0 .027 1.019 ±0 .027

1368.2 2.67 ±0.03 2.61 ±0 .03

1376.1 0.501 ±0.020 0.490 ±0.020

1385.2 0.061 ±0.026 0.060 ±0.025

1436.7 1.225 ±0 .024 1.19 8 ±0.024

1445.3 0.358 ±0.017 0.351 ±0 .017

1489 .0 0.679 ±0.019 0.664 ±0 .018

1526.3 0.410 ±0.024 0.401 ±0.024

1579.9 0.433 ±0 .012 0.424 ±0.012

1622.4 0.035 ±0.012 0.034 ±0 .012

1691.0 48.58 ±0.16 47.52 ±0.23

1720 .

3

0.097 ±0 .007 0 .095 ±0 .007

1918.7 0.052 ±0 .004 0.051 ±0 .004

2015.0 0 .0093 + 0 .0026 0 .0091±0 .0025

2039 .3 0 .0589 ±0.0029 0 .0576±0 .0028

i n i q ^ 0 .0163±0 .0025 0 .0159 ±0 .0024

2091.0 5.589 ±0.022 5.47 ±0.03

2099 .0 0.045 ±0 .006 0.044 ±0 .006

2108.0 0.0438±0 .0027 0 .0428 ±0 .0026

2182.6 0 .0398±0 .0019 0 .0389 ±0 .0019

2283.2 0.0041.±0.0013 0 .0040±0 .0013

2293.7 0.031 ±0 .010 0.030 ±0 .010

2693.9 0 .002710 .0019 0 .0026 ±0 .0019

276 .4 11.53 ±0.06 7.15 ±0.03

302.8 29.48 ±0.14 18.28 ±0.08

356.0 100.0 ±0.4 62.00 ±0.14

383.8 14.39 ±0.06 8.92 ±0.04

48
Nuclide Gamma r^

Energy Relative intensity Intensity per decay

(keV) (%) (%)

131t Cs 563.1

569.2

604.7

795.8

801.8

1038.4

1167.7

1365.0

152 Eu 295.9

329 .4

344.3

367.8

411.1

443.9

488.7

503.5

564.0

566.6

586.3

656 .5

674.6

678.6

688.6

719.3

764.8

778.8

810.4

841.5

867.3

901.2

919.3

926 .2

930.5

963.3

964.0

1005.1

1085.8

1089.7

o • -J / O a O / + ft flR 15.78 ±0.06 15.40 ±0.08

100.0 ±0.4 97.64 ±0 .06

87.5 ±0.3 85.52 ±0.05

8.89 ±0.03 8.68 ±0.04

i n n b + ft ft ft ^ ft Q P. A + ft ft ft £ 1 .827 ±0.008 1.783 ±0 .010

3.074 ±0 .013 3.001 ±0 .017

2 .14 ±0.04

0.711 ±0 .014

xz1 ~) ~l Q / . y

+ ft k 4. 16 ±0.04

10 .90 ±0.05

15.06 ±0.06

2.031 ±0.015

0.768 ±0.018

+ 0 04

0 6 4 ±0.06

2.19 ±0.08

0.71 ±0.05

0 9 4 ±0.05

2.28 ±0*.05

4.20 ±0.04

1.67 ±0.03

0.95 ±0.05

62.16 ±0.22

1.56 ±0.04

0.837 ±0.023

20.33 ±0.10

0.40 ±0.05

2.08 ±0.06

1.38 ±0.06

0.37 ±0.06

70.14 ±0.23

3.078 ±0.024

48.15 ±0.16

8.35 ±0.04

49
Gamma ray

Nuclide

Energy Relative intensity Intensity per decay

(keV) (%) (%)

1 5 *Eu

1108 .9 1.00 ±0.05

1112 ,0 64.67 ±0.21

1212 .0 6.85 ±0.05

1249 r\ OTP 0.875 ±0.024

1292 . 7 0.46 ±0.03

1299 .2 7.80 ±0.05

1408 .0 100.0 ±0.3

1457 .6 2.391 ±0.029

1528 . 1 1.346 ±0.013

401 ,2 0.49 ±0.04

444 .5 1.64 ±0.03

478 .3 0.626 ±0.027

557 .6 0.758 ±0.024

582 .0 2.61 ±0.03

591 .7 14.35 ±0.06

625 = 2 0.927 ±0.021

676 ,5 0 .47 ±0.05

692 .4 5.182 ±0 .025

723 . 2 58 . 19 ±0.21

756 ,8 13.18 ±0 .07

815 .5 1.51 ±0.05

845 .4 1.687 ±0.021

850 .7 0.692 ±0.023

O / J

*3 C TO + 0 12

892 . 8 1 . 497 ±0 .026

904 . 1 2.62 ±0.03

996 . 2 30 .09 ±0 . 12

1004 . 7 52.04 ±0 . 19

1128 .5 0.90 ±0.04

1140 .7 0 .671 ±0.014

1241 .4 0.38 ±0.05

1246 .2 2.49 ±0.04

1274 .4 100.0 ±0.3

1494 „2 2.058 ±0.016

1596 .7 5.247 ±0.026

283 .3 0 .303 ±0.022

296 .0 34.62 ±0.17

308 .5 35.84 ±0.18

316 .5 100.0 ±0.5

374 .5 0.861 ±0.008

192 Ir 283.3 0.303 ±0.022 0.251 ±0.018

28.70 ±0.28

29.71 ±0.29

82.9 ±0.6

0.714 ±0.009

50
Nuclide

Gamma ray

Energy Relative intensity Intensity per decay

(keV) (%) (%)

416 .5 0.800 ±0.010 0.661 ±0.010

420 .5 0.078 ±0.009 0.065 ±0.007

468 .1 57.50 ±0.23 47.7 ±0.4

484 .6 3.810 ±0.018 3.16 ±0.03

. 1 u.dzd ±u. uuy U , 4 JD -U.UUo

588 .6 5.398 ±0.021 4.48 ±0.04

593 .4 0.052 ±0.003 0 .0432±0 .0026

604 .4 9.75 ±0.04 8.08 ±0.07

612 .5 6.336 ±0.025 5.25 ±0.05

884 .5 0.3420±0.0024 0.284 ±0.003

1061 .5 0.0631±0.0011 0 .0523±0 .0010

1089 .9 0.0010±0.0005 0 .0008±0 .0004

1378 .0 0.0016±0.0005 0.0013±0.0004

411 .8 100.0 ±0.4 95.56 ±0.08

675 .9 0.841 ±0.003 0.804 ±0.005

1087 .7 0.1664±0.0021 0.1591±0.0021

569 .7 100.0 ±0.4 97.74 ±0.03

897 .3 0.122 ±0.013 0.119 ±0.012

1063 .6 75.79 ±0.25 74.0 ±0.3

1442 .2 0.132 ±0.005 0.129 ±0.005

1770 .2 7.026 ±0.029 6.87 ±0.04

I

51
International Atomic Energy Agency

Laboratory Seibersdorf

Vienna, Austria

H. Houtermans, 0. Milosevic and F. Reichel

The values given in the summary table have been extracted from the article in

Int. J. appl Radiat. Isotopes, _3_I 153 (1980). The overall uncertainties are the

"arithmetic sum of the statistical error (c.l. 68%) and the systematic errors,

which are estimated for the same confidence level".

Institute d'Electrochimie et de Radiochimie

Ecole Polytechnique Federale

Lausanne, Switzerland

Marc Decombaz and J. -J. Gostely

A half life of (137.8 + 0.2) d was measured for l-^Ce in connection with an international intercomparison arranged by the Bureau International des Poids

et Mesures, and reported in Rapport BIPM - 77/4. The activity of three sources

was measured by the 4 pi(PC)-gamma coincidence method, and followed for 2.5

months. The uncertainty has the significance of the standard deviation of the

mean.

Idaho National Engineering Laboratory

EG&G, Idaho, Inc.

Idaho Falls, Idaho, USA

R.J. Gehrke, R.G.Helmer and R.C. Greenwood

The authors report that the data given in Nuclear Instruments and Methods 147 , 405 (1977) remain valid as given. This article gives a description of their

equipment, methods, corrections and analysis of uncertainties. The significance

of the uncertainties is the same as requested here.

Lawrence Livermore Laboratory

University of California

Livermore, California, USA

R. A. Meyer

The data included in the summary table have been taken from Lawrence Livermore

Laboratory report M-100, Multigamma-Ray Calibration Sources, December 1, 1978.

The uncertainties are taken to be comparable in their meaning to that requested

for the compi 1 ation.

52
NUCLEAR DATA FOR PHOTON

F. LAGOUTINE, J.

LABORATOIRE DE METROLOGIE DES

SPECTROMETERS CALIBRATION

MOREL, J. LEGRAND

RAYONNEMENTS IONISANTS (FRANCE)

This document presents, on the one hand, the nuclear constants characteristic

of several radionuclides measured at Laboratoire de Metrologie des Rayonnements

Ionisants since the year 1970 and, on the other hand, X or y references used

for the efficiency calibration of photon spectrometers.

Concerning the first part of this document, LMRI contributed to the study

of decay schemas by the following measurements :

Half lives

?Be .

24

Na .

33

p . 51^ .

5 6cQ . 56^ . 57^ . 58^ .55

Fe . 65^ _

67

Cu - 67

Ga -

75

Se -

85

Sr -

88Y -

89Y - ^Sr -

9 *\c - 103

Ru -

109Cd - U1ln - ll3mIn -

123

I - 125m

Te -

131

Cs -

131

I -

134

Cs - 137

°>Ba -

139Ce -

152

EU -

152TMEu -

169Yb - 176m

Lu -

177

LU -

192lr - 201T1 -

252

C£.

X or y_rays

60o 59 54^. 93m,. 133n 14 1_ 152_ 176m_ 192T 239,. 24 1_ Co - Fe- Cu - Nb - Ba- Ce- Eu- Lu — Ir - Pu- Am

Internal conversion

^Sr - - 93"k> -

95Nb -

9!%= -

109Cd -113mln - 125^ _ 129^

135n^ . 137^ m 139

Ce . 141^

53
Other constants

Cu - (6 , 8 emission) - Tc (6 emission) - Rh {X^ emission) - Cr (o)K

)

The following rule was generally adopted for evaluating the total uncertainty

of measured constants at LMRI : The uncertainty is the result of the sum of the statistical uncertainties/

evaluated at 99.7 % confidence level and combined quadratically, and of

the systematic ones themselves, summed linearly.

Concerning the second part of this document, dealing with X or y references

used in y spectrometry, most of the data mentioned (especially y emission

intensities) come from Table des Radionucleides (LMRI)

.

54
LABORATOIRE DE K£-mOLOGIE DES

RAYONNEKENTS IONISANTS

AOUT 1930

PARAMETRES DE SCHEMA DE DESINTEGRATIQN

MESURES AU LMRI DEPUIS 1970

Be periode

T 1/2

53,17

24

Na periode

T 1/2

14,956

33 P periode

T 1/2

25,56

incertitude

0,07

incertitude

0,008

incertitude

0,07

unite

jour

unite

heure

unite

jour

reference

IJARI, 26 (1975), 131

reference

publication en cours

reference

IJARI, 23 (1972) , 219

51 Cr periode

T 1/2

27,72

Co periode

T 1/2

77,12

incertitude

0,07

incertitude

0,20

unite

jour

unite

jour

reference

IJARI, 26 (1975) , 131

reference

IJARI, 29 (1978), 269

55
Mn periode

T 1/2 incertitude unite reference

2,5785 0,0006 heure NIM, 112 (1973), 323

^.Cr rendement de fluorescence

24

incertitude reference

0,290 0,003 Z.Phys. A 284 (1978), 389

^Co periode

T 1/2 incertitude unite reference

271,23 0,63 jour IJARI, 23 (1972), 219

58Co periode

T 1/2

70,78

incertitude

0,13

unite

jour

reference

IJARI, 26 (1975) , 131

60

Co probability d' emission P

P (2158keV)

0,5 x

10" 5 incertitude

0,2 x 10

-5

reference

IJARI, 23 (1972) , 225

55

Fe periode

T 1/2

2,68

incertitude

0,02

unit6

an

reference

publication en cours

56
59

Fe probability d' emission F

E

Y 142

192,2

334,7

381

1099

1292

1481

P

Y 0,0098

0,0295

0,0024

0,00023

0,555

0,441

0,0009

incertitude

0,0004

0,0008

0,0004

0,00005

0,017

0,012

0,0002

reference

Nucl . Phys

.

A 142, (1970) , 63

64Cu probability d' emission £ incertitude

0,005

rapport 6~/6 , Y/B

+ V

0,180

reference

N.T. LMRI 76/17

1,99

incertitude

0,10

Y/6

0,0260 0,0011

energie y

E y

1345,88

incertitude

0,12

unite

keV

65 Zn periode

T 1/2

243,75

incertitude

0,35

unite

jour

reference

IJARI, 26 (1975), 131

67^Cu

T 1/2

61,83

periode

incertitude

0,21

unite

heure

reference

IJARI, 23 (1972) , 219

57
67

Ga periode

T 1/2

78,33

75

Se periode

T 1/2

118>45

85

Sr periode

T 1/2

64,68

incertitude

0, 10

incertitude

0,25

incertitude

0,23

unite

heure

unite

jour

unite

jour

reference

IJARI, 29 (1978), 269

reference

IJARI, 26 (1975) , 131

reference

IJARI, 23 (1972)

88,

T 1/2

106,6

89

T 1/2

50,75

90

T 1/2

28,15

periode

Sr periode

Sr periode

incertitude

0,4

incertitude

0,25

incertitude

0,10

unite

jour

unite

jour

unite

ans

reference

IJARI, 26 (1975), 131

reference

IJARI, 23 (1972), 219

reference

IJARI, 29 (1978), 269

58
Probabilites d' emission d' electrons de conversion

P- . e incertitude reference

-4 -4

1,2 x 10 0,6 x 10 CONF-720404 (1972)

probability d'emission de paires internes

e incertitude

3,9 x

10~ 5 0,4 x

10~ 5

rapport K/LMN

K/LMN incertitude

3,2 0,

7

probability d'ionisation interne

pk incertitude

3,6 x

10~ 4 0,4 x 10"4

90

y probability d'ionisation interne

P. incertitude k

6,0 x 10"40,6 x 10~4

93mNb energie y

incertitude

0,02

rapport des emissions y

Y 30,77

unite

k.eV

reference

C.R. Acad. Sci. Paris

E. 284 (1977)

Y/X^ incertitude

8,0 x 10~ 5 1,0 x 10" 5

rapport de coefficients de conversion interne

K/LM . . . incertitude

0,173 0,007

reference

These-Doctorat es Sciences

Orsay n° 2166 (1979)

59
95

Nb coefficient de conversion interne a

aK

1,18 x 10

-3

incertitude

0,05 x 10

rapport K/L

-3

reference

CONF-720404 (1972)

K/L

8,7

incertitude

0,7

"'^ mTc periode

T 1/2 incertitude unite

6,031 0,012 heure

coefficient de conversion interne at

reference

IJARI, 21 (1970), 139

at

0,118

incertitude

0,003

reference

Rapport CEA-R-4427 (1973)

99Tc probability d' emission 6 de 202 keV

V incertitude

1,6' x 10

-5

reference

Phys.Rev. 8C (1973), 366

103 Rh periode

T 1/2

56,112

P (xK

) 0,0753

incertitude

0,028

probability d' emission XK

incertitude

0,0034

unity

minutes

reference

IJARI, 29 (1978) , 269

reference

N.T. LMRI 76/13

60
109Cd

at

25,4

T 1/2

463,1

111

Coefficient de conversion interne at pour la transition y de 88 keV

In periode

T 1/2

2,802

incertitude

0,5

incertitude

0,8

unite

jour

incertitude

0,003

unite

jour

reference

Rapport CEA-R-4427 /1973/

Publication en cours

reference

IJARI, 29 (1978) , 269

113m

T 1/2

1,658

In periode

incertitude unite

0,004 heure

Coefficients de conversion interne

at

0,559

ak

0,441

incertitude

0,014

0,013

reference

IJARI, 21 (1970) , 139

reference

IJARI, 21 (1970) , 139

123

I- T 1/2

13,214

periode

incertitude

0,034

unite

heure

reference

publication en cours

periode

T 1/2 incertitude unite

57,40 0,15 jour

Coefficients de conversion interne

at incertitude

14,25 0,64

ak

11,90

reference

IJARI, 29 (1978) , 269

reference

These-Doctorat es Sciences

Orsay n° 2166 (1979)

0,31

61
Rapports de coefficients de conversion interne

VL

2 /L

3 1/0,082 - 0,004/0,019 - 0,003

VM

2 /M

3 1/0,092 - 0,005/0,044 - 0,003

reference

These Doctorat es Sciences

Orsay n° 2166 (1979)

129raxe coefficient de conversion interne pour la transition y de 39,58 keV

ak incertitude reference

10,72 0,26 These Doctorat es Sciences

Orsay n° 2166 (1979)

131 Cs periode

T 1/2

9,66

incertitude

0,06

unite

jour

reference

IJARI, 26 (1975), 131

131

I T 1/2

8,020

periode

incertitude

0,003

unite

jour

reference

IJARI, 29 (1978) , 269

133 Ba Energie y

EY

53,156

79,624

80,998

160,616

223,224

276,395

302,850

356,006

383,845

incertitude

0,008

0,018

0,007

0,010

0,012

0,012

0,008

0,010

0,010

unite

keV

reference

LMRI/80/776/EM/

62
Probability d' emission y E P incertitude

Y K

a 0,997 0,030

K

6 0,229 0,008

53,2 0,0224 0,0006

79,624 0,0257 0,0012

81,0 0,345 0,008

160,616 0,0064 3 0,0002

223,224 0,00436 0,00015

276 0,0716 0,0015

302,845 0,1827 0,0035

356,006 0,619 0,010

383,845 0,0891 0,0019

reference

LMRI/80/776/EM

134Cs periode

T 1/2

2,058

incertitude

0,012

unite

an

reference

IJARI, 23 (1972), 219

Coefficient de conversion interne pour la transition de 268 keVdu Ba

5,42

incertitude

0,11

reference

Rapport CEA-R-4427

137_ . 137HL, . . , 137m

Cs + sa periode Ba. T 1/2 incertitude unite reference

2,5545 0,0021 minute Rapport CEA-R-4428 (1973)

137 Conversion interne pour la transition de 662 keV du Ba

a , incertitude reference

k

0,0901 0,0011 Rapport CEA-R-4428 (1973)

°t

0,1105 0,0010

K/LM

4,39 0,07

63
139 139 Ce conversion interne pour la transition de 166 keV du La

0,2111

a

t 0,2446

K/L

7,80

K/LM

6,30

L/M

4,30

incertitude

0,0026

0,0012

0,35

0,30

reference

Rapport CEA-R-4427 (1973)

0,40

T 1/2

137,59

periode

incertitude

0,12

unite

jour

reference

IJARI, 29 (1978) , 269

141 Ce

Y 0,4844

a

k

0,359

probability d

1 emission y

incertitude

0,0042

Coefficient de conversion interne

incertitude

0,016

reference

IJARI, 26 (1975), 179

152 Eu

T 1/2

13,10

periode

incertitude

0,15

unity

an

reference

IJARI, 29 (1978) , 269

64
energie y

E incertitude unite reference

Y121,78 0,02 KeV Rapport CEA-R-4656 (1975)

148.3 0,7

207.4 0,7

'210,0 0,7

212.3 0,2

237,0 0,7

239,1

244,69 0,02

251,76 0,08

271,00 0,06

275.4 0,1

285,7 0,7

295,94 0,03

315,28 0,07

317,0 0,7

324,80 0,09

329,44 0,06

339,6

344,28 0,02

351,7 0,7

367,76 0,03

411,12 0,02

416.04 0,07

C443,98 0,02

\444,00 0,10

482.5 0,1

488,68 0,03

493.6 0,1

496,4 0,7

503,47 0,05

520,23 0,07

523,0 0,7

65
E Y (suite) incertitude unite' reference

526,9 0,7 keV

534,33 0,14

556,6 0,5

564,02 0,04

566,36 0,08

586,26 0,03

616,1 0,7

644,5 0,7

656,47 0,08

665,0 0,7

671,5 0,7

f 674,63 0,06

1675,0 0,3

678,60 0,04

f 686,4

1 688,69 0,08

712,85 0,06

("719,36 0,04

\719,3

728.5 0,7

764,9 0,1

768,9 0,1

778,90 0,03

794.6 0,7

810,47 0,06

("839,4

|841,65 0,06

867,38 0,03

901,05 0,1

919,34 0*04

926,29 0,06

930,54 0,05

958,4

f963,43 0,08

{964,05 0,03

974,7 0,7

Rapport CEA-R-4656 (1975)

