ASTM E244-80(1995)

Test Method for Atom Percent Fission in Uranium and Plutonium Fuel (Mass Spectrometric Method) (Withdrawn 2001)

SCOPE
1.1 This test method covers the determination of the heavy element atom percent fission in irradiated uranium (U) fuel with initial plutonium (Pu) content from 0 to 50% from isotopic analyses of the fuel before and after irradiation (1,2).  
1.2 The test method specifies the computational procedures for handling mass spectrometric analyses. Chemical separation procedures and mass spectrometer operation procedures are specified in Test Method E267.  
1.3 The test method is applicable to thermal-reactor U and Pu fuels but does not apply to fuels containing thorium or    U before irradiation.  
1.4 The determination of burnup from changes in isotopic composition has several requirements that limit its usefulness and accuracy. The most obvious requirement is the availability of a pre-irradiation specimen which truly represents the sample to be analyzed. A second limiting requirement is the availability of correct neutron-spectrum-dependent reactor parameters, especially capture-to-fission ratios for    U,    Pu, and    Pu. Finally, many additional factors implicitly assumed to be negligible in this treatment become significant at high exposures.  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

General Information

• Status: Withdrawn
• Publication Date: 26-Feb-1997
• Withdrawal Date: 09-Jun-2001
• ICS: 27.120.30 - Fissile materials and nuclear fuel technology
• Technical Committee: C26 - Nuclear Fuel Cycle
• Drafting Committee: C26.05 - Methods of Test

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or
withdrawn. Contact ASTM International (www.astm.org) for the latest information.
Designation: E 244 – 80 (Reapproved 1995)
AMERICAN SOCIETY FOR TESTING AND MATERIALS
100 Barr Harbor Dr., West Conshohocken, PA 19428
Reprinted from the Annual Book of ASTM Standards. Copyright ASTM
Standard Test Method for
Atom Percent Fission in Uranium and Plutonium Fuel (Mass
1
Spectrometric Method)
This standard is issued under the fixed designation E 244; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (e) indicates an editorial change since the last revision or reapproval.
1. Scope 3.1.2 heavy element atom percent fission—the number of
fissions per 100 U plus Pu atoms initially present in a nuclear
1.1 This test method covers the determination of the heavy
fuel.
element atom percent fission in irradiated uranium (U) fuel
3.2 Symbols:Symbols—Symbols used in the procedural
with initial plutonium (Pu) content from 0 to 50 % from
2
isotopic analyses of the fuel before and after irradiation (1,2). equations are defined as follows:
1.2 The test method specifies the computational procedures
for handling mass spectrometric analyses. Chemical separation
F , F ,F , F 5 heavy element atom percent fis-
5 9 1 8
procedures and mass spectrometer operation procedures are
sion from fission
specified in Test Method E 267.
235 239 241
of U, Pu, Pu,
1.3 The test method is applicable to thermal-reactor U and
238
and U.
233
Pu fuels but does not apply to fuels containing thorium or U
F 5 total heavy element atom percent
T
before irradiation.
fission.
1.4 The determination of burnup from changes in isotopic
0 0
N , N 5 heavy element atom
8 5
composition has several requirements that limit its usefulness
238 235
percent U and U, in the
and accuracy. The most obvious requirement is the availability
pre-irradiated fuel.
of a pre-irradiation specimen which truly represents the sample
0 0 0 235
R , R , R 5 atoms ratios of U
5/8 6/8 6/5
to be analyzed. A second limiting requirement is the availabil- 238 236 238
to U,Uto U,
ity of correct neutron-spectrum-dependent reactor parameters,
236 235
and Uto U in the pre-
235 239 241
especially capture-to-fission ratios for U, Pu, and Pu.
irradiated fuel.
Finally, many additional factors implicitly assumed to be 235
R , R , R 5 atom ratios of U
5/8 6/8 6/5
238 236 238
negligible in this treatment become significant at high expo-
to U,Uto U,
sures. 236 235
and Uto U in the final
1.5 This standard does not purport to address all of the
irradiated sample.
239
safety concerns, if any, associated with its use. It is the
R , R , R , R 5 atom ratios of Pu,
9/8 0/8 1/8 2/8
240 241 242
responsibility of the user of this standard to establish appro-
Pu, Pu, and Pu
238
priate safety and health practices and determine the applica-
to U in the final irradiated
bility of regulatory limitations prior to use.
sample.
241 238
R8 5 atom ratio of Pu to Uin
2. Referenced Documents 1/8
the final irradiated sample cor-
2.1 ASTM Standards:
rected for neutron capture, fis-
E 267 Test Method for Uranium and Plutonium Concentra-
sion, and decay during and after
3
tions and Isotopic Abundances
irradiation.
3. Terminology n 5 2.67 6 0.30 neutrons per fission
8
238
of U (3).
3.1 Definitions:
n 5 2.426 6 0.006 neutrons per fis-
5
3.1.1 gigawatt days per metric ton—the gigawatt days of
235
sion of U (4).
heat produced per metric ton of U plus Pu initially present in
n /n 5 ratio of number of neutrons per
9 5
a nuclear fuel.
239
fission of Pu
235
to U 5 1.192 6 0.005 (4).
1
This test method is under the jurisdiction of ASTM Committee C-26 on Nuclear
n /n 5 ratio of number of neutrons per
1 5
Fuel Cycle.
241
fission of Pu
Current edition approved Sept. 26, 1980. Published November 1980. Originally
235
published as E 244 – 64 T. Last previous edition E 244 – 69 (1974). to U 5 1.237 6 0.017 (4).
2
The boldface numbers in parentheses refer to the list of references appended to
t8 5 elapsed time from the end of
this method.
irradiation to measurement.
3
Annual Book of ASTM Standards, Vol 12.02.
1

---------------------- Page: 1 ----------------------
E 244
t 5 irradiation time, s. r 5 epithermal index which is a mea-
l 5 decay constant of
sure of the proportion of epither-
1
241 −9 −1
Pu 5 1.53 3 10 s . mal neutrons in a reactor spec-
238
c 5 ratio of the U fission rate to
trum. In Ref (7), r is defined and
the fission rate from all other
related mathematically to the
sources expressed as
cadmium ratio. Note that for
235
equivalent U fission rate.
r 5 0 the spectrum is pure Max-
e5 fast fission factor [defined in Ref
wellian.
2
(5)] which is 1.00 for fully en-
f5 neutron flux, neutrons/cm -s.
riched reactors. Typically, e
s , s , s 5 total neutron absorption cross
1 5 6
241 235
ranges from 1.03 to 1.07 for l
...