66
E y (suite) incertitude unit£ reference

990,2 0,2 keV Rapport CEA-R-4656 (1975)

1005,15 0,05

1085,83 0,03

1089,72 0,04

1109,2

1112,08 0,04

1171.02 0,07

1205", 4 0,7

1212,94 0,04

1249,88 0,07

1261.3 0,2

1292,86 0,07

1299,13 0,04

1315.7 0,7

1348.2 0,3

1364.0 0,2

1389.8 0,7

1408.03 0,03

1457,62 0,04

1528,10 0,05

1605,5 0,2

1608,7 0,2

1647.1 0,2

1768.9 0,2

67
Intensite absolue des photons ^

Ey l f

(%) incertitude reference

rapport CEA-R-4656

(1975)

121,78 28,2 0,5

148,3 ~> 0,01

207,4

210,0

212,3

^ 0,005 ^ 0,005

-v 0,01

237,0 ~ 0,01

239,

1

244,69 7,38 0,13

251,76 0,04 0,02

271 ,00 0,080 0,011

275,4 0,038 0,009

285,7 4 0,005

295,94 0,423 0,013

315,28 0,038 0,008

317,0 ~0,01

324,80 0,066 0,014

329,44 0,104 0,012

339,6

344,28 26,4 0,4

351,7 0,009 0,006

367,76 0,84 0,03

411,12 2,21 0,04

416,04 0,090 0,017

(443,98

| 444,00

3,076 0,05

482,5 0,013 0,006

488,68 0,400 0,023

493,6 0,033 0,015

496,4 ~ 0,005

47 0 1 ^Cl 520,23 0,049 0,016

523,0 ~j 0,005

526,9 0,005

534,33 0,041 0,015

556,6 ^ 0,01

564,02 0. 486 0.021

63
566,36

586,26

616,1

644,5

656,47

665,0

671,5 { 674,63 I 675,0

678,60 [ 686,4 \ 688,69

712,85 ( 719,36 I 719,3

728,5

764,9

768,9

778,90

794,6

810,47 ' 839,4 , 841,65

867,38

901,05

919,34

926,29

930,54

958,4

963,43

964,05

974,7

990,2

1005,15

0,127

0,454

'v 0,01 ~ 0,005

0,135 ~ 0,005

0,013

0,175

0,459

0,849

0,094

0,322 ~ 0,005

0,143

0,072

13,00

0,026

0,321

0,123

4,16

0,100

0,410

0,253

0,070

0,013

0,023

0,016

0,007

0,023

0,020

0,025

0,022

0,018

0,019

0,024

0,22

0,013

0,024

0,019

0,06

0,031

0,022

0,021

0,024

14,48

0,011

0,020

0,59

0,23

0,003

0,009

0,03

69
incertitude reference

rapport

CEA-R-4656

1085,83

1089,72

1109,2

1112,08

1171,02

1205,4

1212,94

1249,88

1261,3

1292,86

1299,13

1315,7

1348,2

1364,0

1389,8

1408,03

1457,62

1528, 10

1605,5

1608,7

1647,1

1768,9

10,14

1,70

13,55

0,034

0,01

1,39

0,179

0,034

0,113

1,63

0,003

0,019

0,026

-v/ 0,005

20,70

0,488

0,266

0,007

0,005

0,006

0,009

0,16

0,09

0,20

0,012

0,03

0,015

0,017

0,023

0,03

0,002

0,006

0,006

0,29

0,015

0,015

0,002

0,001

0,002

0,002

152 p£riode

Tl/2

9,274

incertitude

0,009

unite

heure

reference

publication en cours

70
periode

Tl/2

31,97

incertitude

0,05

unite

jour

reference

IJARI, 26 (1975), 131

176

"Lu

Tl/2

3,635

periode

incertitude

0,012

unite

heure

reference

publication en cours

energie

88,36

202,2

936,25

956,8

1061,42

1138,25

1159,26

1204,70

1226,61

1247,62

incertitude

± 0,02

0,3

0,20

0,3

0,08

0,15

0,07

0,18

0,16

0,09

unite

keV

reference

N.T. LMRI 77 43/MJ

publication en cours

71
probability d'emission <T

Py incertitude reference

88,36 0,088 0,002

202,2 8,10~

936,25 2,2 x 10~? 0,7 x 10~f

956,8 0,4 x 10:^ 0,2 x 10Z?

1061,42 7,5 x 10 6 1,7 x 10 6

1138.25 2,3 x 10~6

0,6 x 10

_6

1159.26 13,7 x

10~6

3,0 x

10~6

1204,70 0,9 x 10~60,3 x

10"6

1226.61 1,3 x

10"6

0,4 x 10~6

1247.62 0,20 x 10

_6 0,16 x 10"6

NT LMRI 77 43/MJ

177Lu periode

T 1/2

6,645

incertitude

0,030

unite

jour

reference

publications en cours

Ir periode

T 1/2 incertitude unite reference

74,02 0,18 jour IJARI 23 (1972) 219

72
incertitudes relatives des photons 5

Ey Iy incertitude ref

Nucl. Phys. A 142

(1970) 63

110.1 non observe

136,32 0,22 0,08

201.2 0,56 0,08

205,8 4,2 0,2

283.3 0,29 0,10

295,94 36,5 1,0

308,43 37,4 1,0

316.49 100

374.4 0,82 0,05

416,45 0,70 0,15

468.05 57,4 2,0

484,5 3,5 0,2

489,1 0,41 0,13

588,56 5,37 0,25

604,37 10,0 0,4

612,3 6,4 0,2

766,43 non observe

884.50 0,35 0,04

1062,2 0,062 0,020

1378,7 non observe

39 y

Pu energie des principaux photons 3

Ey incertitude unite keV reference

111,33 0,13 rapport CEA a paraitre

129.29 0,02

161.30 0,21

171,30 0,07

179,19 0,09

195,65 0,05

203,55 0,02

73
9 9 C TO 6zd , jy

a 1 a U , 1 

9yl "3 *3 /Ia 1 a 0,10

ICC 9 ,/!

aa o 0, 03

263 ,95 0, 07

29 / , 4b 0 , 04

911 "7nA A/1 0, 04

TIC 9 r Jib, J3

A A"7 0,0/

j^u o on , onyu

a r\A 0 , 04

32J , o J

A AO 0 , 03

mQ yl

J

J 2 ,U4

A AO 0, 02 j jo, uy A AO 0, 03

"3 yl 1 C

A .341 , b4A AC

j4b, UU

A AO 0 , 02 3 /b,U4 A AO 0, 02

3o0, lo

A A/1 0,04

lOO -7/" 3o2 , /bA A/1 0, 04

jyz, /2

A AO 0 , 02

399 ,33

A AiC 0, 0b

y! 1 9 "7 "3 4 1 O , / JA AO 0 , 02

yi 9 9 cn 422 , bUA AO 0 f 02

yl "7 "3 42b, 

j A

A /I 0 ? 04

yl

C 1 CA 451 , 5U 0, 02

ylO 1 CA 4ol , 54 0,06

COO "3 598,3 o o 0,2

y- 4 o 618,32 0, 09

/TOO DO 639 , ooO 1 o 0,10

/-AC OQ 643 , oo

O o "7 0, 07

703,59 0,08

717,58 0,18

756,24 0,08

769,19 0,04
probability d' emission des principaux photons V

Ej Py incertitude (%) reference

rapport CEA a paraitre

129,3 6,23 10

5 0,7

143,3

144,2 2,96 10"6 4,0

161,5 1,21 10~ 6 5,7

171,4

-6

1,05 10 6,0

179,2 6,45 10" 7 7,2

189,3

-7

8,30 10

195,7

-6

1,02 10 6,4

203,5

-6

5,57 10 4,7

255,4 7,94 x

10~7 7,7

297,5 4,83 x

10~7 9,5

345,0 5,45 x

10"6 3,5

375,0 1,55 x

10"5 3,2

414,0 1,48 x

10~5 3,2

201Tl

T

1/2

3,048

Incertitude

0,0040

Unite

3 our

Reference

publication en cours

75
Am energie y

E

K incertitude incertitude E

r

incertitude

(keV) (keV) (keV) (keV) (keV) (keV)

26,345 0,005 164,63 0,04 275,66 0,05

165,94 0,05 291,15 0,12

33,20 0,02 169,59 0,03 292,77 0,05

43,42 0,02 175,10 0,04 233

Pa

55,54 0,02 190,25 0,15 304,2 0,2

59,537 0,001 191,90 0,04 233 Pa

322,50

322,37

0,02

0,02

69,75 0,05 204,01 0,16 335,40 0,02

98,94 0,02 208,02 0,02 confondu

102,97 0,02 221,47 0,03 233^

Pa

232,93 0,06 350,5 0,2

1 00 QQ 1 "» 3 3 U , Uj coniuiiuu J DO f u , z 125,27 0,02 246,74 0,07 368,60 0,02

139,59 0,10 260,9 0,2 371,00 0,02

146,56 0,03 264,83 0,04 376,60 0,02

150,14 0,04 267,53 0,03 383,75

390,62

0,04

0,05

76
E vyY incertitude E wY i ncc

keV keV keV keV

406,45 0,08

CCiO HA boo , /4 0 ,02

233 Pa

CQ"3AO byJ , 4 2. 0 ,08

419,25 0,03 byb ,4b 0 , 06

426,54 0,06 709,38 0,05

429,7 0,2

"7/ z0 1 QC i , yb 0 , 02 7 OQ *5 n / ^y , ju U , 13

442,73 0,04

71 1 A 0,3

452,0 0,2

777 0 "5

n PiA

454,61 0,04

7^t? rc; /JJf OJ

U , Ub

459,62 0,06

icq cc / Dy ,33

nU, 113^

468,01 0,07

7fi7 / DO 7, / u , b

AOCOO 48b, 2^

n 1 766,89 0,07

M.P. 770,50 0,12

514,2 0,2 772,3 0,2

522,3 0,2 777

AOA

574,0 0,2

7QAQ /OU , O 0,3

M.P.

586,66 0,10

7DQQ /DO , OA "5 0,3

590,30 0,06

on 1 oc OUl , 03

A 1 A

597,43 0,03

one c BUD , 3 0,4

619,00 0,02

O 1 1 h c oil, /b 0,15

627,22 0,15 o iy , 3 A

O 0,3

632,92 0,13 o o o n

AA 0,4

641,40 0,04 828 , 5

0,4

652,93 0,04 851,6 0,3

662,40 0,02 855 , 1

0,4

670,2 0,3

AD 0,3

675,5 0,3 887,6 0,4

680,00 0,10 898,5 0,6

902,6 0,3

912,3 0,5

922,5 0,4

929,0 0,5

945,7 0,4

955,8 0,3

962,0 0,5

77
Probability d'emiss on y

E Y

26,3

32,2

33,2

43,4

55,5

59,5

67,5

69,7

k a2 (97,1)

98,9

k al (101,1)

103,0

kB3, k3 1, k65(113,3-

114,2 - 114,9)

k84, k&2, kfiX (117,3

117,6 - 118,4)

123,0

125,3

139,6

146,6

150,

1

159,1

164,6

165,9

169,6

17-5,1

190,3

191,9

194,7

201 ,7

204,0

2,35 x 10

-2

limite 3.10

1,22 x 10~ 3

6,9 x

10"4

1,5 x 10

0,365

-5

-4

limite 5.10

<\,2.10~ 6

-6

1,22 x 10

2,05 x 10

1,96 x 10

-5

-4

-5

2,02 x 10

.-6

-4

6,35 xlO

2,0 x 10

-6

-5

1,07 x 10

4,17 x 10" 5

5,7 x 10"8

4,70 x 10~6

7,6 x

10~7

limite 8.10

7,1 x

10"7

-9

2,28 x 10

1,84 x 10

-7

-6

1,74 x 10

'

2,5 x

10~8

2,20 x 10

-7

limite 5.10

limite 5.10

4,2 x 10"8

-9

-9

Incertitude

0,07x10"

0,04x10"

0,3xl0"4

0,2 x 10

0,002

0,05x10

0,06x10"

0,07x10"

0,06x10"

-6

0,4x10

0,2 X10~6

0,05xl0~

0,13x10"

0,7xl0~8

0,20xl0~

0,4xl0~

7

0,3xl0~

?

0,12x10"

0,06x10"

0,07x10"

0,2xl0"8

0,09 xlO~

0,7x10

78
Incertitude

208,0 7,97x 10 0,20xl0"6

221,5 4,26x

10" 7 0,14xl0~ 7

232,9 ^ 7 v ~1

n -8

D , JX 1U

U , 4x 1 (J 234,4

246,7 3,2x

10~8

0,5xl0~8

260,9

-9 7 x 10

-9

2x10 *

264,8 8,8

x

10~8

0,4xl0"8

267,5 2,40

x

10~ 7 0,08xl0~7

27i ,6 233 Pa

275,7 6,1

x

10~8

0,4

X 10"8

291,1 2,72

x

10~8 0,17

x 10"8

292,8 1,40

x

10~ 7 0,05xl0" 7

300,2 233 Pa

304,2

-9 9 x 10 2X 10

-9

(6)

311,9 233 Pa

322,5

—6

1,470

x 10 0,05x10

332,4 1,479

x

10"6 0,05xl0~6

335,4 4,75

x 10

-6

0,15xl0~6

337,7

340,4 233 Pa

350,5 1,47x

10~8 0,12xl0"8

358,2

-9

~i 6.10

368,6 2,08

x 10"6

0,06x 10~6

371,0 4,74

x 10" 7 0,15x 10" 7

376,6 1,283

x 10~ 6

0,04x 10" 6

383,7 2,76

x 10"7 0,09x 10"7

390,6 5,1

x 10~8

0,2xl0"8

406,4 1,6

x 10

-8

0,l

x10" 8

416,8 233 Pa

419,3 2,84

x 10~7 0,09

x 10" 7

426,5 2,36

x

10~7 0,08x 10~ 7

429,7 2,8

x 10~9

0,6xl0~9

440, 1

-9

limite 5.10

442,7 3,2x 10~ 8 0,2x 10" 8

452,0 2,6x 10" 8

0,3x 10"8

454,6 8,4

x

10~ 8 0,4xl0~8

459,6 2,7

x 10"8 0,2x 10~8

79
468,0 2,4

x 10~80,2x10 8

486,2 1,7

x

10~8

O.lxio"8

512,0 M.P. ± limite 1 .io- 8

514,2 3,2

x 10~ 8

0,4xl0~8

522,3 4,8

x

10~ 9 0,8xl0~9

574,0 1,4

x 10~ 8 0,lxl0

-8

582,6 M.P.

x limite 7 .lO" 9

586,7 4,7

x 10~9 0,8xl0~9

590,3 2,1

x

10~8 0,2xl0"8

597,4 6,7x

10" 8 0,3xl0"8

619,0 5,72x 10"7 0,19xl0"?

627,2 5,8x 10~ 9 l,0xl0"9

632,9 8,9x 10"9 l,lxl0~9

641,4 6,2x 10"8 0,2xl0

-8

652,9 3,53

x

10~7 0,12xl0"7

662,4 3,50

x

10"6

0,11 xl0~6

670,2 2,1x

10~8 0,3x10

675,5 1,16

x 10~80,07x10

680,0 3,6x

10~8

0,2xl0"8

688,7 2,84

x 10"7 0,09 xl0~7

693,4 3,4

x

10"8 0,2xl0~8

696,4 4,9

x 10

-8

0,3xl0~8

709,4 6,2

x

10"8 0,2xl0

-8

722,0 1,87

x

10~6 0,06xl0~6

729,3 1,04x 10~8

0,06x IO -8

731,4 4,5

x

10" 9 0,7xlO~9

737,2 7,6

x

10~8 0,3xl0~8

755,9 7,0

x 10" 8 0,3xl0"8

759,5 1,87x 10"8 0,09x 10"8

763,7 5 x 10 2:U0-

10

766,9 5,4

x

10~8 0,2xl0~8

770,5 5,4x 1Q~ 8 0,2xl0~8

772,3 9,5

x 10~ 9 l,0xl0~9

777,4

-9

1,1

x 10

-9

0,3x10

780,8 3,4

x 10~9 -9

0,5x10

786,6 limite 5.10~ 10

80
788,8

801,9

805,5

811,8

819,5

823,0

828,5

851,6

855,1

859,2

862,4

887,6

898,5

902,6

912,3

922,5

929,0

945,7

955,8

962,0

3,8

1,20

1.6 x 10

6,3 x 10

2.8 x

10"

1.9 x 10

1,9 x 10

4.7 x 10

-9

-9

1,9 x 10 * limite 5.1 "

7,0 x

10~"

-9

-9

-9

-9

-10

2,0 x 10

-\< 2xl0~

10

-9

2,5 x 10

^5x10

-9

1,2 x 10

'WxlO

-10

-9

^8x10

-10

4,9 x 10

^7x10" 10

-9

0,5x10

-9

-8

0,07x 10

0,3x 10~9

-9

-9

-9

-9

-9

-9

0,9x10

0,3x10

0,2x 10

0,2x10

0,7x10

0,2x10

0,8x10

0,4x10

-9

-9

0,3x10

-9

0,2x10

-9

0,8x10

-9

252

Cf

Tl l/2

2,639

periode

incertitude

0,030

unite reference

publication en

81
Liste des references utilisees pour l'etalonnage des spectrometres de photons

Radionucleide Periode Energie (keV) Probability

d' emission X ou y

Be

22 Na

24

Na

51 Cr

54.Mn

55 Fe

56

Co

57.Co

GOCo

53,17 +0,07 jours 477,605

2,602 +0,001 ans 1274,542

14,960 +_ 0,006 heures 1368,633

2754,030

27,703 + 0,OO4 jours 320,084

312,3 + 0,3 jours 834,843

2,68 +_ 0,02 ans E.moy 6,0(K

a ,K )

77, 12 + O, 10 jours 846,764

1037,844

1238,287

1360,206

1771,350

2015, 179

2034,759

2598,460

3009,596

3201 ,954

3253,417

3272,998

3451 ,154

3548,18

271,4 + 0,3 jours E.mov 6,5(K ,KQ ) — a p 14,4127

122,0614

136,4743

1173,238

1332,502

5,271 + 0,002 ans

0, 1035 + 0,0008

0,9995 + O,0003

0,99994 +_ 0, 00002

0,9987 +_ 0,0002

O,0983 +_ 0,0014

0,99876 +_ 0,00002

0, 277 +_ 0,020

0,99923 + 0,00007

0, 1409 + 0,0006

0,670 + 0,007

0,0426 + 0,0002

0, 1549 +_ 0,0005

0,0303 +_ 0,0004

0,0778 +_ 0,0012

0, 1695 +_ 0,0OO6

0,0106 + 0,0005

0,0318 +_ 0,0008

0,0764 + 0,0020

0,018 +_ O,001

0,0093 +_ 0,0003

0,0019 + 0,0001

0,565 + 0,020

0,091 + 0,002

0,8568 + 0,0013

0, 1067 + 0,0013

0,9989 + 0,0002

0,999830 + 0,000006

82
Periode Energie (keV) Probability

d' emission X ou y

243,9 +0,2 jours E.moy 8,1(K ,K)

a 3 0,387 + 0,009

1115, 546 0,5075 + 0,0010

64,85 + 0,02 jours E.moy 13,6(K ,K0 ) 0,591 + 0,008

514,009 0,9929 + 0,0004

106,62 + 0,03 jours 898,042 0,934 + 0,007

1836,063 0,9934 + 0,0007

35,05 + 0, lO Jours 765,800 0,9980 + 0,0002

39,265 + 0,010 jours 497,080 0,895 + 0,006

610,33 0,0564 + 0,0018

372,6 + 1,0 jours 511,860 0,205 + 0,005

463, 1+0,8 jours E.moy 23,3 (K Kn ) a 3

1 ,00 + 0,04

88,034 0,365 + 0,006

2,802 + 0,003 jours E.moy 23,8(Ka,K„

3 0,824 + 0,038

171,3 0,909 + 0,006

245,40 0,942 + 0,003

115, 10 + 0, 17 jours E.moy 24, 7 (K^, K^) 0,968 + 0,013

391 , 688 0,6489 + 0,0017

13,22 + 0,04 heures E.moy 28,0(K ,Kj

a 3 0,868 + 0,030

158,96 0,834 + 0,005

59,89 + 0, 15 jours E.moy 27,4 (K ) a

1 , 146 + 0,041

35,492 o nfifi7 + o 001 ~>, \*l ,

"—l U *~> I ' \J , UU 1 J

9,69 + 0,01 jours E.moy 30,4 (K ,K„) a 3 0,749 + 0,022

10,6 + 0,2 ans E.moy 30,85 (K ) a 0,982 + 0,040

E.moy 35, 1 (K_)

3 0,218 + 0,009

53, 156 0,0220 + 0,0006

79,623 0,0264 + 0,0012

80,998 0,343 + 0,006

223,234 0,00447 + 0,00020

276,397 0,0712 + 0,0007

302,845 0, 183 + 0,002

356,006 0,621 + 0,007

383,845 0,0892 + 0,0009

30, 18 + 0,O5 ans E.moy 32,9 (Ka K

g

) 0,069 + 0,004
Radionucleide Periode Energie (keV)

661 ,660

139

Ce

141 Ce

152 Eu

137,64 + 0,05 jours

32,50 + 0,04 jours

13,4 + 0, 1 ans

159.

Dy

203.

Hg

241 Am

144,4 +0,6 jours

46,585 + 0,008 jours

432,6 + 0,6 ans

E.moy 34,2(K ,K„)

ct D 165,857

E.moy 37,1 (K ,K0 ) a p 145,444

121 ,782

244,699)

251,76 . 295,939

344,281

367,788

411,115)

416,04 ) 443,99

564,021 ) 566,36 ( 688,678

773,903

867,388

963,48 ) 964, 131)

1085,914)

1089, 700

j

1112, 116

1212,950-

1292,86 ) 1299, 124)

1408,01

E.moy 45,5(K ,K ) a g E.moy 76,2(K

a ,K

g

) 279, 197

13,9 (L X)

26,344

59,537

Probability

d' emission X ou y

0,854 + O,008

0,798 + 0,026

0,799 + 0,001

0, 166 + 0,010

0,488 + 0,004

0,282 +_ 0,005

0,0742 +_ 0,0015

0,00423 +_ 0,00013

0,264 + 0,004

0,0084 + 0,0003

0,0230 +_ 0,0006

0,03076 + 0,00050

0,00,61 3 *+ 0,00034

O, 0084 9 + 0,00025

0, 1300 + 0,0022

0,0416 + 0,0006

0, 1446 +_ 0,0023

0, 1184 + 0,0025

0, 1355 + 0,0020

0,0139 j_ 0,0003

0,01743 + 0,00053

0,2070 + 0,0023

0,946 + 0,040

0, 130 + 0,004

0,814 + 0,002

O, 132 + 0,003

0,0235 + 0,0007

0,365 + 0,002

84
Nuclear Data for X- or Gamma-Ray Spectrometer Efficiency Calibrations

D.D. Hoppes, J.M.R. Hutchinson, F.J. Schima, and M.P. Unterweger

National Bureau of Standards, Washington, DC, U.S.A.

Abstract

Half-lives measured with reference ionization chambers are reported

for 22 Na> 24Na> 46 SCj 51 Crj 54M|% 5

7

Co ^ 58 Co ^ 59 Fe ^ 60 COj 65 ZPj 67 Ga>

75 Se, 85 Sr, 88Y, 99 Mo, 99mTc (two chemical forms), 109 Cd, 110mAg, mIn,

113 Snj 123 Is 125 Is 125 sb> 127 Xe , 131i, 131mXej 133 Xe , 133 Baj 134 Cs>

137 Cs , 13 9 Ce, 140 Ba , 140La , 141 Cej 144 Cej 152 EUj 153Gd> 154 EUj 155 EUj

169Ybj 181 Wj 192 Irj 195AU} 198AlJ} 201 T1 f 203 Hg , 203 Pbj 207 Bij and 228 T1 . Gamma-ray probabilities per decay measured with calibrated germanium

spectrometry systems are given for , 99 Mo, 125 Sb, ^l, 154 Eu, and

The gamma-ray to K-x-ray emission-rate ratio for 109 Cd and the

gamma-ray probabliity per decay for 241 Am as meaS ured with Nal(Tl)

systems of known efficiency are given.

1. Introduction

Instruments used in the preparation of radioactivity standard reference

materials are also useful for measuring some of the data required for

accurate efficiency calibrations of x- or gamma-ray spectrometry systems.

Three types of such data are discussed in this contribution: half-lives

measured by observation of the activity over a period of time, gamma-ray

probabilities per decay measured with germanium spectrometers, and x- or gamma-ray probabilities measured with def ined-geometry systems.

The ionization chambers which serve as a repository for the calibrations of

gamma-ray-emitting radionuclides at the National Bureau of Standards (NBS)

have been routinely used to follow the decay of most such radionuclides used

in the production of Standard Reference Materials or in the calibration of

local laboratory counting systems. Deviation of the measured half-lives from

tabulated values indicates that a significant additional uncertainty must be

attached to standards after appreciable decay.

85
The ionization chambers used are not sensitive to low-energy radiations and

other instruments must be used for checking half-lives in such cases. For

example, a half-life of 1009.0 + 1.7 days was measured for 55pe> with proportional and Si (Li) detectors.

Calibrated germanium spectrometer systems are used for impurity searches, the

calibration of submitted samples containing more than one gamma-ray-emitting

radionuclide, and for a final check of all photon-emitting standards. They also

are used for confirming or revising gamma-ray probabilities per decay by direct

measurement with samples of known activity.

Photon counting systems for which efficiencies are defined by geometrical limits are used to directly measure x- or gamma-ray emission rates of standards of lowenergy photons. With suitable precautions to minimize scattering and source absorption, the measurement of sources of known activity gives probabilities

per decay with an accuracy greater than that which can be calculated from available decay scheme data.

Results from the three types of measurement will be discussed in the order

given above. In all cases the component uncertainties have been calculated or estimated at a level corresponding to the standard deviation of the mean for

repetitive measurements, and have been combined quadratical ly to give an overall uncertainty.

2. Hal f-1 i fe measurements

Well-type ionization chambers, filled with 20 atmospheres of argon, are used

for the half-life measurements. The majority of the measurements were made with

a 2.5-cm-di ameter well chamber in use since 1967. Measurements with newer 2.5-

and 5-cm-di ameter well chambers are included in the results for ^Sc, ^Se, 125^

127 Xe, l69 Yb, and 181 W. All decay data are taken relative to 228Ra reference

sources, assuming a half-life of 1600 + 7 years. A typical data point has a standard error (standard deviation of the mean) of 0.01 to 0.06 percent, derived from

10 sample and 20 reference source readings.

86
The calibration factors for various radionuclides on the older chamber have been

checked periodically by direct activity determinations, and no indications of

change, within the measurement uncertainties, have been found. All sources are of

an activity well below the level where saturation effects have been observed.

The radium reference sources were prepared from material old enough for longlived daughters to be in equilibrium; checks with germanium spectrometers showed

no evidence of 228r 3j which would have perturbed the reference decay calculations.

In some cases, impurities are a significant source of systematic uncertainty. All sources have been investigated with germanium spectrometer systems, and the decay

data have been corrected for any impurities found. If, for a given radionuclide,

only the material from one separation has been used in determining the half-life,

an estimate of the uncertainty due to the impurity effects has been added in quadrature to the uncertainty derived from repeated counts.

In most cases, the half-life reported is the weighted average of the results from

different batches of the radionuclide, prepared and measured at various times over

14 years. The uncertainty is the "external error" in the weighted mean value. The

weights used are the reciprocal squares of the standard errors in the fitting of

the data to an exponential function (or sum of exponentials, if impurities are present), multiplied by the goodness of fit, if greater than 1. The data are fitted by x

2

- minimization and the goodness of fit is defined as the square root of

X

2 divided by the number of degrees of freedom. Using a technique suggested by

Stevenson(l) to estimate possible variations among replicate samples not due to

the expected distribution variations, but to other noncommon variations (i.e., inexact impurity estimates, chemical instabilities, density changes), we add the following- uncertainty (if greater than zero) in quadrature:

cr 1

2

(k - 1)

k

va r (x^)

»

where k is the number of results averaged.

87
When following a long-lived radionuclide, at high precision and with a large num- ber of data points, the uncertainties estimated from the fitted data appear to be

underestimated when the time span is small compared to the half-life. In other

words, the fitted values, as points are added, fluctuate more than the individual

fitting uncertainties would indicate. For example, for a source of 207g -j t ne fitted

value is 32.9 + 0.1 years after being followed 0.152 half-lives (n=57) and 32.25 +

0.06 after 0.28 half-lives (n=87). This observation would seem to indicate that the

uncertainties quoted for the half-lives of long-lived radionuclides may often be

seriously underestimated.

Table I lists the radionuclides for which the half-lives have been determined. In most cases, as indicated in Column II by a range for the number of half-lives followed, a number of sources from different preparations and different 226r 3 refer- ence sources have been used to follow the decay of the radionuclide. The half-life

values are given in Column III. The stated uncertainties are the sum, in quadrature,

of the statistical and systematic uncertainties. Column IV gives the "external er- ror" in the weighted mean value. Column V shows the remaining uncertainty calculated

from the Stevenson equation given above. Column VI shows the uncertainty due to the

effect of impurities when only one batch of material has been measured. Column VII

gives a possible uncertainty due to the relatively short fraction of a half-life

that a radionuclide has been followed. This last uncertainty is not included in the

overall uncertainty in column III, but is shown as a warning that the apparent un- certainty may be optimistic.

3. Gamma -ray probabil ities per decay measured with germanium spectrometers

Other duties have prevented re-examination of much of the germanium-spectrometersystem data taken before 1979. Results which should be modified are not included.

This includes all data for energies below 120 keV.

The general features of the systems and analysis have been published (2,3) # Efficiency calibrations of the two systems described in Table 2 use only gamma-rayemission rates which can be inferred from decay-scheme data without significant use

of past spectrometric results.

88
All germanium detectors that we have studied, including those in Table 2, have

shown important efficiency changes with time. Variations observed for detector

2 during a 2- year period are shown in figure 1. The observed change in the

counting rate of several gamma rays from a source of 152fr u nas b een use(j t0

correct for the efficiency changes at different energies. A half-life of 13.5 + 0.2 years was assumed.

Table 3 gives the component and total uncertainties estimated for the calibration efficiencies. The estimates, other than the standard deviation of the

mean, are based on the propagation of given uncertainties (Py, activity, halflife) or the influence of variation of parameters (pile-up, peak analysis, efficiency changes, geometry). Most calibrations are based on at least three

sources of different activity, measured over a 3-year period and corrected for observed efficiency changes. Fractional losses due to pile-up, as measured by

losses from a constant-f requency-pul ser peak, are in general less than 3 percent,

and have been shown to be a linear function of total count rate. Geometry variations considered include positioning, source diameter, and source absorption.

Many of these component uncertainties are thus included to some extent in the

measured standard deviation of the mean. Although the overall uncertainty is

given to two figures, in general only one is significant.

The efficiencies have been corrected for losses from the simultaneous detection

of cascade radiations. Angular dependences were taken into account. The maximum

correction was 0.31 percent, and the uncertainty in the correction is taken as being negligble.

Although the efficiency points are numerous, the rapid and essentially unpredictable dependence of the efficiency on energy makes necessary a reliable

interpolation function in order to apply the results. We divide the measured

points for each detector into three overlapping energy regions, and fit the

natural logarithm of the efficiency against a polynomial in the energy for

each energy region. The results are shown in Tables 4a and 4b. The deviations

from the fitted functions are in reasonable agreement with the uncertainties

assigned. There are small, but significant, departures from the calculated dependence in some regions; corrections to the fitted curve have been made for

a few of the measured gamma rays.

89
The data analysis used for the measurement of unknown gamma- ray -emi ssion rates

is similar to that used for the detector calibrations, with interpolated efficiency values at a selected energy corrected for the observed change in that

energy region at the time of measurement. Again sources of different activity

are measured repeatedly, and uncertainties assigned from observed variation in

values with changed parameters.

The gamma-ray probabl i 1 i ties measured for selected gamma rays from the decay of

88Y, "Mo, 125Sb, 131 I, 154Eu, and 228Th are given in Table 5. The uncertainties are also given in Table 5. Activities were measured with thin sources in

a pressurized proportional counter, in coincidence or anticoincidence with ex- ternal Nal(Tl) spectrometers, for the first five radionuclides. Efficiency extrapo

lation techniques were used to derive activities essentially independent of decayscheme data. 1255(3 SOurces were measured soon after the chemical separation of

the I25mye daughter (60 day half-life). The 228-^ activity was measured with alphaparticle counters of known efficiency; comparison of the apparent efficiency for

the 2614.5-keV gamma ray in the subsequent 208j] deC ay with that measured with sources of known retention of radon led to a correction of about 1.5 percent for

radon loss in the sources used in the gamma-ray measurements.

3. Measurements with def ined-geometry systems

The 59.5-keV gamma-ray probabl ility in the the decay of 241^m was measured as 0.3582 + 0.0014 with a specially constructed Nal(Tl) detector with a very thinwalled well, for the gamma-ray measurement, and the NBS 0.8tt a-particle detector

for the activity measurement. The gamma-ray measurement was carried out in

essentially 4tt geometry and total corrections of approximately 5 percent were made for iodine K-x-ray escape, wall absorption, escape through the well ends,

and other smaller effects.

The ratio of emitted K x rays (22 to 25 keV) divided by emitted 88-kev gamma rays

in the decay of l°9cd has been determined to be 27.34+0.27.

The x-ray measurement was performed with the defined-solid-angle low-energy-photon

detector described in Hutchinson et al(4). where the techniques used to minimize

scattering are discussed. A platinum diaphragm with an accurately known aperature

90
was used to define the subtended solid angle of the K x rays from the source into

the Nal(Tl) crystal. Cadmium-109 sources were measured at known distances from

the diaphragm, and calculated solid-angle and other correction were applied to

the measured count rates to obtain the emission rates. Results for sources mounted

on three shelves at source-to-detector distances of 2, 4, and 8 inches agreed to

within 0.2 percent. Total corrections for other than solid angle amounted to about

1 percent.

The 109Q<j 88-keV gamma rays were measured with a "pin-well" detector previously described^). A dried source contained in a "bag" made from thin polyester film was inserted into the thin-walled well. Corrections totalling less than 2 percent were

applied to the counting rate from loss through the end of the well, absorption in

the well wall, and accidentally summed pulses falling into the 88-keV region.

91
References

1) P. C. Stevenson, "Processing of Counting Data", NAS-NS 3109, 98, 1965

2) A. T. Hirshfeld, D. D. Hoppes, and F. J. Schima, Germanium Detector

Efficiency Calibration with NBS Standards, in Proceedings of ERDA

Symposium on X- and Gamma-Ray Sources and Applications , NTIS

CONF-760539, 90, 1976.

3) F. J. Schima, D. D. Hoppes, and A. T. Hirshfeld, An Accurate On-Line

Method for the Evaluation of Peak Areas in Pulse-Height-Analyzer Data

in Computers in Activation Analysis and Gamma-Ray Spectroscopy , CONF-780421, 177, 1979.

4) J. M. R. Hutchinson, W. B. Mann, and P. A. Mullen, Development of

the NBS Low-Energy-Photon-Emission-Rate Radioactivity Standards, in

Proceedings of ERDA Symposium on X- and Gamma-Ray Sources and

Applications , NTIS CONF-760539, 25, 1976.

5) J. M. R. Hutchinson and S. B. Garfinkel, IJARI 22, 405, 1971.

92
TABLE 1

Half-Lives Measured With Ionization Chambers

Number ot Uncertainty Uncertainty

Radio- half lives Statistical Uncertainty due to due to mea- nuclide followed Half life(l) Uncertainty from EQN (1) Impurities surement time

22Na 4.6-5.2 (2 .6057 o 0003) y o 0002 o 0003

24Na 1-7.5 (1 4.951 o 003) h o 0009 0 0031 46Sc 1 .6-4.3 (83.79 g 06) d o 02 g 06

51 Cr 2-8 (27.73 o 01 ) d o 005 g 01 0 54Mn 2-7 '31 2.02 ± o 04) d o 04 g g 57 Co 3.6-6 (271 .9 o Q o 06 g 1 3 0.1 4 58Co 9 (70.75 o 07) d o 05 g g 0.05

59 Fe 4-9 (44.507 0 007) d o 005 g 005

60 Co 1-2.4 (5.282 o 007) y o 003 g 006

65Zn 3.2 (244.2 o 1 ) d o 1 0 g 67Ga 2-8 (3.261 o 001 ) d o 0005 g 001 3 75 Se 1 -6 (1 1 9.80 o 07) d o 02 g 07

8 5 Sr 1 -4.8 (64.851 o 006) d o 004 0 005

88 Y 1 -4.6 (1 06.64 o 05) d o 02 g j. 99Mo 3-9.5 (65.924 o 006) h o 003 g 005

99mTc (2) 2-12 (6.0072 o 0009) h o 0001 6 g 00086

99mTc (3) 1 -8 (6.01

7

0 002) h o 0004 0 001 5 109Cd 3.4-5.3 (463.2 o 6) d o 3 o 5 110mAq 9.5 (249.93 + 0 06) d 0 023 g 0 lllln 1 .5-9.3 (2.8048 + 0 0005) d 0 0002 0 0005

l 13Sn 2.3-11 (1 1 5.06 + 0 07) d 0 02 o 07 123! 9-1 2.7 (1 3.21

9

+ 0 007) h o 005 g g 0.005

125! 1-3 (59.47 0 21 ) d 0 04 g 05 0.2

125sb 0.1-0.2 (2.75 0 02) y 0 02 g g 0.06

127 Xe 1 -6 (36.34 0 01 ) d 0 008 g 01 131; 1 -1

1

(8.020 0 002) d 0 0005 g 002 131m Xe 1 .8 (1 1 .93 0 02) d 0 01 g 02 133 Xe < 4 > 3-7 (5.245 0 006) d 0 003 g 0 0.003

133 Ba 0.2-0.3 (1 0.48 o 03) y o 02 g 02 0.07 134Cs 1-1.7 (2.0649 o 0004) y 0 0004 g 0 137 Cs .26- .43 (30.68 o 02) y o 02 g n 0.04

139Ce 1 .5-6.4 (1 37 .74 o 08) d o 03 g 08 140Ba 2-4.4 (1 2.753 o 002) d o 0009 g 002

140La 4.2 (1 .6783 o 0007) d o 0003 g 0003 0.0005

141 Ce 5 (32.52 o 03) d o 007 g g 0.03

144Ce 3-7 .5 (284.9 o SI d o 22 g 4 152Eu . 1 - .4 (1 3.57 o 1i ]1 \ V 1 y o 05 0 1 0 0.24

153Gd 5.9-6.0 (239.63 + 0 04) d 0 03 0 03 154Eu 0.14 (8.49 + 0 ii) y 0 11 0 0 0.008 0.35

155Eu 0.2-0.4 (4.73 + 0 02) y 0 01 0 Q2 0.01 0.04

169 Yb 2-9 (32.02 + 0 01) d 0 004 0 013

181 W 1-3 (121 .1 0 6) d 0 2 0 5 192 Ir 2.4 (73.81 + 0 07) d 0 02 0 0 0.07

19 5Au 4.5-7.4 (186.09 + 0 04) d 0 02 0 03

l 9 8Au 4.5-7.5 (2.695 + 0 002) d 0 0002 0 0 0.002

201 T1 2.6-1

1

(3.0447 + 0 0009) d 0 0003 0 0008

2 °3Hq 1 .7-6.6 (46.62 0 03) d 0 007 0 026 203pb 1 .8-2.8 (51 .92 + 0 04) h 0 01 3 0 034

207 Bi 0.3 (32.23 + 0 04) y 0 04 0 0 0.9 228Th 1-5 (698.1 ± 0 5) d 0 17 0 48

(1 ) 1 year = 365.2422 days

(2) Sal ine solution

(3) 3 N HC1 solution

(4) Uncertainties added linearly.

Phys. Rev. C10 2631 (1974)

(5) Not includedTn overall uncertainty
Table 2

Description of Germanium Detectors

Detector # 1

Type

Approximate

Volume (cm^)

Resolution in keV,

at 122 keV

at 1332 keV

Source distance (cm)

Location method

coaxial Ge(Li)

30

0.90

1.72

25

vertical plastic

spacer

wraparound

coaxial Ge(Li)

60

0.80

1.77

26.2

two telescopes referenced

to a horizontal removable

fi xture.

Cryostat window 0.5mm Al 0.5mm Al

94
cm

s-o

---> <_> QJ +J

QJ Q

Co

+-> (O

s- -Q CO

Ol (O

c_> J3 • (0 >>

t— O

Ol

•I—u

4—

UJ

4-o

to

CO

+-> Q

r— i

i— ra

03 +>

S- SCD > u o c

n>

>i

5- +J

CDEO

CD C3CM

CO

+-> £Z r—

0)o

Q. >- E Q. O

<_> >i >>

+-> -P c

•r- >

(0 +J

S- O

o> <t oO >>o

c o>

re cu cn o C

•i

u ra Q_ Jd >> 4- O

I— Ef

—

"rt3 >)

CD p

D_ rac

<c c

1 10 3 l/l c e

<D CD o

i

cxE +j oo

>

CD T3 JZ e

+J ro

0) o 4- E

o

00

1 (O

S- c i/> OJ c

-O 4— E o E o 5-CU 4-> +J

CD T3

>- D_

a>

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95
1ABLE 4A

FITTING

LOG (EFT) = A< RESULTS FOR DE I ECTOR 1 . 3)/E*E*E + A(-2)/£*E + A(

+ A(O) + A ( 1 ) + E

I ) /£

GOODNESS OF FIT = 0.97915 1 E 0

A ( - 3 ) = 0 . 285 7 1 7 E 7 + , - 3 20(313.

A(- 2 ) = -871 50 . 9 + 7949.46

A ( - 1 ) = 869 .717 + , - 6 7.8377

A ( 0 ) = -10.0116 + ,- 0.236949

A ( 1 ) = -0.159864E -3 + , - 0 .281 965 E -; 5 H H ENERGY OKS EFF CALC EFT 7. RE SI DUAL

1 88. 037 0 .000743700000 0 .000743718312 -0 .0025

2 122 063 0 .000758000000 0 . 000758453439 -0 . OS 98

3 1 40. 479 0 .000728000000 0 .0007 2 55 7 6594 0 .3340

4 165. 853 0 .000652400000 0 .000651 509324 0 . 1 36?

5 171. 280 0 .000629800000 0 . 00063409623 2 -0 .6775

A 245. 390 0 .0004 2 7 900000 0 .000426228273 0 . 3922

279 . 188 0 . 000358300000 0 .000360 5 5 8481 -0 .6264

8 364 . 480 0 .000253500000 0 .00025336 1 270 0 .0548

9 411. 795 0 . 00021 4700000 0 .000 216 3 90151 -0 . 781 I

1 0 433 . 927 0 .000203460000 0 .000202545751 0 .4514

GOODNESS OF FIT = 0.101513E 1

A ( -2 ) = -87597.7 + , - 6632 . 1 8 A < - 1 ) = 881.622 + , - 24.0020

A< 0) = -9.90949 + , - 0.254646E -1

A < 1 ) = -0.378480E - 3 + ,- 0.771 621 E -5

1 « ENERGY OBS EFF CALC EFF 5 RESIDUAL

1 4 1 1 . 7 9 5 0 .000214700000 0 .000215835852 -0 . 5 26 3 2 433 9 y 0 .000203460000 0 .000202005835 0 . 71 99

3 569 .685 0 . 00 01 43800000 0 .000143747019 0 . 0 36?

4 604 .699 0 .000132800000 0 .00013369 3 089 -0. 6680

5 61 4 .370 0 .0001 31 600000 0 .00013116 0142 0 . 3354

6 661 .645 0 .0 001 19800000 0 .0001 20057871 -0 . 2148

7 702 .627 0 .000112430000 0 .0001 1 1877632 0 . 4937

8 722 .950 0 .000108510000 0 .00010 8231990 0. 2569

V 834 .825 0 .00 0 0914 9 0000 0 .0000918 7 4415 ~0 . 41 84

1 0 871 .099 0 .000088130000 0 .000087616352 0. 5862

1 1 889 .250 0 .0000356 300 0 0 0 . 00008563587

1

-0 . 0068

1 2 1 1 20 .510 0 .000066830000 0 .000066617432 0 . 3 191

1 3 1173 .208 0 .000063930000 0 .000063421 730 0 . 8 0 14

1 4 12 74 .540 0 .000058110000 0 .000058057098 0 . 091 1

1 5 13 3 2 .470 0 . 0 0 0 0 5 5 7 5 0 0 0 0 0 .000055 3 6 8766 0. 6885

1 6 1368 . 5 3 0 0 . 000054200 0 0 0 0 .000053812161 0 . 7207

1 ? 1 59 6 .490 0 .00004561000 0 0 .000045587740 0 . 0488

1 B 1 8 3 6 .040 0 . 000 0 3 8 9 5 0 0 0 0 0 .000039068159 -0 . 3024

1 9 2 3 18 .900 0 .0000 2 9 750000 0 . 0000 2 9 7 3 31 96 0 . 0565

20 2614 .600 0 .0000 2 5 6 0 0 000 0 .000025554828 0 . I 76 8 21 2754 . 090 0 .000024020000 0 . 000023860373 0 . 6690

96
FABLE 4B

KITTING

LOG(EFF) = A< RESULTS FOR DETECTOR 2. 3)/E*E*E + A<~2)/E*E + A<-1)/E

+ A < 0 ) f A( 1 )*E

GOODNESS OF FIT * 0.990432E 0

A < - 3 ) 0.211960E 7 + 330160.

A<-2) -46457.3 + ,- 8133.78

A ( - 1 ) 669.481 + 68.7024

A ( 0 ) -8.84039 + ,- 0.237333

A ( 1 ) -0.532320E -3 + 0.281387E -3

'T « ENERGY OBS EFF CALC EFF X RESIDUAL

1 88 .037 0. 001 169400000 0 .001 1 6985351

6

-0 , .0388

2 1 22 .063 0. 001214500000 0 .00121 1874944 0 ,2166

3 1 40 .479 0 . 001 171500000 0 .001 167969138 0 ,3023

4 1 65 .853 0 . 001066400000 0 .001066393095 0 ,0006

u 1 7 1 .280 0. 001038200000 0 .001042259975 -0 , .3895

6 245 .390 0. 000747000000 0 .000744363634 0 ,354 2

"j 279 . 1 88 0. 000640800000 0 .0006450041 21 -0 , ,6518

8 364 .480 0 . 000471 400000 0 .0004741 06043 -0,.5708

9 41 1 .795 0 , 000413100000 0 .00041 1631512 0,.3567

1 0 433 .927 0 . 000389700000 0 .000387590545 0 ,5442

GOODNESS OF FIT = 0.710940E 0

A (-2) = -10105.3 +,- 52385.7

A<-1) - 442.650 + 267.800

A< 0) = -8.54350 + ,- 0.438915

A( 1) = -0.634197E -3+,- 0.231151E -3

PI tt ENERGY

1 411 .795

2 433.927

3 569.685

4 604.699

5 614.370

6 661.645

7 702.627

8 722.950

9 834.827

10 871.099

11 889.250

OBS EFF 0.000413100000

0 .000389700000

0.000286700000

0 .000267600000

0 .000264200000

0 .000245200000

0 .000230 I 00000

0.000223100000

0.000191730000

0.000185140000

0 .0001 79760000

CALC EFF

0 .00041 41 32425

0.000388871 141

0 .0002861 70486

0.00026851 1099

0 .000264039634

0.000244282893

0 .000229505979

0 .000222842469

0.000192153519

0 .0001 83900530

0.000180016704

X RESIDUAL

-0.2493

0.2131

0. 1850

-0.3393

0.0607

0.3754

0 . 2588

0 . 1 1 56

-0 . 2204

0 .6740

-0.1426

GOODNESS OF FIT 0.605105E 0

A<-2) = -165323. +,- 44431.6

A(-1) = 976.674 + 99.2687

A< 0) = -9.21731 +,- 0.682483E -1 A( 1) = -0. 32901 5E -3+,- 0.144856E -4

PT « ENERGY

1 834 .827

2 871 .099

3 889 .250

4 1 1 20 .510

5 1 1 73 . 208

6 1 274 .540

1 332 .470

8 1 368 .530

9 1 596 .490

1 0 1 836 .040

1 1 2614 .600

1 2 2754 .090

OBS EFF 0.000191730000

0.000185140000

0.000179760000

0 .0001 43580000

0.000137880000

0 .0001 27080000

0.000121610000

0 .0001 1 8820000

0.000101250000

0.000087950000

0 .000059550000

0.000056010000

CALC EFF

0 .0001 91 756498

0.000183997367

0.000180344235

0.000143953887

0 .0001 37629602

0.000126897483

0.000121469265

0.0001 18312064

0.000101476668

0 .000087971 888

0 .000059579866

0.000055974237

X RESIDUAL

-0.0138

0.6210

-0.3240

-0.2597

0.1819

0 . 1 438

0. 1 159

0 .4293

-0 . 2234

-0.0249

-0.0501

0.0638

97
Table 5

Radionuclide Energy (keV) Photon probability Uncertainty

per decay, % in last digit

88

y

"Mo

125 Sb*

131

j

154

Eu

228

Th

898.0 94,3

140.5 90.3 10

181.1 6.00 5 739.4 12.06 9

777.8 4.25 3

176.4 6.68 4

427.9 28.78 18

600.6 17.18 10

606.7 4.88 3 635.9 10.91 7 671.4 lo80 2

284.3 6o21 4

637.0 7.11 4

722.9 1.78 1

123.1 40.8 3

248.0 6.91 4

591.7 4.95 3 723.3 20.08 12

873.2 12.19 9

1004.8 18.08 11 1274.4 34.84 17

277.4 2.34 4

300.1 3.28 3

583.2 30.7 3 727.3 6.67 6

860.5 4.55 4

These values are based on preliminary activity measurements which are currently

being checked, hence only relative values are quoted in the summary table.

98
ENERGY, keV

03

o

CD

ro CO

OJ

%

1>

o

o

roO

CO

cn o

o

o

o

ro

8c*

OJ Iso

o

o

o

o

roO

CD

OJ h~

O

O

^ ° 7 ^o 7 - o T

EFFICIENCY CHANGES, %

99
National Physical Laboratory

Division of Radiation Science

Teddington, Middlesex TW111 OLW

United Kingdom

Peter Christmas

Hal f -Li ves

Many half-life values shown in the summary table have been checked in use since the original measurements (referenced in the table), and no discrepancies

have been observed. Eight previously unpublished values, all with uncertainties

at the "one sigma" level, are included.

Electron Measurements

The iron-free, double-focussing beta-ray spectrometer at NPL has been used by

P. Christmas and P. Cross to measure PY (662) following the decay of 1-^Cs. A value of (84.56 + 0.09) percent was published in Metrologia 14, 157 (1978), but

a further, and continuing, investigation of the influence of~~b~eta-ray spectral

shapes suggests that this value may be revised.

The authors have used the same instrument for relative conversion-electron mea- surements in the decay of 180m Hf [nuc i. instrum. Methods ^74, 571 (1980)]. The

measured ratios are used, together with theoretical conversion coefficents, to

derive the relative gamma-ray probabilities shown in the summary table.

P X (K) Measurement

Measurements of K x-ray emission rates in an internal-source pressurized proportional counter, combined with activity measurements by 4 (A,x)- gamma-ray

coincidence counting, gave a value of (58.66 + 0.41) percent for P

X (K) in the

decay of 85Sr, as reported by D.J. Thomas in Z. Physik A289, 51 (1978).

100
Decay data of radionuclides used for the calibration of

germanium detectors

by

K. Debertin, U. Schotzig and K. F. Walz

Physikalisch-Technische Bundesanstalt

Braunschweig, Fed. Rep. of Germany

December 197 9

Contribution to ICRM action 10/7 9

Summary:

Results for gamma-ray emission probabilities of 1 2 radionuclides

and for half -lives of 18 radionuclides are summarized. Most of

the data were obtained within the last five years. The selected

radionuclides are suitable for the efficiency calibration

of Ge(Li) and high purity germanium detectors.

i

101
Part I: Photon emission probabilities

1.1. Introduction

Photon emission probabilities of many radionuclides have been

determined over the last five years in the Phys ikalisch-Technische

Bundesanstalt by means of three accurately calibrated germanium

spectrometers. The nuclides considered in the past can be

divided into three groups:

1. fission product nuclides;

2. nuclides of interest in nuclear medicine;

3. nuclides which are used for the efficiency

calibration of germanium spectrometers

In Part I of this paper we summarize the results obtained for 1

nuclides of the third group. When calibrating a spectrometer we

differentiate between "primary" and "secondary" calibration lines.

The term "primary" is used here

1 . if the activity of the source has been determined

fundamentally by accurate absolute measurements,

like 4tt ;

, -coincidence counting and

2. if the determination of the photon emission probability

is not or not solely based on measurements with germanium

detectors and if p is known with good accuracy.

Examples for primary calibration lines are given in Table 2.

Other calibration lines which do not fulfil both conditions given

above are called "secondary".

An efficiency calibration with primary lines of many calibration

sources may be very time-consuming. Moreover, it may be difficult

to obtain or produce the sources which in part are short-lived.

It has therefore become common practice to use only one or a few calibration sources of long-lived nuclides emitting photons

of several energies in the region of interest. In that case most

lines are secondary lines. Gamma-ray emission probabilities of

such nuclides are determined by means of germanium detectors

which were calibrated by using primary lines. All lines for which

experimental results for p are given in this report are secondary

102
calibration lines.

We do not give much detail on the experimental set-up, the

efficiency calibration and the evaluation of our measurements,

because this is contained in other publications quoted later on. We also do not discuss our results for the gamma-ray emission

probabilities and we do not compare them with those of other

authors. This report is just a summary of our work, most of which

has been published in individual reports and papers.

1.2. Experimental set-up

Specifications of the detectors used in our three spectrometers

G1 , G2 and G3 are given in Table 1 . For measurements with G3

at energies below 122 keV lead or tantalum collimators (3 or 2 mm

thick, 10 mm hole) are inserted near the source and detector.

Table 1 Detector specifications

Spectrometer G1 G2 G3

Type

Supplier

Date of delivery

High voltage

Volume

FWHM

Source to detector

distance

Ge(Li)

true coaxial

Canberra

June 1969

- 1400 V

30 cm"

Ge(Li)

coaxial , one

end open

Canberra

Oct. 1973 + 2900 V

3 70 an

2.9 keV at 1.33 MeV 2.2 keV at 1.33 MsV

16.5 cm 16.5 cm

HPGe

planar

PGT

Oct. 1973

- 1500 V

2 area 200 nm

depth 5 mm

208 eV at 5.9 keV

520 eV at 122 keV

6.2 cm

Used energy range 122 - 2754 keV 122 - 2754 keV 5-412 keV

After amplification in the preamplifier (CI 1408 C, CI 970,

PGT P012/B), amplifier (CI 1413, CI 2010), and biased amplifier/

(CI 1467) the pulses are fed into a 4096 channel pulse height ana- lyzer (ND 2400, Northern 720, CI 8180). Data are printed out on

103
paper or magnetic tape and evaluated by our central CGK computer

TR 440. Pulses of a periodic 50 Hz pulse generator ( BNC BH1

or PB-4 triggered by PTB 7401) are added at the input of the

preamplifier

.

1.3. Peak evaluation, corrections

The number of counts in the gamma-ray and pulser peaks of the

4 spectra are determined by our computer program GELI . ) Losses

due to dead- time and pile-up effects are corrected by using the

2 6 8 1 6 pulser method ' ' '

) . Coincidence summing corrections are calcu4 1 1 lated by the program KORSUM '

) . The program GELIMI averages

results of several runs within a measuring series ( combines the output information of GELI and KORSUM, and calculates either the peak

efficiency of the spectrometer system from the emission rate of

the calibration sources or the gamma-ray emission probability from

the efficiency and the source activity A.

1.4. Efficiency calibration

The efficiency £. at an energy E^ is obtained from ^ (E } = N(E ± ) • C(Ei)

1 rTe~)

with NCE^) number of counts in the peak corresponding

to the energy E^

C(E^) factor accounting for all necessary

R(E . ) = A • p(E .

corrections

emission rate of calibration source

A activity of the source

p(E^) emission probability for photons of

energy E^

Primary photon lines used for the calibration of our detectors are listed in Table 2. The efficiency curves are given in several

publications^ ' ^ ' ^ °' ^

1 ^ ) . Interpolation between the calibration

points is performed either manually or by fitting an analytical

function. Table 3 gives estimates of the relative uncertainties

(68 % confidence level) reached for our spectrometers. The figures

have to be considered as pessimistic estimates, the uncertainties

may even be smaller in the neighbourhood of calibration points.

104
Table 2 Primary calibration lines

Most of the data are taken from a contribution of M.J. Martin

to NCRP Report No. 58 30

)

Nuclide Half-life Energy

in keV

Emission

probability

22

24 Na

Na

46

5154

57

Sc

Cr

Mn

Co

58Co

60Co

65

85 Zn

Sr

88,

95ft

111?

C

In

125.

131

134 Cs

1 37

Cs

139 Ce

180^

1 40

1 80

1 98

203

207

241

La„

Hj

Au

Hg

Bi

Am

950.4 d

1 5 .00 h

83.80 d

27.705 d

312.5 d

272 d

70.78 d

5.272 a

243. 97 d

64.85 d

106.64 d

35.0 d

6.006 h

2.802 d

60. 1 4 d

8.02 d

2.062 a 30.0 a

1 37 . 65 d

40.272 h

5.5 h

2.696 d

46.59 d

32.49 a 432.0 a

1 274 .

1 368,

2754,

889,

1 1 20

4

5,

834,

1 4

1 22,

6 810,

1173

1 332

8

1 3 51 4,

1 4

1 836

765

1 40

23,

171

245

27

364

604

795

32,

661 , 33

165

1 596

21 5 332

411

72

279

74

59

(K

(a

542

633

030

277

545

95 (K ) 41 (K ) 843 a 4147

061 4 40 (K ) 775 a 237

501

04

37

009

1 4 064

800

509

1 1 28

39

38

480

699

845

06

6 60

30

857

49

251

307

8044

1 <K a

) 1967

537 a

(K

(K

(K ) a

99940(20)

99863 (5)

1 970 (45)

2213(45)

0. 999760(2)

0.0954 (13)

8559 ( 1 9)

231 8(45)

99450(10)

99900(20)

0

o

o

0

1

0.3410(58)

0. 5010(81 ) 980(10)

51 5 ( 1 6)

9944 (2)

9980(4)

8896 (24)

0.678(1 8)

0. 9093 (22)

9417 (1 1 )

1 40(29)

81 6 (6)

976 ( 1 ) 853 (9)

0548 ( 1 1

3456 (0)

657 (1 6)

800(2)

9540(8)

81 70

9447

9547 (8)

1011 (19)

81 3 (2)

588 (1 5)

360(3)

105
Table 3 Estimates of the uncertainty of the efficiency calibration

Spectrometer Energy region Uncertainty

in keV in % G3 5-20 1.5

20 - 70 1 .0

70 - 1 10 1.5

1 1 0 - 1 80 0.7

1 80 - 4 1 1 1.0

G1 , G2 1 22 - 250 1 .0

250 - 550 0.7

550 - 1400 0.5

1 400 - 1 900 0.7

1 900 - 2754 1 .5

1 . 5 Results for photon emission probabilities

Photon emission probabilities per decay were obtained

according to

p(E) = N(E) * C(E)

A • t(E)

(cf. section 1.4). For all nuclides except ^^Eu and 22<^Ra

activities were determined by 4"R"ft-/ or 4TX-Y coincidence counting

13 3' Details can be found in reference 9 for Ba and in reference 1

5

for 75 Se and 182

Ta. For 110Ag

m

, 1 52Eu and 1 82Ta 4tf\ -counting with

1517 2 26 a Nal(Tl) detector system was applied ' ) . In the case of Ra

emission probabilities per decay were derived from a source with

known radium mass. The results for the emission probabilities are summarized in Table 4. Quoted uncertainties correspond to one stan

1 9 dard deviation and include systematic uncertainties. )

106
Table 4

Results for photon emission probabilitites p. Energies E

taken from reference 30

A reference with an contains preliminary results.

Nuclide E

in keV

Reference

51

57

65

75

88

1 10

133

1 34

141

1 52

Cr 320.076 0.0985 ( 9) 1 5 Co 136.476 0.1058(8) 1 5 Zn 1 1 1 5. 546 0. 5039 (26) 7 Se 66 .050 0. 01 1 4 (2) 23*,

96.733 0.0348 (9)

121.115 0. 1 73 ( 3)

13 6. 000 0.590(8)

1 98. 596 0.01 47 (3)

264.651 0.591 (8)

279. 528 0. 252 (4)

303 .910 0.01 34 (2)

400. 646 0. 1 1 56 (1 5)

Y m 898.020 0.946(5) 7

_ m

Ag 657 .749 0. 9465 (1 6) 6 706 . 670 0. 1 656 (1 3)

763 .928 0. 2243 (1 8)

884 . 667 0.734 (1 8)

937.478 0.346(4)

1 384. 270 0. 2470(22)

1 505.001 0.1316(13)

Ba 30.85 (Ka ) 0. 971 (16) 21 , 35.1 (K 6

) 0. 232 (5)

53. 1 55 0.0220 (4

79. 621 0.0261 (7)

80. 997 0. 340(8)

1 60. 605 0.00646 (10)

223.25 0.0045 (1 ) 276. 397 0.0710 (10)

302. 851 0.1833(22)

356 • 005 0.623 (7

383.851 0.0892 (9)

Cs 475. 35 0.01 51 (3) 23

563 .227 0.0834 (1 2)

569.31

0.1 538(22)

604 .699 0. 976 ( 1

795. 845 0.853 (9)

801 .932 0.0864 (1 2)

1038. 57 0.00998 (1 3)

1 1 67 . 94 0.01800(20)

1365.1

0.0302 ( 3)

Ce 1 45.440 0.489(4) 1 5 Eu 39.9 (Ka ) 0.591(12) 1 4 45.7 (Kg) 0.149(3)

1 21 . 7824 0. 2855 (37) 21*, ! 244 . 6989 0.0744 (1 1 ) 344 . 275 0.2652 (29)

5, 27

107
Table 4 continued

Nuclide E p Reference

in keV

15:

"Eu

1 82 Ta

226

Ra

411 , 443,

778,

964

1085,

1112,

I 1 5 983

910

131

91 4

I I 6

1 408.01

1

31 .7370

42,

58,

65,

67,

67

69,

84 , 100

1 1 3

1 16

152

1 56

179

1 98

222

229

264

1 121

1 1 89

1 221

1 230

1257

1 289

1 85

241

295

351

609

768

934

1 120

1 238

1 509

1 764

2118

2 204

2293

2447

71 43

8 (Kct)

7217

2 (Kg x

) 7495

1 (Kg 2 ) 6805

1064

6670

4149

4281

381 7

3 904

3477

101

316

071

28

04

418

97

47

1 7 ,99

91

, 1 7 90

, 32

, 36

,05

,28

. 1 1

, 1 9 ,51

, 54

, 1 2 ,36

.71

0.0224 (4)

0.0312(5)

0. 1 291 (14)

0.1466(15)

0. 1009(1 3)

0. 1 353 ( 19)

0.2085(19)

0.00892 (21

)

0.00266 (8)

0.2802 (52)

0.571 (13)

0.0263 (10)

0. 1 423 (42)

0.01 87 (6)

0.00445(1 5)

0.0695 (9)

0.0263 (5)

0.0309 (4)

0.01 44 ( 2)

0.0750(10)

0.0364 (5)

0.0362 (6)

0. 3530(32)

0.1 644 ( 15)

0.2717(25)

0. 1 1 58 (1 1 ) 0.01 50(2)

0.0136 (2)

0.0351 (6)

0.071 2 ( 1 1 ) 0. 1 81 5 (22)

0.351 (4)

0.446 (5)

0.0475(7)

0.0307 (4)

0.147(2)

0.0578 (7)

0.0208(5)

0.1 506 (26)

0.01 17 (3)

0.0498 (1 2)

0.00301 (9)

0.01 55(4)

23 1 5

24

108
Part II: Half-lives

Half-lives are measured by following the radioactive decay

with two ionization chambers (open air and high pressure

argon chamber) . All sources were checked for ;£-ray emitting

impurities. Their contributions to the ionization current

were subtracted for each measuring point. Details on the

measurements and the data evaluation are given in references

3 1, 13 and 15. In some cases a Ge (Li) -spectrometer was used ).

Table 5 summarizes the results obtained for calibration nuclides.

Table 5 Half-lives

A reference with an contains preliminary results

Nuclide Half-life Reference

28

28

1 5

28

*, 9

1 5

51 Cr

6 5^°

75 Se 85f

88Y 110? m

111^

131*n 133f

1 37 Ba

Cs

140^ S

141^a

1 52^e 154*U

182*U

241 „Am

27

271

5 243

1 1 9 64

106

249

28

10

29

40

32

4931

8

1 1 4 432

.705(12) d

.5(5) d

.272(2) a .97(8) d

.76(5) d

.865(8) d

.64(8) d

.78(4) d

.8045(8) d

.021 (1 ) d

.74(5) a

. 901 (45) a .272(7) h

.51(6) d

(15) d

.57(7) a .43(4) d

.0(2) a

20 , 24

1 2o*,

22*,

28

20*,

25

25

1 , 20

1 28

3

1 5*

25

22

29

109
References

1) K.F. Walz, H.M. WeiB: "Messung der Halbwertszeiten von

6CV 1 37^ . 133 D „ Co , Cs una Ba , Z. Naturf. 25a (1970) 921-927

2) K. Debertin: "Relative Aktivitatsbes timmungen mit Ge(Li)-

Detektoren" , Atomkernenergie J_7 (1 971) 97-1 02

3) K. Debertin: "Halbwertszeiten von 95 Zr f 103 RU und 141 ce" ; Z.f. Naturf. 26a (1971) 596-597

4) U. Schotzig, K. Debertin, H.M. WeiB: "Bestimmung von

Gammastrahlen-Emissionswahrscheinlichkeiten mit einem

Ge (Li) -Spektrometer" ; PTB-Mitteilungen 8_3 (1 973) 307-31 2

5) K. Debertin, U. Schotzig, H.M. WeiB: "Kalibrierung der

Nachweiswahrscheinlichkeit von Ge ( Li) -Spektrometern mit

152

Eu"; PTB-Mitteilungen 85 (1 975) 1 87-1 95

6) K. Debertin, U. Schotzig, K.F. Walz, H.M. WeiB: "Efficiency

Calibration of Semiconductor Spectrometers - Techniques

and Accuracies"; Proceedings of ERDA Symp. on X- and GammaRay Sources and Applications. Ann Arbor (USA), 19. - 21.5.1976; H.C. Griffin (Hrsg.) National Technical Information Service, Springfield (USA), Sept. 1976, p. 59-62

7) K. Debertin, U. Schotzig, K.F. Walz, H.M. WeiB: "Radioaktive

Standards zur Kalibrierung von Germanium-Detektoren fur

die Gammastrahlen-Spektrometrie" ; PTB-Mitteilungen _87 (1977)

22 - 26

8) K. Debertin, U. Schotzig: "Limitations of the Pulser Method

for Pile-Up Corrections in Ge(Li) - Spectrometry"; Nucl.

Instr. and Methods 140 (1977) 337-340.

9) U. Schotzig, K. Debertin, K.F. Walz: "Standardization and

1 3 3 Decay Data of Ba" ; Intern. J. Appl. Rad . Isotopes 28

( 1 977) , 503 - 507

10) K. Debertin, U. Schotzig: "Calibration of Germanium Spectrometers for Gamma-Radiation"; Kerntechnik J_9 (1 977)

4 20 - 423

11) K. Debertin, U. Schotzig: "Coincidence Summing Corrections

in Ge (Li ) -Spectrometry at Low Source-to-Detector Distances";

Nucl. Instr. and Methods 158 (1979) 471-477

110
12) K. Debertin: "International Intercomparison of GammaRay Emission-Rate Measurements by Means of Germanium1 5 2 Spectrometers and Eu Sources"; Nucl. Instr. and

Methods 158 (1979) 479-486. ( Zusammenfassung von

Bericht PTB-Ra-7)

13) K. Debertin, W. PeBara, U. Schotzig, K.F. Walz: "Decay

Data of 67 Ga and 201 Tl"; Intern. J. Appl . Rad . Isotopes

30 (1979) 551-555

14) K. Debertin: "X-ray emission probabilities per decay of

152 Eu" ; Nucl. Instr. and Methods 1 6_5_ (1 979) 279-231

15) U. Schotzig, K. Debertin, K.F. Walz: "Efficiency calibration

of germanium spectrometers in the energy range from 122 keV

to 412 keV" ; Nucl. Instr. and Methods 169 (1980) 43-51

16) W. PeBara:" Amplitude dependent count rate losses in

pulsed optical feedback preamplifiers"; to be published

17) U. Schotzig, K. Debertin: " 417^ -MeBstand mit zwei Nal(Tl)-

Bohr lochkristallen zur Aktivitatsbes timmung von Radionukliden mit komplexem Zerfallsschema" ; PTB-Bericht in

preparation

18) K. Debertin, W. PeBara, K.F. Walz: "Kalibrierung von Halbleiterspektrometern fur Photonenstrahlung im Energiebereich 15 bis 300 keV" ; Friih j ahrstagung Kernphysik der

DPG 1 976, Verhandlungen der DPG (VI) V\_ (1 976) 879

19) S.R. Wagner: "On the quantitative characterization of the

uncertainty of experimental results in metrology" , PTBMitteilungen 89 (1979) 83-89

20) PTB-Jahresbericht 1973, 6.16 (p. 185)

21) PTB-Jahresbericht 1974, 6.10 (p. 222)

22) PTB-Jahresbericht 1975, 3.6.12 (p. 239) and 3.6.16 (p. 242)

23) PTB-Jahresbericht 1976, 3.6.10 (p. 160)

24) PTB-Jahresbericht 1977, 3.6.12 (p. 177) and 3.6.13 (p. 178)

25) PTB-Jahresbericht 1978, 3.6.6 (p. 189) and 3.6.7 (p. 190)

26) PTB-Jahresbericht 1979, in press

27) Contribution to ICRM intercomparison (see reference 12)

28) K.F. Walz, H.M. WeiB, K. Debertin: "Halbwertszeiten von

Radionukliden" , Internal report, Gruppe Radioakt ivitat der

PTB, March 1976

111
H. Ramthun, W. Muller: "Kalorimetrische Neubestimmung

241 der Halbwertszeit des Am", Int. J. Appl . Rad . Isotopes

26 (1975) 589-593

National Council on Radiation Protection and Measurements

"A Handbook of radioactivity measurements procedures"

,

NCRP-Report No. 58, Washington D.C., November 1978

112
Decay data of radionuclides used for the calibration of

germanium detectors

Supplement to the PTB-contr ibution to ICRM-SP action 10/79

July 1980

Table 5

Nuclide Half-life Reference

59

67

95

103

133

Fe

Ga

Zr

Ru

Ba

140

144

Ba

Ce

44.529 (7) d

3.2594 (12) d

64 .10 (4) d

39.276 (9) d

10.53 (6) a

12.746 (10) d

285.08 (18) d

28

13

28

22, 28

*.

24

28

i

113
Decay data of radionuclides used for the calibration of

germanium detectors

Supplement to the PTB-contribution to ICRM-SP action 10/7 9

July 1980

Table 4

Nil C* 1 1 HP

i n keV

p Ppf 1 v C J- pvpnf Cllv

9 5 7 24.-2 0.440 (5) 31

756,7 0.543 (5)

99Mo 140. 5 0.905 (5) 25

181 .0.0603 (7)

366.4 0.0122 (2)

739.5 0.1231 (9)

7 7 7 Q U . U'l J J

Ru 496 .9 0.909 (7) 21*

O I u . z ( 1 ) 125 Sb 176.4 0.0695 (12)

427 .9 0.305 (5)

463.4 0. 1071 (17)

600.6 0.180 (3)

606.7 0.0512 (8) cor q r\ l l a 7 u. in / I 1 0 ) 671 .4 0. 1842 (24)

131

I 284 .3 0.0620 (6) 24

364 .5 0.816 (6)

637 .0 0.0712 (6)

722.9 0.0178 (2)

140Ba 162.6 0.0621 (8) 32

537 .3 0.2439 (22)

140La 328 .8 0. 2074 (18) 32

487 .0 0.4594 (38)

815.8 0.2364 (17)

867.9 0.0559 (5)

925.2 0.0705 (8)

1596.5 0. 9540 (8)

144 Ce 133.5 0.1109 (16) 31

144

pr 696 .5 0.01342 (14) 31

1489.1 0.00279 (3)

2185.6 0.00700 (10)

114
Decay data of radionuclides

germanium

used for the

detectors

calibration of

ICRM-SP Action 10/79

Corrections to computer entries referring to PTE data

75 Se Photon probability per decay

All data except for 400.5 keV are lacking

133 Ba Photon probability per decay^79 and 81 keV

data are lacking

133 Ba Half-life

Replace our value by the new value given in the

supplementary table

134 Cs Photon probability per decay

Data for high energy lines should be given

although the probability is less than 5 %.

18 2 Ta Photon probability per decay

Reference to be replaced by reference 15

The energy selection criteria should be the same

for relative and absolute probabilities (e.g. 198.4 keV

Supplementary references

31) K. Debertin, U. Schotzig, K.F. Walz, H.M. WeiB: "Gamma-ray

emission probabilities of the fission products 144 Ce - 14 ^Pr,

106 Rh, 95 Zr";Ann. Nucl. Energy 2 (74) 37 - 43

32) K. Debertin, U. Schotzig, K.F. Walz: "Gamma-ray emission

probabilities in the decay of barium-140 and lanthanum-1 40"

;

Nucl. Sci. Eng. 64 (1977) 784 - 786

115
University of Guelph

Department of Physics

Guelph, Ontario, Canada

J.L. Campbell and L.A. McNelles

In Nucl. Instr. Meth. 98, 433 (1972), the authors give the results of 4 tt CsI(Tl) measurements of the emission rate of K x rays relative to gamma rays

in the decay of 109 Cd, ^9 Ce and l^Ce. These values are believed still to be

valid as given. The uncertainties given there are taken to have the significance

suggested for this compilation.

116
IV. Table of Selected Calibration Data

The process for selecting the data from those supplied by ICRM-SG members is

outlined in part I. The laboratory corresponding to each label is given in

part II.

Final zeros after a decimal point are suppressed by the computer program used to

group the data even if the zeros are significant (as indicated by the accompanying uncertainty). An asterisk signifies that the uncertainty is at the 3 sigma or 99% confidence level. Other uncertainties are to be taken as total uncertainties equivalent, in significance, to one standard deviation of the mean.

i

117
BE HALF LIFE

LABORATORY Tl/2

UNCERTAINTY

UNIT VALUE REF. AECL

LMRI NPL

53.284

53.17

53.16

PHOTON PROBABILITY PER DECAY

LABORATORY

477 KEV

AECL

F 18

HALF LIFE

LABORATORY

AECL

AECL

NPL

NA 22

HALF LIFE

P(%)

D .004 AECL-3668;50 (1970) D .07* IJARI-26;131(1975)

D .01 NPL PREV. UNPUBL.

UNCERTAINTY REF.

10.32 .04 CAN J PHYS 40,-926 (1962)

AECL-3512;29 (1969)

Tl/2

UNCERTAINTY

UNIT VALUE REF. 109.73

109.71

109.68

M .04 AECL-4708;20 (1974) M .02 AECL-4708;20 (1974) M .17 NPL PREV. UNPUBL.

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF.

AECL 950.3 D .27 AECL-6788;45 (1980)

IAEA 950.34 D .13 IJARI-31;153 (1980)

NBS 2.6057 Y .0003 NBS PREV. UNPUBL.

NA 24 HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. AECL 14.965 H .01 AECL-3912;43 (1971)

AECL 14.959 H .01 CAN J PHYS 36;983(1958)

AECL 14.965 H .001 AECL PREV. UNPUBL.

IAEA 14.959 H .0012 IJARI-31;153 (1980)

LMRI 14.956 H . 008* (IN PRESS)

NBS 14.951 H .003 NBS PREV. UNPUBL.

K 42 HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. AECL 12.358 H 007 CAN J PHYS 40;1044 (1962)

118
K 42 (CONTINUED)

PHOTON PROBABILITY PER DECAY

LABORATORY P(%)

153 0 KEV

AECL 19.1

UNCERTAINTY REF.

.6 AECL-1142;25 (1960)

SC 46

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. AECL 83.752 D .015 AECL-6788;45 (1980)

IAEA 83.819 D . 006 IJARI-31;153 (1980)

NBS 83.79 D .06 NBS PREV. UNPULB.

CR 51 HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. AECL 27.704 D .003 AECL-3668;50(1970)

IAEA 27 .69 D . 005 IJARI-31;153 (1980)

LMRI 27.72 D .07* IJARI-26;131 (1975)

NBS 27.73 D . 01 NBS PREV. UNPULB.

NPL 27.71 D .01 NPL PREV. UNPULB.

PTB 27.705 D .012 INT. REP. PTB RADIOACT. GROUP ; MARCH 1976

PHOTON PROBABILITY PER DECAY

LABORATORY P (%) UNCERTAINTY REF. 320.1 KEV

PTB

MN 52

9.85 ,09 NIM-169;43 (1980)

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF,

744.2 KEV

HNRE

848.2 KEV

HNRE

93 5.5 KEV

HNRE

1246.2 KEV

HNRE

1333.6 KEV

HNRE

1434.1 KEV

HNRE

90.35

3.39

94.89

4.32

5.07

99.9871

,07

,03

,03

,09

,04

.0014

NIM-175;525 (1980)

NIM-175;525 (1980)

NIM-175;525 (1980)

NIM-175;525 (1980)

NIM-175;525 (1980)

NIM-175;525 (1980)

119
MN 52 (CONTINUED)

RELATIVE PHOTON PROBABILITY

LABORATORY P(%) UNCERTAINTY REF

,

744.233 KEV

LLL

935.544 KEV

LLL

1333.65 KEV

LLL

1434.09 KEV

LLL

90

94.5

5.07

100

9

05

,5

M-l 00; LAWRENCE LIVERMORE LAB; (1978)

M-100; LAWRENCE LIVERMORE LAB; (1978)

M-100;LAWRENCE LIVERMORE LAB; (1978)

M-100 ;LAWRENCE LIVERMORE LAB; (1978)

MN 54

HALF LIFE

FE 55

HALF LIFE

LABORATORY

IAEA

LMRI

NBS

MN 56

HALF LIFE

LABORATORY

Tl/2

1000.4

2.68

1009.0

Tl/2

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. AECL 312.21 D .03 AECL-6530;44 (1979)

NBS 312.02 D .04 NBS PREV. UNPUBL.

BIPM 312.19 D .13 PROC.CIPM-41;68(1973)

BIPM 312.15 D .23 PROC.CIPM-42;64 (1974)

UNCERTAINTY

UNIT VALUE REF.

D 1.3 IJARI-31;153 (1980)

Y .02* (IN PRESS)

D 1.7 NBS PREV. UNPUBL.

UNCERTAINTY

UNIT VALUE REF. AECL

LMRI

NPL

CO 56 HALF LIFE

LABORATORY

LMRI

2. 5764

2.5785

2.578

Tl/2

77.12

H .0008 AECL-3333;32(1969)

H .0006* NIM-112;323 (1973)

H .008 IJARI-19;823 (1968)

UNCERTAINTY

UNIT VALUE REF.

.20* lJARI-29;269 (1978)

120
CO 56 (CONTINUED)

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF.

Q AG. Q }\tj v HMO IT 99.92 .007 NIM-174;109 (1980)

1 fl *5 "7 D KEV

HNRE 14.15 .07 NIM-174;109(1980)

1238.3 KEV

HNRE 66 .3 NIM-174;109 (1980)

1360.2 KEV

HNRE 4.262 .022 NIM-174;109 (1980)

1771.4 KEV

HNRE 15.48 .07 NIM-174;109 (1980)

2015.4 KEV

HNRE 3.024 .017 NIM-174;109(1980)

2034.9 KEV

HNRE 7.76 .04 NIM-174;109 (1980)

2598.6 KEV

HNRE 16.95 .08 NIM-174;109(1980)

RELATIVE PHOTON PROBABILITY

LABORATORY P(%) UNCERTAINTY REF. 846.8 KEV

INEL 100 1 NIM-147;405(1977)

LLL 100 0 M-100; LAWRENCE LIVERMORE LAB; (1978)

1037.8 KEV

INEL 14.04 .14 NIM-147;405(1977)

LLL 14 .1 M-100,-LAWRENCE LIVERMORE LAB; (1978)

1175.1 KEV

INEL 2.28 .02 NIM-147;405 (1977)

LLL 2.28 .02 M-100,-LAWRENCE LIVERMORE LAB; (1978)

1238.3 KEV

INEL 66.4 .7 NIM-147;405(1977)

LLL 67.6 .4 M-100,-LAWRENCE LIVERMORE LAB; (1978)

1360.2 KEV

INEL 4.24 .04 NIM-147,-405 (1977)

LLL 4.33 .04 M-100,-LAWRENCE LIVERMORE LAB; (1978)

1771 KEV

INEL 15.65 .16 NIM-147;405(1977)

LLL 15.7 .15 M-100,-LAWRENCE LIVERMORE LAB; (1978)

2015.2 KEV

INEL 3.09 .05 NIM-147;405 (1977)

LLL 3.08 .03 M-100,-LAWRENCE LIVERMORE LAB; (1978)

2034.7 KEV

INEL 7.95 .12 NIM-147 ,-405 (1977) LLL 7.89 .07 M-100,-LAWRENCE LIVERMORE LAB; (1978)

2598.4 KEV

INEL 17.34 .26 NIM-147,-405 (1977)

LLL 16.9 .15 M-100,-LAWRENCE LIVERMORE LAB; (1978)

3201.9 KEV

INEL 3.18 .1 NIM-147,-405 (1977)

LLL 3.04 .03 M-100,-LAWRENCE LIVERMORE LAB; (1978)

3253.4 KEV

INEL 7.79 .24 NIM-147,-405 (1977)

LLL 7.41 .065 M-100,-LAWRENCE LIVERMORE LAB; (1978)

121
CO 57 HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. CBNM 271 .90 D .09 IJARI ( IN PRESS)

IAEA 271 .77 D .05 IJARI-31;153 (1980)

LMRI 271 .23 D .63* IJARI-23;219 (1972)

NBS 271 .9 D .2 NBS PREV. UNPUBL.

PTB 271 .5 D .5 PTB-ANNUALQ977) ;177

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF. 136.5 KEV

PTB 10.58 .08 U.SCHOTZIG ET AL NIM(IN PRESS)

CO 58

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. CBNM 70. 81 D .1* IJARI-27;727 (1980)

IAEA 70. 916 D .015 IJARI-31;153 (1980) LMRI 70. 78 D .13* IJARI-26;131 (1975)

NBS 70. 75 D .07 NBS PREV. UNPUBL.

NPL 70. 83 D .02 NPL PREV. UNPUBL.

FE 59

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. IAEA 44.496 D NBS 44.507 D PTB 44.529 D

.007 IJARI-31;153 (1980)

.007 NBS PREV. UNPUBL.

.007 PTB; INT. REP. MAR 1976

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF.

1099 KEV

LMRI 55.5 1.7* NP A-142 ; 63 ( 1970

)

1292 KEV

LMRI 44.1 1.2* NP A-142;63 (1970)

CO 60

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. AECL 1923.78 D AECL 1924.33 D CBNM 5.283 Y IAEA 1925.2 D NBS 5.282 Y PTB 5.272 Y BIPM 46195 H BIPM 1925.5 D

.94 AECL-6788;46 (1980)

1.36 AECL-6788;46 (1980)

.008* IJARI-27;727 (1976)

.4 IJARI-31;153 (1980)

.007 NBS PREV. UNPUBL.

.002 Z.NATURF-25A;921 (1970)

24 PROC.CIPM-41;68(1973)

.3 BIPM PREV. UNPUBL.

122
ZN 65

HALF LIFE

LABORATORY Tl/2

UNCERTAINTY

UNIT VALUE REF. CBNM

LMRI

NBS

PTB

244

243.75

244.2

243.97

D .2 Z.PHYSIK-250;395 (1972) D .21* IJARI-26;131 (1975)

D .1 NBS PREV. UNPUBL.

D .08 INT. REP. PTB RADIOACT. GROUP MAR 1976

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF,

1115 KEV

CBNM

PTB 50.7550.39

.1.26Z.HYSIK-250;395 (1972)

PTB-MITTEILUNGEN-87;22 (1977)

GA 67

HALF LIFE

LABORATORY

IAEA

LMRI

NBS

NPL

PTB

Tl/2

3.2607

78.33

3.2606

3.261

3.2594

UNCERTAINTY

UNIT VALUE REF.

D .0008 IJARI-31;153 (1980)

H .10* IJARI-29;269 (1978)

D .001 NBS PREV. UNPUBL.

D .006 IJARI-23;279 (1972) D .0012 IJARI-30;551 (1979)

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF. 91.237 KEV

LLL

93.291 KEV

LLL

184.569 KEV

LLL

208.97 KEV

LLL 300.23 KEV

LLL

393.539 KEV

LLL

336.6

21.7

2.4

16.6

4.5

.2

1.4

.9

.1

.4

.1

M-l 00,-LAWRENCE LIVERMORE LAB; (1978)

M-100;LAWRENCE LIVERMORE LAB; (1978)

M-100; LAWRENCE LIVERMORE LAB; (1978)

M-100; LAWRENCE LIVERMORE LAB; (1978)

M-100; LAWRENCE LIVERMORE LAB; (1978)

M-100; LAWRENCE LIVERMORE LAB; (1978)

SE 75

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF.

IAEA 119.779 D .004 IJARI-31;153 (1980)

LMRI 118.45 D .25* IJARI-26;131 (1975)

NBS 119.80 D .07 NBS PREV. UNPUBL.

PTB 119.76 D .05 NIM-169;43 (1980)

123
75 (CONTINUED)

PHOTON PROBABILITY PER DECAY

r V « 1 UNCERTAINTY REF.

Qfi 7 VP\7

nrnp rlu 7 A ft .09 NIM-169;43 (1980)

191 1 K PV

r Id 17 "\ X / • 0 .3 NIM-169;43 (1980)

IjDoU IVE* V PTB 59.0 .8 NIM-169;43 (1980)

264.7 KEV

PTB 59.1 .8 NIM-169;43 (1980)

279,5 KEV

PTB 25.2 .4 NIM-169;43 (1980)

4 0 0 R K P\7 APPT J. A • J .3 AECL-3666;46 (1970)

PTB III II JVRfi .15 NIM-169;43 (1980)

RPT ATTVF PHOTON PRORARTT r I\ \J DnD ] LilTTV1 I

T ARORATORY UNCERTAINTY REF.

Qfi 7 K"P\7 TMPT 1 IN Ej J_i .3 NIM-147;405(1977)

t r t .21 M-100 ; LAWRENCE LIVERMORE LAB; (1978)

191 1 V PV

T MPT 9 Q ft .9 NIM-147;405(1977)

T T T 9 Q ft .2 M-100; LAWRENCE LIVERMORE LAB; (1978)

11 JO1 fiis. W PWe* V

1 IN Lj Li 1 fl 9 3 NIM-147;405(1977)

T T T i nn .3 M-100; LAWRENCE LIVERMORE LAB; (1978)

7 fi A 7 V P\7 100 3. NIM-147;405 (1977)

LLL 100 .5 M-100; LAWRENCE LIVERMORE LAB; (1978)

279.5 KEV

INEL 42.4 1.3 NIM-147;405 (1977)

LLL 42.2 .4 M-100; LAWRENCE LIVERMORE LAB; (1978)

400.5 KEV

INEL 19.1 .3 NIM-147;405(1977)

LLL 19.5 .3 M-100; LAWRENCE LIVERMORE LAB; (1978)

82 HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. AECL 35.344 H .016 CAN . J . P

. -40 ; 1044 ( 1 962)

RELATIVE PHOTON PROBABILITY

LABORATORY P(%) UNCERTAINTY REF. 554.3 KEV

INEL 84.7 .8 NIM-147;405(1977)

LLL 84.8 1.6 M-100; LAWRENCE LIVERMORE LAB; (1978)

619.1 KEV

INEL 52 .5 NIM-147;405(1977)

LLL 51.6 .5 M-100; LAWRENCE LIVERMORE LAB; (1978)

776.5 KEV

INEL 100 1 NIM-147;405 (1977)

LLL 100 0 M-100; LAWRENCE LIVERMORE LAB; (1978)

827.8 KEV

INEL 28.77 .29 NIM-147;405(1977)

LLL 28.7 .7 M-100; LAWRENCE LIVERMORE LAB; (1978)

1044 KEV

INEL 32.55 .33 NIM-147;405(1977)

LLL 32.8 .5 M-100; LAWRENCE LIVERMORE LAB; (1978)

1317.4 KEV

INEL 31.74 .32 NIM-147;405(1977)

LLL 32.2 .6 M-100; LAWRENCE LIVERMORE LAB; (1978)

1474.9 KEV

INEL 19.53 .2 NIM-147;405(1977)

LLL 19.9 .3 M-100; LAWRENCE LIVERMORE LAB; (1978)

124
KR 85

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF

.

514 KEV

AECL .46 .03 NUCLEONICS-19 ; 97 ( 1 961

)

SR 85

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. AECL 64.845 D .009 AECL-5315;37 (1976)

IAEA 64.856 D .007 IJARI-31;153 (1980)

NBS 64.851 D .006 , NBS PREV. UNPUBL.

NPL 64.84 D .013 Z.PHYSIK-A-289;51 (1978)

PTB 64.865 D .008 PTB; PREV. UNPUBL.

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF.

13.38 KEV

NPL

88

58.66 .41 K X-RAY;Z.PHYSIK-A-289;51(197

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. IAEA 106.612 D .014 IJARI-31;153 (1980)

LMRI 106.6 D .4* IJARI-26;131 (1975)

NBS 106.64 D .05 NBS PREV. UNPUBL.

PTB 106.64 D .08 PTB INT. REP. MAR 1976

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF.

898 KEV

HNRE 93.7 .4 NIM-174;109(1980)

NBS 94.3 .3 NBS PREV. UNPUBL.

PTB 94.6 .5 PTB-MITTEILUNGEN-87;22 (1977)

NB 90

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF.

141.2 KEV

HNRE 70.1 1.7 NIM-175;525 (19*50) 1129.2 KEV

HNRE 94.22 .09 NIM-175;525 (19i30) 2186.2 KEV

HNRE 18.11 .08 NIM-175;525 (19!]0) 2319 KEV

HNRE 81.82 .08 NIM-175;525 (19fJO)

125
NB 90 (CONTINUED)

RELATIVE PHOTON PROBABILITY

LABORATORY P(%)

132.7 KEV

LLL

141.2 KEV

LLL

1129.2 KEV

LLL

2186.2 KEV

LLL

2319 KEV

LLL

5.04

81 .4

113

21.9

100

UNCERTAINTY REF. ^5

.5

.2

.2

M- 100,-LAWRENCE LIVERMORE LAB; (1978)

M-100;LAWRENCE LIVERMORE LAB; (1978)

M-100; LAWRENCE LIVERMORE LAB; (1978)

M-100; LAWRENCE LIVERMORE LAB; (1978)

M-100; LAWRENCE LIVERMORE LAB; (1978)

ZR 95

HALF LIFE

UNCERTAINTY

LABORATORY Tl/ 2 UNIT VALUE REF. CBNM 64. 05 D .06* Z.HYSIK A -276;317 (1976)

IAEA 64. 03 D .006 IJARI-31; 153 (1980)

PTB 64. 10 D .04 PTB INT. REP. MAR 1976

PHOTON PROBABI LITY PER DECAY

LABORATORY P( %) UNCERTAINTY REF. 724.2 KEV

LLL

PTB 756.7 KEV

LLL

PTB

43.7

44.0

55.4

54.3

.8

. 5

1.1

.5

M-100; LAWRENCE LIVERMORE LAB; (1978)

ANN. NUCL. ENERGY-2;37 (1974)

M-100; LAWRENCE LIVERMORE LAB; (1978) ANN. NUCL. ENERGY-2;37 (1974)

NB 95

HALF LIFE

LABORATORY

AECL

CBNM

IAEA

MO 99

HALF LIFE

LABORATORY

IAEA

NBS

NPL

Tl/2

34.98

34.97

34.979

Tl/2

65.945

65.924

65.903

UNCERTAINTY

UNIT VALUE REF.

D .02 AECL-3668;50 (1970)

D .03* Z.PHYSIK-A-278;317 (1976)

D .009 IJARI-31;153 (1980)

UNCERTAINTY

UNIT VALUE REF.

H .003 IJARI-31;153 (1980)

H .006 NBS PREV. UNPUBL.

H .001 NPL PREV. UNPUBL.

126
MO 99 (CONTINUED)

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF.

1 A (\ A 14U . 4 KEV

LLL 90.6 1.8 M-100; LAWRENCE LIVERMORE LAB; (1978) MD C 90.3 1.0 NBS PREV. UNPUBL.

PTB 90.5 .5 PTB-ANN . REP . (1978)

1 O 1 1 1 01 . 1 KEV

LLL 6.04 .12 M-100; LAWRENCE LIVERMORE LAB; (1978)

NBS 6.00 .05 NBS PREV. UNPUBL.

PTB 6.03 .07 PTB-ANN. REP. (1978)

739.5 KEV

LLL 12 .33 M-100; LAWRENCE LIVERMORE LAB; (1978)

NBS 12.06 .09 NBS PREV. UNPUBL.

PTB 12.31 .09 PTB-ANN. REP. (1978)

777 .9 KEV

LLL 4.24 .09 M-100; LAWRENCE LIVERMORE LAB; (1978)

NBS 4.25 .03 NBS PREV. UNPUBL.

PTB 4.33 .04 PTB-ANN. REP. (1978)

TC 99M

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. AECL 6.008 H .004 AECL-6083;38(1978)

IAEA 6.006 H .002 IJARI-31;153 (1980)

LMRI 6.031 H .012* IJARI-21;139(1970)

NBS 6.0072 H .0009 SALINE; NBS PREV. UNPUBL.

NBS 6.017 H .002 AC ID; NBS PREV. UNPUBL.

NPL 6.0067 H .0038 NATURE-210;614 (1966)

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF.

140 KEV

AECL 88.75 .14 AECL-3157 ; 30 (1968)

RU103

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. CBNM

IAEA

PTB

39.26

39.254

39.276

D .02 D .008

D .009

IJARI (IN PRESS)

IJARI-31;153 (1980)

PTB-INT.REP. MAR 1976

RELATIVE PHOTON PROBABILITY

LABORATORY P(%) UNCERTAINTY REF.

497 KEV

LLL

610.2 KEV

LLL

100

6.3

.5

.2

M-100; LAWRENCE LIVERMORE

M-100; LAWRENCE LIVERMORE

LAB;

LAB; PHOTON PROBABILITY PER DECAY

LABORATORY P ( % ) UNCERTAINTY REF.

497 KEV

PTB 610.2 KEV

PTB

90.9

5.65

.7

.07

PTB-ANN. REP. (1974)

PTB-ANN. REP. (1974)

127
CD109

HALF LIFE

LABORATORY Tl/2

UNCERTAINTY

UNIT VALUE REF. CBNM

LMRI

NBS

461.9

463.1

463 .2

D .3 IJARI (IN PRESS)

D .8* (IN PRESS)

D .6 NBS PREV. UNPUBL.

RELATIVE PHOTON PROBABILITY

LABORATORY P(%) UNCERTAINTY REF. 22.5 KEV

NBS

UGDP

88 KEV

NBS

UGDP

2734

2560

100

100

27

90

00

NBS PREV. UNPUBL.

NIM-98; 433 (1972)

NBS PREV. UNPUBL.

NIM-98; 433 (1972)

AG110M

HALF LIFE

LABORATORY Tl/2

UNCERTAINTY

UNIT VALUE REF. IAEA

NBS

PTB

249.74

249.93

249.78

D .05 IJARI-31;153 (1980)

D .06 NBS PREV. UNPUBL.

D .04 PTB-INT.REP. MAR 1976

PHOTON PROBABILITY PER DECAY

LABORATORY P(%)

657.8 KEV

HNRE

PTB

677.1 KEV

HNRE

687 KEV

HNRE

707.5 KEV

HNRE

PTB

744.3 KEV

HNRE

763.9 KEV

HNRE

PTB

818 KEV

HNRE

884.7 KEV

HNRE

PTB

937.5 KEV

HNRE

PTB

1384.3 KEV

HNRE

PTB

1505 KEV

HNRE

PTB

94.54

94.65

10.48

6.43

16.7

16.56

4.73

22.26

22.43

7.33

72.6

73.4

34.33

34.6

24.25

24.7

13 .03 13.16

UNCERTAINTY REF.

.2.16

.09

.06

.12

.13

.03

.13

.18

.05

.4 1.8

.2.4

.14

.22

.07

.13

NIM-174;109(1980)

USAEC REP. CONF-760539;59;NTIS;1976

NIM-174;109 (1980)

NIM-174;109 (1980)

NIM-174;109 (1980)

USAEC REP. CONF-760539;59;NTIS;1976

NIM-174;109(1980)

NIM-174;109 (1980)

USAEC REP. CONF-760539;59;NTIS;1976

NIM-174;109(1980)

NIM-174;109(1980)

USAEC REP. CONF-760539;59;NTIS;1976

NIM-174;109(1980)

USAEC REP. CONF-760539; 59 ; NTIS ; 1976

NIM-174;109 (1980)

USAEC REP. CONF-760539;59;NTIS;1976

NIM-174;109 (1980)

USAEC REP. CONF-760539;59;NTIS;1976

128
AG110M (CONTINUED)

RELATIVE PHOTON PROBABILITY

LABORATORY P (%) UNCERTAINTY REF

657.7 KEV

INEL 100 1 NIM-147;405(1977)

LLL 100 0 M-100 ; LAWRENCE LIVERMORE LAB; (1978)

^* "7 "7 f~ TP l-l* T 677.6 KEV

INEL 11.31 . 11 NIM-147;405(1977)

LLL 11.2 . 2 M-100 ; LAWRENCE LIVERMORE LAB; (1978)

687 KEV

INEL 6.85 . 07 NIM-147; 405 (1977) LLL 6 . 83 .05 M-100 ; LAWRENCE LIVERMORE LAB; (1978)

706.7 KEV

INEL 17 . 67 .18 NIM-147;405(1977)

LLL 17.28 .05 M-100 ; LAWRENCE LIVERMORE LAB; (1978)

74 4.3 KEV

INEL 4 . 92 . 05 NIM-147 ; 40 5 ( 1977

)

LLL 4 . 93 . 08 M-100 ; LAWRENCE LIVERMORE LAB; (1978)

763.9 KEV

INEL 23 .

6

. 24 NIM-147; 405(1977)

LLL 23.6 . 3 M-100 ; LAWRENCE LIVERMORE LAB; (1978)

818 KEV

INEL 7 .73 .08 NIM-147; 405 (1977)

LLL 7 .71 . 05 M-100 ; LAWRENCE LIVERMORE LAB; (1978)

884.7 KEV

INEL 76.9 . 8 NIM-147;405(1977)

LLL 77 .

1 M-100; LAWRENCE LIVERMORE LAB; (1978)

937.5 KEV

INEL 36.22 .36 NIM-147;405 (1977)

LLL 36.3 .6 M-100;LAWRENCE LIVERMORE LAB; (1978)

1384.3 KEV

INEL 25.7 .26 IM-147;405 (1977)

LLL 26.1 .5 M-100; LAWRENCE LIVERMORE LAB; (1978)

1505 KEV

INEL 13.84 .14 NIM-147;405 (1977)

LLL 14.01 .19 M-100; LAWRENCE LIVERMORE LAB; (1978)

IN111

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF.

IAEA

LMRI

NBS

PTB

IN113M

HALF LIFE

LABORATORY

2.8071

2.802

2. 8048

2.8045

Tl/2

D

D Cv a

UNIT

.0015 IJARI-31;153 (1980)

.003* IJARI-29;269 (1978)

.0005 NBS PREV. UNPUBL.

.0008 PTB-ANN . REP (1978)

UNCERTAINTY

VALUE REF.

AECL 99.49 M .06 AECL-2256;23 (1965)

CBNM 99.47 M .07 IJARI-22;1(1971)

LMRI 1.658 H .004* IJARI-21;139 (1970)

NBS 99.21 M .13* IJARI-26;314 (1975)

NPL 1.658 H .002* IJARI-21;678(1970)

129
IN113M (CONTINUED)

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF.

392 KEV

AECL 64.9 .2 AECL-2256 ; 23 ( 1965

NPL 64.9 .3* IJARI-21;678(1970)

SN113

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF.

AECL 115.12 D .13 AECL-5315;37 (1976)

IAEA 115.09 D .04 IJARI-31;153(1980)

NBS 115.06 D .07 NBS PREV. UNPUBL.

123

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. LMRI 13.21 H .03* (IN PRESS)

NPL 13.222 H .003 NPL PREV. UNPUBL.

SB125

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF.

IAEA 1007.3 D .3 I JARI-31 ; 1 53 ( 1980

NBS 2.75 Y .02 NBS PREV. UNPUBL.

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF. 176.4 KEV

LLL 6.79 .02 M-100 /LAWRENCE LIVERMORE LAB; (1978)

PTB 6.95 .12 PTB PREV. UNPUBL.

427.9 KEV

LLL 29.4 .2 M-100 ; LAWRENCE LIVERMORE LAB; (1978)

PTB 30.5 .5 PTB PREV. UNPUBL.

463.4 KEV

LLL 10.45 .15 M-100; LAWRENCE LIVERMORE LAB; (1978)

PTB 10.71 .17 PTB PREV. UNPUBL.

600.6 KEV

LLL 17.78 .2 M-100; LAWRENCE LIVERMORE LAB; (1978)

PTB 18.0 .3 PTB PREV. UNPUBL.

606.7 KEV

LLL 5.02 .07 M-100; LAWRENCE LIVERMORE LAB; (1978)

PTB 5.12 .08 PTB PREV. UNPUBL.

635 .9 KEV

LLL 11.32 .18 M-100; LAWRENCE LIVERMORE LAB; (1978)

PTB 11.47 .15 PTB PREV. UNPUBL.

671.4 KEV

LLL 1.8 .4 M-100; LAWRENCE LIVERMORE LAB; (1978)

PTB 1.842 .024 PTB PREV. UNPUBL.

130
SB125 (CONTINUED)

RELATIVE PHOTON

LABORATORY

PROBABILITY

P (%) UNCERTAINTY REF

.

176.4 KEV

INEL 23.9 .7 NIM-147; 405 (1977)

NBS 23.2 .1 NBS PREV. UNPUBL.

380.4 KEV

INEL 5.1 . 05 NIM-147;405 (1977)

427.9 KEV

INEL 100 1 NIM-147;405 (1977)

NBS 100.0 .6 NBS PREV. UNPUBL.

463.4 KEV

INEL 35.26 .37 NIM-147;405 (1977)

600.6 KEV

INEL 60.6 .6 NIM-147;405 (1977)

NBS 59.7 .4 NBS PREV. UNPUBL.

606.7 KEV

INEL 17.12 .17 NIM-147;405 (1977)

NBS 17.0 .1 NBS PREV. UNPUBL.

63 5.9 KEV

INEL 38.6 .4 NIM-147;405 (1977)

NBS 38.1 .2 NBS PREV. UNPUBL.

671.4 KEV

INEL 6.18 .06 NIM-147;405 (1977)

NBS 6.3 .1 NBS PREV. UNPUBL.

I 125

HALF LIFE

LABORATORY Tl/2

UNCERTAINTY

UNIT VALUE REF. IAEA 59.156 D .02 IJARI-31;153 (1980)

NBS 59.47 D .21 NBS PREV. UNPUBL.

I 131

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF.

IAEA 8.0213 D .0009 IJARI-31;153 (1980)

LMRI 8.020 D .003* IJARI-29;269 (1978)

NBS 8.020 D .002 NBS PREV. UNPUBL.

PTB 8.021 D .001 PTB-ANN . REP . (1978)

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF.

KEV

284.3 KEV

LLL

NBS

PTB

364.5

LLL

PTB

637 KEV

LLL

NBS

PTB

6.01

6.21

6.20

80.6

81.6

7.21

7.11

7.12

.06

.04

.06

1.6

.6

.09

.04

.06

M-100; LAWRENCE LIVERMORE LAB; (1978)

NBS PREV. UNPUBL.

PTB-ANN. REP. 1977

M-100; LAWRENCE LIVERMORE LAB; (1978)

PTB-ANN. REP. 1977

M-100; LAWRENCE LIVERMORE LAB; (1978)

NBS PREV. UNPUBL.

PTB-ANN. REP. 1977

XE133

HALF LIFE

LABORATORY Tl/2

UNCERTAINTY

UNIT VALUE REF. AECL

NBS

NPL

5.243

5.245

5.25

D .001 AECL-5032;34 (1975)

D .006* PRC-10;2631 (1974)

D .013* IJARI-26;485 (1975)

131
BA133

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. AECL 3785.17 Un Z01/ • X1 7/ AECL-6788;45 (1980)

IAEA 3848 IJARI-31;153 (1980)

NBS 10.48 NBS PREV. UNPUBL.

PTB 10.53 v nfi PRELIMINARY VALUE IN IJARI-28;503 (1 PHOTON PROBABILITY PER DECAY

T.ARORATDRY P (%

)

UlN\^I_jI\Xr^XLNX X REF.

ftS KFV

LMR

I

99.7 3.0* K-ALPHA X-RAY;LMRI/80/776/EM

PTB 97 .

1

1 .

6

K-ALPHA X-RAY ;PTB- ANN. REP. 1 19

3 5.1 KEV

LMRI 22.9 . 8* K-BETA X-RAY; LMRI/ 80/776/EM

PTB 23.2 . 5 K-BETA X-RAY ;PTB-ANN. REP. V979

79.6 ^ t' I LMRI 2.57 .12*

PTB 2.61 . 07 PTB-ANN.REP. 1979

ftl n LMRI 34.5 . 8* LMRI/80/776/EM

PTB 34.0 . 8 PTB-ANN.REP. 1979

01 P. A WM

HNRE 7.15 .03 Y. YOSHIZAWA PRI

.

COMM. (1980) LMRI 7.16 . 15* LMRI/80/776/EM

XT X D 7 • J. PTB-ANN.REP. 1979

1 n 0 Q V F\7

1 ft 9ft n ft Y. YOSHIZAWA PRI. COMM. (1980)

r MDT x1 oft . 01z / .35* LMRI/80/776/EM

rlu 1ft "< .22 PTB-ANN.REP. 1979

^J ^f, JO KF\7 f\. Ej V H MP F D Z .14 Y. YOSHIZAWA PRI. COMM. (1980)

T MPT 1.0* LMRI/80/776/EM

r 1 D O Z J • 77 PTB-ANN.REP. 1979

TO") Q 1/ p\7 MRP ft Q9 Y. YOSHIZAWA PRI. COMM. (1980)

Xil T MRvll\ TX

fto • yQlx .19* LMRI/80/776/EM

"DTR Jr X o ft Q9 n Q PTB-ANN.REP. 1979

RFTATTVF r\i-j ijr\ J. J. v a PHOTON rnuiui\ PRORARTT TTV

TbnDU£\n ARORATORY X \JX\ X P (% ) IINCFRTA TNTY REF.

81 KEV

TNFT XVtXjXi 49.2 2 .

6

NIM-147;405 (1977) LLL 51 .

2

_ 4 M-l 00; LAWRENCE LIVERMORE LAB; (1978)

GITSC 52.6 -L Z. PHYSIK-249; 286 (1972)

276.4 KEV

INEL 11.7 A NIM-147;405(1977)

LLL 11.3 . 2 M-l 00 ; LAWRENCE LIVERMORE LAB; (1978)

GITSC 11.4 "5 . J Z. PHYSIK-249; 286 (1972)

302.9 KEV

INEL 29.76 J • .J NIM-147;405 (1977)

LLL 29.2 . 3 M-100; LAWRENCE LIVERMORE LAB; (1978)

GITSC 30.2 .6 Z. PHYSIK-249; 286 (1972)

356 KEV

INEL 100 1 NIM-147;405(1977)

LLL 100 .3 M-100; LAWRENCE LIVERMORE LAB; (1978)

GITSC 100 0 Z. PHYSIK-249; 286 (1972)

383.9 KEV

INEL 14.36 .14 NIM-147;405(1977)

LLL 14.5 .2 M-100 ; LAWRENCE LIVERMORE LAB; (1978)

GITSC 14.4 .3 Z. PHYSIK-249; 286 (1972)

132
CS134

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF.

AECL 753.78 D .3 AECL-6788;45 (1980)

IAEA 754.5 D .07 IJARI-31;153 (1980)

LMRI 2.058 Y .012* IJARI-23;219 (1972)

NBS 2.0649 Y . 0004 NBS PREV. UNPUBL.

PHOTON PROBABILITY PER DECAY

LABORATORY P (%

)

UNCERTAINTY REF. 563.1 KEV

HNRE 8.37 .05 NIM-174;109 (1980)

LLL 8.38 . 05 M-100; LAWRENCE LIVERMORE LAB; (197!})

PTB 8.34 . 12 PTB-ANN . REP . 1976

DO y . 2. KEV

HNRE 1 C A .08 NIM-174;109 (1980)

LLL 1 D . 4 . 1 M-100; LAWRENCE LIVERMORE LAB; (197!5) PTB 15.38 . 22 PTB-ANN. REP. 1976

o(J4 . / KEV

HNRE 0*7 C A y / . o4 .06 NIM-174;109 (1980)

T T T Q"7 C y / . o .3 M-100; LAWRENCE LIVERMORE LAB; (197cn

PTB 97.6 .1 PTB-ANN. REP. 1976

795.8 KEV

HNRE 85.52 .05 NIM-174;109(1980)

LLL 85.4 .4 M-100; LAWRENCE LIVERMORE LAB; (1978)

PTB 85.3 .9 PTB-ANN. REP. 1976

801.8 KEV

HNRE 8.68 .04 NIM-174;109 (1980)

LLL 8.73 .4 M-100 ;LAWRENCE LIVERMORE LAB; (197ci) PTB 8.64 .12 PTB-ANN. REP. 1976

1167.9

HNRE 1.783 .010 NIM-174;109 (1980)

LLL 1.81 .03 M-100; LAWRENCE LIVERMORE LAB; (197cn

PTB 1.80 .20 PTB-ANN. REP. 1976

1365.2

HNRE 3.001 .017 NIM-174;109(1980)

LLL 3.04 .04 M-100; LAWRENCE LIVERMORE LAB; (197c

PTB 3.02 .02 PTB-ANN. REP. 1976

CS137

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. AECL

IAEA

NBS

PTB

10677.5

11009

30.68

29.901

D 140.3

D 11

Y .02

Y .045

AECL-6788;## (1980)

IJARI-31;153 (1980)

NBS PREV. UNPUBL.

Z. NATURF-25A; 921 (1970)

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF.

662 KEV

AECL

CBNM

NPL

84.7

85.1

84.56

.6

.4.08

AECL-6203; (1978)

Z.HYSIK-215;25 (1969)

METROLOGIA-14;157 (1978)

133
CS137 (CONTINUED)

RELATIVE PHOTON PROBABILITY

LABORATORY P(%) UNCERTAINTY REF.

661.6 KEV

CBNM 100 0 REFERENCE LINE

32.1 KEV

CBNM 8.13 .1 Z.HYSIK-215;25 (1969)

CE139

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. AECL 137.65

IER 137.8

LMRI 137.59

NBS 137.74

D .03 D . ij * D .2 D .12*

D .08

AECL-5546;32 (1976)

I JARI-27 ; 727 (1976)

RAPPORT BIPM-77/4

IJARI-29;269(1978)

NBS UNPUBLISHED

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF.

165 KEV

AECL 79.95 .06 BAPS-7 ,-352 (1962)

RELATIVE PHOTON PROBABILITY

LABORATORY P(%) UNCERTAINTY REF.

34 KEV

UGDP 101

165.8 KEV

UGDP 100

2.5

0

NIM-98; 433 (1972)

NIM-98; 433 (1972)

BA140-LA140 ===========

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF.

NBS 12.753 D .002 NBS UNPUBLISHED

PTB 12.746 D .010 PTB-ANN. REP. 1977

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF. 162.5 KEV

PTB 6.21 .08 NUCL. SCI. ENG. 64,784(1977)

537.3 KEV

PTB 24.39 .22 NUCL. SCI. ENG. 64,784(1977)

134
BA140-LA140 (CONTINUED)

RELATIVE PHOTON PROBABILITY

LABORATORY P(%) UNCERTAINTY REF. 162.5 KEV

INEL

328.8 KEV

INEL

487 KEV

INEL 537.3 KEV

INEL 751.7 KEV

INEL 815.8 KEV

INEL

867.8 KEV

INEL 925.2 KEV

INEL 1596.2 KEV

INEL

5.83

21.46

47.7

22.07

4.65

24.85

5.9

7.42

100

.18

.22

.5

.23

.05

.25

.06

.08

1

NIM-147;405 (1977)

NIM-147;405 (1977)

NIM-147;405(1977)

NIM-147;405 (1977)

NIM-147;405 (1977)

NIM-147;405(1977)

NIM-147;405 (1977)

NIM-147;405(1977)

NIM-147;405(1977)

LAI 40 HALF LIFE

LABORATORY

IAEA

PTB

NBS

Tl/2

40. 28

40.272

1.6783

UNCERTAINTY

UNIT VALUE REF,

H .006 IJARI-31;153 (1980)

H .007 PTB-INT . REP . MAR 1976

D .0007 NBS PREV. UNPUBL.

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF. 328.8 KEV

PTB

487 KEV

PTB

815.8 KEV

PTB

867.8 KEV

PTB 925.2 KEV

PTB 1596.2 KEV

PTB

20.74

45.94

23.64

5.59

7.05

95.40

,18

.38

,17

,05

,08

,08

NUCL. SCI. NUCL. SCI,

NUCL. SCI. NUCL. SCI.

NUCL. SCI.

NUCL. SCI.

ENG.

ENG.

ENG.

ENG.

ENG.

ENG.

64,784 (1977)

64,784 (1977)

64,784 (1977)

64,784 (1977)

64,784 (1977)

64,784 (1977)

CE141

HALF LIFE

LABORATORY Tl/2

UNCERTAINTY

UNIT VALUE REF. AECL

CBNM

NBS

PTB

32.5

32.5

32.52

32.51

D .03 AECL PREV. UNPUBL.

D .04* IJARI-27;727 (1976)

D .03 NBS PREV. UNPUBL.

D .06 Z. NATURF-26A; 596 (1971)

135
CE141 (CONTINUED)

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF. 145.44 KEV

AECL

CBNM

LMRI

PTB

48.5

48.2

48.44

48.9

,4

.3.42*

.4

AECL-5909 (ICRM-LS-1) (1977)

Z.PHYSIK-A-290;113 (1979)

IJARI-26;179 (1975)

NIM-169;43 (1980)

RELATIVE PHOTON PROBABILITY

LABORATORY P(%) UNCERTAINTY REF.

3 5.8 KEV

UGDP

145 KEV

UGDP

33.4

100

.9

0

NIM-98; 433 (1972)

NIM-98; 433 (1972)

CE144

HALF LIFE

LABORATORY Tl/2

UNCERTAINTY

UNIT VALUE REF.

IAEA

NBS

PTB

285.8

284.9

285.08

D .1 D .5 D .18

IJARI-31; 153 (1980)

NBS PREV. UNPUBL.

PTB-INT. REP . MAR 1976

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF. 133.5 KEV

PTB 11.09 .16 ANN. NUCL. ENERGY 2,37(1974)

RELATIVE PHOTON PROBABILITY

LABORATORY P(%) UNCERTAINTY REF.

80.1 KEV

INEL 133.5 KEV

INEL 696.5 KEV

INEL

1489.1 KEV

INEL

2185.6 KEV

INEL

112

836

100

20.27

52.3

6

25

1

.21

.7

NIM-147;405(1977)

NIM-147;405(1977)

NIM-147 ;405 (1977)

NIM-147;405 (1977)

NIM-147;405 (1977)

EU152

HALF LIFE

LABORATORY Tl/2

UNCERTAINTY

UNIT VALUE REF,

AECL

LMRI NBS

PTB

4892.3 D 8.2 AECL-6788 ; 45 ( 1980

)

13.10 Y .15* IJARI-29;269 (1978)

13.57 Y .11 NBS PREV. UNPUBL.

4931 D 15 NIM-169;43 (1980)

136
EU152 (CONTINUED)

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF.

39.9 KEV

PTB 59.1 1.2 K-ALPHA X-RAY ;NIM 45.7 KEV

PTB 14.9 .3 K-BETA X-RAY ;NIM- 121.8 KEV

LMRI 28.2 .5* CEA-R-4656 (1975)

PTB 28.55 .37 NIM-158;479 (1979)

244.7 KEV

LMRI 7.38 .13* CEA-R-4656 (1975)

PTB 7.44 .11 NIM-158;479 (1979)

344.3 KEV

PTB 26.52 .29 NIM-158;479 (1979)

411.12 KEV

LMRI 2.21 .04* CEA-R-4656 (1975)

PTB 2.24 .04 NIM-158;479 (1979)

444.0 KEV

LMRI 3.076 .05* CEA-R-4656 (1975)

PTB 3.12 .05 NIM-158;479 (1979)

778.9 KEV

LMRI 13.00 .22* CEA-R-4656 (1975)

PTB 12.91 .14 NIM-158;479(1979)

964.0 KEV

LMRI 14.48 .23* CEA-R-4656 (1975)

PTB 14.66 .15 NIM-158;479(1979)

1085.9 KEV

LMRI 10.14 .16* CEA-R-4656 (1975)

PTB 10.09 .13 NIM-158;479 (1979)

1112.1 KEV

LMRI 13.55 .20* CEA-R-4656 (1975)

PTB 13.53 .19 NIM-158;479 (1979)

1408.0 KEV

LMRI 20.70 .29* CEA-R-4656 (1975)

PTB 20.85 .19 NIM-158;479 (1979)

137
EU152 (CONTINUED)

RELATIVE PHOTON PROBABILITY

LABORATORY P(%) UNCERTAINTY REF. 121.8 KEV

INEL 141. 4. NIM-147;405 (1977)

LLL 136.2 1.6 M-100; LAWERENCE LIVERMOP" LAB ; (1978)

244.7 KEV

INEL 36.6 1.1 NIM-147;405(1977)

LLL 35.9 .6 M-100; LAWERENCE LIVERM( ; i (1978)

344.3 KEV

HNRE 127.9 .6 NIM-174;133 (1980) INEL 127.2 1.3 NIM-147;405 (1977)

LLL 127.5 .9 M-100; LAWRENCE LIVERMORE

411.1 KEV

HNRE 10.9 .05 NIM-174;133 (1980) INEL 10.71 .11 NIM-147;405 (1977)

LLL 10.7 .1 M-100 ; LAWRENCE LIVERMORE LAB; 8) 443.9 KEV

HNRE 15.06 .06 NIM-174;133 (1980) INEL 15 .15 NIM-147;405(1977)

LLL 14.8 .2 M-100; LAWRENCE LIVERMORE LAB; (1978)

778.8 KEV

HNRE 62.16 .22 NIM-174;133 (1980)

INEL 62.6 .6 NIM-147;405 (1977)

LLL 61.9 .8 M-100; LAWRENCE LIVERMORE LAB; (1978)

867.3 KEV

HNRE 20.33 .1 NIM-174;133 (1980) INEL 20.54 .21 NIM-147;405 (1977)

LLL 19.9 .4 M-100; LAWRENCE LIVERMORE LAB; (1978)

963.65 KEV

HNRE 70.14 .23 NIM-174;133 (1980) INEL 70.4 .7 NIM-147;405 (1977)

LLL 69.2 .9 M-100 ;LAWRENCE LIVERMORE LAB; (1978)

1085.8 KEV

HNRE 48.15 .16 NIM-174;133 (1980) INEL 48.7 .5 NIM-147;405(1977)

LLL 47.5 .7 M-100; LAWRENCE LIVERMORE LAB; (1978)

1089.7 KEV

HNRE 8.35 .04 NIM-174;133 (1980) INEL 8.26 .09 NIM-147;405 (1977)

LLL 8.2 .1 M-100; LAWRENCE LIVERMORE LAB; (1978)

1112 KEV

HNRE 64.67 .21 NIM-174;133 (1980) INEL 65 .7 NIM-147;405 (1977)

LLL 64.9 .09 M-100 ;LAWRENCE LIVERMORE LAB; (1978)

1212 KEV

HNRE 6.85 .05 NIM-174;133 (1980) INEL 6.67 .07 NIM-147;405 (1977)

LLL 6.7 .08 M-100; LAWRENCE LIVERMORE LAB; (1978)

1299.2 KEV

HNRE 7.8 .05 NIM-174;133 (1980) INEL 7.76 .08 NIM-147;405 (1977)

LLL 7.8 .1 M-100; LAWRENCE LIVERMORE LAB; (1978)

1408 KEV

HNRE 100 .3 NIM-174;133 (1980)

INEL 100 1 NIM-147;405 (1977)

LLL 100 .03 M-100; LAWRENCE LIVERMORE LAB; (1978)

138
EU154

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF

NBS 8.49 Y .11 NBS PREV. UNPUBL.

PTB 8. 57 Y .07 PTB--ANNUAL REPORT; 189 (1978)

PHOTON PROBAB ILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF

123.1 KEV

LLL 40.5 .7 M-100; LAWRENCE LIVERMORE LAB; (1978)

NBS 40.8 .3 NBS PREV. UNPUBL.

248.0 KEV

LLL 7 .11 M-100 ; LAWRENCE LIVERMORE LAB; (1978)

NBS 6.91 .04 NBS PREV. UNPUBL.

591.7 KEV

LLL 5.02 .05 M-100; LAWRENCE LIVERMORE LAB; (1978)

NBS 4.95 .03 NBS PREV. UNPUBL.

692.4 KEV

LLL 1.81 .03 M-100; LAWRENCE LIVERMORE LAB; (1978)

723.3 KEV

T T T Of) ^ M-100; LAWRENCE LIVERMORE LAB; (1978)

NBS 20.08 .12 NBS PREV. UNPUBL.

LLL 4.61 .05 M-100; LAWRENCE LIVERMORE LAB; (1978)

pTO O VT?\7 0 I 3 • Z iSX V LLL 12.3 .1 M-100; LAWRENCE LIVERMORE LAB; (1978)

NBS 12.19 .09 NBS PREV. UNPUBL.

996.3 KEV

LLL 10.7 .1 M-100; LAWRENCE LIVERMORE LAB; (1978)

NBS 10.59 .08 NBS PREV. UNPUBL.

1004.8 KEV

LLL 18.4 .2 M-100; LAWRENCE LIVERMORE LAB; (1978)

NBS 18.08 .11 NBS PREV. UNPUBL.

1274.4 KEV

LLL 35.5 .1 M-100; LAWRENCE LIVERMORE LAB; (1978)

NBS 34.84 .17 NBS PREV. UNPUBL.

1596.5 KEV

LLL 1.82 .03 M-100 ; LAWRENCE LIVERMORE LAB; (1978)

NBS 1.785 .014 NBS PREV. UNPUBL.

RELATIVE PHOTON PROBABILITY

LABORATORY P(%) ============= UNCERTAINTY ===============

REF. =============

591.7 KEV

HNRE 14.35 .06 NIM-174;133 (196 0) 692.4 KEV

HNRE 5.182 .025 NIM-174;133 (19E 0) 723.3 KEV

HNRE 58.19 .21 NIM-174;133 (19£ 0) 756.9 KEV

HNRE 13 .18 .07 NIM-174;133 (196 0) 873.2 KEV

HNRE 35.18 .12 NIM-174;133 (196 0) 904.1 KEV

HNRE 2.62 .03 NIM-174;133 (19£ 0) 996.3 KEV

HNRE 30.09 .12 NIM-174;133 (19£ 0) 1004.8 KEV

HNRE 52.04 .19 NIM-174;133 (19E 0) 1274.4 KEV

HNRE 100 .3 NIM-174;133 (19£ 0) 1596.5 KEV

HNRE 5.247 .026 NIM-174;133 (19E 0)

139
EU155

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF

NBS 4 . 73 Y .02 NBS PREV. UNPUBL.

RELATIVE PHOTON PROBABILITY

LABORATORY P(%) UNCERTAINTY REF. 45.295 KEV

LLL 6.3 .3 M-100; LAWRENCE LIVERMORE LAB; (1978)

60.022 KEV

LLL 5.39 .06 M-100; LAWRENCE LIVERMORE LAB; (1978)

86.554 KEV

LLL 149.6 3 M-100,-LAWRENCE LIVERMORE LAB; (1978)

105.338 KEV

LLL 100 2 M-100 ;LAWRENCE LIVERMORE LAB; (1978)

H0166M

RELATIVE PHOTON PROBABILITY

LABORATORY P (%) UNCERTAINTY REF

80.6 KEV

INEL 21.4 1 .

NIM-147;405 (1977)

184.4 KEV

INEL 128 4 NIM-147;405 (1977)

280.5 KEV

INEL 51 . 5 1 .

NIM-147;405 (1977)

300.7 KEV

INEL 6 .36 . 2 NIM-147;405(1977)

410.9 KEV

INEL 19.55 . 2 NIM-147;405 (1977)

529.8 KEV

INEL 16.36 .16 NIM-147 ; 405 (1977)

571 KEV

INEL 9. 53 . 1 NIM- 147,-405(1977)

670.5 KEV

INEL 9.43 .1 NIM-147,-405 (1977)

711.7 KEV

INEL 95.3 1 NIM-147,-405 (1977)

752.3 KEV

INEL 21.21 .21 NIM-147;405(1977)

810.3 KEV

INEL 100 1 NIM-147;405(1977)

830.6 KEV

INEL 16.97 .17 NIM-147,-405 (1977)

140
YB169

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. AECL 32.015 D .009 AECL-5032;35 (1975)

IAEA 32.022 D .008 IJARI-31;153 (1980)

LHRI 31.97 D .05* IJARI-26;131 (1975)

NBS 32.02 D .01 NBS PREV. UNPUBL.

NPL 32.040 D .004 NPL PREV. UNPUBL.

RELAf JtVE PHOTON PROBABILITY

LABORATORY P(%) UNCERTAINTY REF.

63.1 KEV

INEL

93.7 KEV

INEL

109.8 KEV

INEL

118.1 KEV

INEL

130.5 KEV

INEL

177.2 KEV

INEL

198 KEV

INEL

307.7 KEV

INEL

116

7.1

48.5

5.31

32

62.2

100

27.5

6

.4

1.5

.16

1

1.9

3

.8

NIM-147;405(1977)

NIM-147 ;405 (1977)

NIM-147 ;405 (1977)

NIM-147 ,-405 (1977)

NIM-147 ;405 (1977)

NIM-147;405(1977)

NIM-147;405(1977)

NIM-147;405(1977)

HF180M

HALF LIFE

LABORATORY Tl/2

UNCERTAINTY

UNIT VALUE REF. IAEA 5.519

RELATIVE PHOTON PROBABILITY

LABORATORY P ( %

)

004 IJARI-31;153 (1980)

UNCERTAINTY REF.

93.3 KEV

NPL

215.3 KEV

NPL

332.3 KEV

NPL

443.2 KEV

NPL

21.94

100

117.46

100.72

.1

0

.74

.69

NIM-174;571 (1980)

NIM-174;571(1980)

NIM-174;571 (1980)

NIM-174;571 (1980)

TA182

HALF LIFE

LABORATORY

PTB

Tl/2

114.43

UNCERTAINTY

UNIT VALUE REF.

04 NIM-169;43 (1980)

141
TA182 (CONTINUED)

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF

58.8 KEV

PTB 28.02 .52

67.8 KEV

PTB 57.1 1.3

84.7 KEV

PTB 2.63 .1 100.1 KEV

PTB 14.23 .42

113.7 KEV

PTB 1.87 .06

152.4 KEV

PTB 6.95 .09

156.4 KEV

PTB 2.63 .05

179.4 KEV

PTB 3.09 .04

198.4 KEV

PTB 1 . 44 .02

222.1 KEV

PTB 7.5 . 1 229.3 KEV

PTB 3.64 .05

264.1 KEV

PTB 3.62 .06

1121.3 KEV

PTB 35.3 .32

1189 KEV

PTB 16.44 .15

1221.4 KEV

PTB 27.17 .25

1231 KEV

PTB 11.58 .11

K-ALPHA X-RAY;NIM-169;43 (1980)

UNRESOLVED GAMMA AND K-BETA X- NIM-169;43 (1980)

NIM-169;43 (1980)

NIM-169;43 (1980)

NIM-169;43 (1980)

NIM-169;43 (1980)

NIM-169;43 (1980)

NIM-169;43 (1980)

NIM-169;43 (1980)

NIM-169;43 (1980)

NIM-169;43 (1980)

NIM-169;43 (1980)

NIM-169;43 (1980)

NIM-169;43 (1980)

NIM-169;43 (1980)

NIM-169;43 (1980)

142
TA182 (CONTINUED)

RELATIVE PHOTON PROBABILITY

LABORATORY P(%) UNCERTAINTY REF. 67.8 KEV

INEL 122 6 NIM-147;405 (1977)

LLL 131 10 M-100; LAWRENCE LIVERMORE LAB; (1978)

84.7 KEV

INEL 7.8 .4 NIM-147;405(1977)

LLL 7.19 .14 M-100; LAWRENCE LIVERMORE LAB; (1978)

100.1 KEV

INEL 40.8 1.2 NIM-147;405 (1977)

LLL 40.4 .5 M-100; LAWRENCE LIVERMORE LAB; (1978)

113.7 KEV

INEL 5.43 .17 NIM-147;405 (1977)

LLL 5.34 .05 M-100; LAWRENCE LIVERMORE LAB; (1978)

152.4 KEV

INEL 20.5 .6 NIM-147;405 (1977)

LLL 19.95 .18 M-100; LAWRENCE LIVERMORE LAB; (1978)

156.4 KEV

INEL 7.77 .23 NIM-147;405 (1977)

LLL 7.59 .1 M-100; LAWRENCE LIVERMORE LAB; (1978)

179.4 KEV

INEL 9.1 .28 NIM-147;405 (1977)

LLL 8.82 .1 M-100; LAWRENCE LIVERMORE LAB; (1978)

198.4 KEV

INEL 4.31 .13 NIM-147;405 (1977)

LLL 4.19 .09 M-100; LAWRENCE LIVERMORE LAB; (1978)

222.1 KEV

INEL 21.9 .7 NIM-147;405 (1977) LLL 21.6 .3 M-100; LAWRENCE LIVERMORE LAB; (1978)

229.3 KEV

INEL 10.6 .3 NIM-147;405 (1977)

LLL 10.39 .18 M-100; LAWRENCE LIVERMORE LAB; (1978)

264.1 KEV

INEL 10.5 .3 NIM-147;405 (1977)

LLL 10.26 .18 M-100; LAWRENCE LIVERMORE LAB; (1978)

1121.3 KEV

INEL 100 1 NIM-147;405(1977)

LLL 100 .3 M-100; LAWRENCE LIVERMORE LAB; (1978)

1157.4 KEV

INEL 2.85 .04 NIM-147;405 (1977)

1189 KEV

INEL 46.5 .5 NIM-147;405(1977)

LLL 47.1 .8 M-100; LAWRENCE LIVERMORE LAB; (1978)

1221.4 KEV

INEL 77.8 .8 NIM-147;405(1977)

LLL 77.8 1.3 M-100; LAWRENCE LIVERMORE LAB; (1978)

1231 KEV

INEL 32.96 .33 NIM-147;405(1977)

LLL 33.1 .5 M-100; LAWRENCE LIVERMORE LAB; (1978)

1257.4 KEV

INEL 4.26 .04 NIM-147;405 (1977)

LLL 4.36 .08 M-100 ;LAWRENCE LIVERMORE LAB; (1978)

143
IR192

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. IAEA 73 . 831 D .008 IJARI-31;153 (198

LMRI 74.02 D .18* IJARI-23 ;219 (197

NBS 73 . 81 D .07 NBS PREV. UNPUB.

RELATIVE PHOTON PROBABILITY

LABORATORY =============

P (%) ============== UNCERTAINTY REF.

296 KEV —————————————————

LMRI 36 .

1.0* NPA-142;63 (1970)

INEL 34.64 .35 NP-A204 ; 26 (1973)

308.5 KEV

LMRI 37.4 1.0* NPA-142; 63 (1970)

INEL 35 . 77 .36 NP-A204;26 (1973)

316.5 KEV

LMRI 1000 NPA-142;63 (1970)

INEL 1000 NP-A204;26 (1973)

468.1 KEV

LMRI 57 .

2.0* NPA-142 ; 63 ( 1970) INEL 58

.9 NP-A204 ; 26 (1973)

COO C TJ DT 7 DOO . D KEV

LMRI 5.37 .25* NPA-142;63 (1970) INEL 5.52 .10 NP-A204;26(1973)

604.4 KEV

LMRI 10.0 .4* NPA-142;63 (1970) INEL 10.04 .26 NP-A204;26(1973)

612.5 KEV

LMRI 6.4 .2* NPA-142;63(1970)

INEL 6.55 .13 NP-A204;26 (1973)

AU198

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. AECL 2.6935 D .0004 AECL-5802;43 (1977)

NBS 2.695 D .002 NBS PREV. UNPUB.

NPL 2.695 D .007 IJARI-19;823 (1968)

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF. 411.8 KEV

HNRE 95.56 .08 NIM-175;525(1980)

HG203

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. AECL 46.6 D .01 AECL-4205 ; 21 ( 1972

IAEA 46.582 D .002 IJARI-31 ; 153 ( 1980

NBS 46.62 D .03 NBS PREV. UNPUB.

144
PB203

HALF LIFE

LABORATORY

IAEA

NBS

NPL

BI207

HALF LIFE

LABORATORY

Tl/2

51.88

51.92

51.873

Tl/2

UNCERTAINTY

UNIT VALUE REF.

H .02 IJARI-31;153 (1980)

H .04 NBS PREV. UNPUBL.

H .009 NPL PREV. UNPUBL.

UNCERTAINTY

UNIT VALUE REF. NBS 32.23 Y PHOTON PROBABILITY PER DECAY

.0 NBS PREV. UNPUBL.

569.7 KEV

HNRE

1063.6 KEV

HNRE

1770.2 KEV

HNRE

97.74

74

6.87

.03

.3

.04

NIM-174;109 (1980)

NIM-174;109 (1980)

NIM-174;109 (1980)

RA226

PHOTON PROBABILITY PER DECAY

LABORATORY P ( %

)

UNCERTAINTY REF,

186.0 KEV

PTB

241.9 KEV

PTB

295.2 KEV

PTB

351.9 KEV

PTB 609.3 KEV

PTB 768.4 KEV

PTB

934.05 KEV

PTB

1120.3 KEV

PTB

1238.1 KEV

PTB

1764.5 KEV

PTB

2204.1 KEV

PTB

3.51

7.12

18.15

35.1

44.6

4.75

3.07

14.7

5.78

15.06

4.98

.6

.11

.22

.4

.5

.07

.04

,2

.07

.26

.12

PTB ANN. PTB ANN. PTB ANN. PTB ANN. PTB ANN. PTB ANN. PTB ANN. PTB ANN. PTB ANN. PTB ANN. PTB ANN.REP.

REP.

REP.

REP.

REP.

REP.

REP.

REP.

REP,

REP.

REP.

1977

1977

1977

1977

1977

1977

1977

1977

1977

1977

1977

145
TH228

HALF LIFE

UNCERTAINTY

LABORATORY Tl/2 UNIT VALUE REF. NBS 698.1 D . 5 NBS PREV. UNPUBL.

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF.

583 .2 NBS

727 .

3

NBS

860 .

5

NBS

30.7

6.67

4.55

.3

.06

.04

NBS PREV. UNPUBL.

NBS PREV. UNPUBL.

NBS PREV. UNPUBL.

RELATIVE PHOTON PROBABILITY

LABORATORY P(%) UNCERTAINTY REF. 583.2 KEV

INEL

860.5 KEV

INEL

2614.5 KEV

INEL

100

14.79

118.5

1

.15

1.6

NIM-147;405 (1977)

NIM-147;405 (1977)

NIM-147;405 (1977)

AM241

HALF LIFE

LABORATORY Tl/2

UNCERTAINTY

UNIT VALUE REF. PTB 432 Y .2 IJARI-26;589(1975)

PHOTON PROBABILITY PER DECAY

LABORATORY P(%) UNCERTAINTY REF.

26.3LMRI

59.5LMRI NBS

2.35

36.5

35.82

.07*

.2*

.14

LMRI PREV. UNPUBL.

LMRI PREV. UNPUBL.

NBS PREV. UNPUBL.

146
NBS-114A IREV. 2-8CI U.S. DEPT. OF COMM. BIBLIOGRAPHIC DATA

SHEET (See instructions)

1. PUBLICATION OR

REPORT NO. NBS SP 626

2. Performing Organ. Report No. 3. Publication Date

January 1982

4. title and SUBTITLE Nuclear Data for the Efficiency Calibration of Germanium

Spectrometer Systems: Measurements from the Laboratories of the International Committee

for Radionuclide Metrology a-, and y-Ray Spectrometry Group

5. AUTHOR(S)

D.D. Hoppes and F.J. Schima, Editors

6. PERFORMING ORGANIZATION (If joint or other than NBS. see instructions)

NATIONAL BUREAU OF STANDARDS

DEPARTMENT OF COMMERCE

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8. Type of Report & Period Covered

Final

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Same as #6.

10. SUPPLEMENTARY NOTES

Library of Congress Catalog Card Number: 81-600161

^ Document describes a computer program; SF-185, FlPS Software Summary, is attached.

11. ABSTRACT (A 200-word or less factual summary of most significant Information. If document includes a significant

bibliography or literature survey, mention it here) Members of the Alpha-, Beta-, and Gamma-Ray Spectrometry Group of the

International Committee for Radionuclide Metrology agreed in 1979 to

collect the nuclear data from any measurements in their laboratories

that were pertinent to the calibration of the efficiency of germanium

spectrometer systems. This report is composed of the contributions

from 14 laboratories, as listed in part II. If a self-contained con- tribution was received, it has been incorporated without editing. Less

formal communications, or references to published articles, are discussed

in short comments prepared by the compilers. Part IV is a compilation

of a selected portion of the data, arranged by radionuclide.

12. KEY WORDS (Six to twelve entries; alphabetical order; capitalize only proper names; and separate key words by semicolon s) compilation; efficiency data; half lives; measurement uncertainties; photon

probabilities per decay; relative photon-emission probabilities

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