ENSDF Decay Data in the MIRD
(Medical Internal Radiation Dose) Format
for 153Gd

64-GADOLINIUM-153 64-GADOLINIUM-153M
Additional Views or Possible Data Parent Information

64-GADOLINIUM-153

Halflife = 240.4 Days Apr-1998
Decay Mode: EC
Radiations


y(i)
(Bq-s)-1


E(i)
(MeV)


y(i)E(i)

gamma 5 2.4210-02 6.96710-02 1.6910-03
ce-K, gamma 5 1.0810-01 2.11510-02 2.2910-03
ce-L, gamma 5 1.7710-02 6.16210-02 a 1.0910-03
ce-M, gamma 5 3.8510-03 6.78710-02 a 2.6110-04
ce-N+, gamma 5 1.0910-03 6.93110-02 a 7.5310-05
gamma 7 1.9610-03 8.33710-02 1.6310-04
ce-K, gamma 7 4.6510-03 3.48510-02 1.6210-04
ce-L, gamma 7 2.2210-03 7.53210-02 a 1.6710-04
ce-M, gamma 7 5.0610-04 8.15710-02 a 4.1310-05
ce-K, gamma 8 1.4910-03 4.09710-02 6.1010-05
gamma 10 2.9010-01 9.74310-02 2.8310-02
ce-K, gamma 10 7.4810-02 4.89110-02 3.6610-03
ce-L, gamma 10 1.1110-02 8.93810-02 a 9.9510-04
ce-M, gamma 10 2.3810-03 9.56310-02 a 2.2810-04
ce-N+, gamma 10 6.6410-04 9.70710-02 a 6.4510-05
gamma 11 2.1110-01 1.03210-01 2.1810-02
ce-K, gamma 11 3.0610-01 5.46610-02 1.6710-02
ce-L, gamma 11 4.5610-02 9.51310-02 a 4.3410-03
ce-M, gamma 11 9.8810-03 1.01410-01 a 1.0010-03
ce-N+, gamma 11 2.8510-03 1.02810-01 a 2.9310-04
Kalpha1 X-ray 6.2510-01 4.15410-02 2.6010-02
Kalpha2 X-ray 3.4710-01 4.09010-02 1.4210-02
Kbeta X-ray 2.4810-01 4.70010-02 * 1.1710-02
L X-ray 2.2710-01 5.85010-03 * 1.3310-03
Auger-K 9.2710-02 3.37010-02 * 3.1210-03
Auger-L 1.12 4.69010-03 * 5.2510-03

Listed X, gamma, and gamma Radiations 1.0510-01
Omitted X, gamma, and gamma Radiations** 2.0410-04
Listed beta, ce, and Auger Radiations 3.9810-02
Omitted beta, ce, and Auger Radiations** 1.2810-04
Listed Radiations 1.4510-01
Omitted Radiations** 3.3210-04

*   Average Energy (MeV).
a   Maximum Energy (MeV) for subshell.
** Each omitted transition contributes <0.100% to Sumof y(i)E(i).


Europium-153 Daughter is stable.





64-GADOLINIUM-153M

Halflife = 76.0 Microsec Apr-1998
E(excitation) = 0.1712 MeV
Decay Modes: IT, IT
Radiations


y(i)
(Bq-s)-1


E(i)
(MeV)


y(i)E(i)

gamma 1 3.0610-01 1.83010-03 5.6010-04
gamma 2 9.9910-01 1.83010-03 1.8310-03
gamma 3 5.2210-01 2.80010-03 1.4610-03
gamma 4 9.0010-02 4.15610-02 3.7410-03
gamma 5 9.0010-02 4.15610-02 3.7410-03
gamma 6 4.5010-02 5.17810-02 2.3310-03
ce-K, gamma 6 5.1710-01 1.54110-03 7.9710-04
ce-L, gamma 6 1.0110-01 4.34010-02 a 4.3910-03
ce-M, gamma 6 2.2410-02 4.99010-02 a 1.1210-03
ce-N+, gamma 6 6.4410-03 5.14010-02 a 3.3110-04
gamma 7 4.5010-02 5.17810-02 2.3310-03
gamma 8 3.6010-02 7.50710-02 2.7010-03
ce-K, gamma 8 1.1210-01 2.48310-02 2.7710-03
ce-L, gamma 8 8.2810-02 6.66910-02 a 5.5210-03
ce-M, gamma 8 1.8010-02 7.31910-02 a 1.3210-03
ce-N+, gamma 8 5.4010-03 7.46910-02 a 4.0310-04
gamma 9 1.8910-01 7.60110-02 1.4410-02
ce-K, gamma 9 9.6810-02 2.57710-02 2.4910-03
ce-L, gamma 9 1.5210-02 6.76310-02 a 1.0310-03
ce-M, gamma 9 3.2710-03 7.41310-02 a 2.4210-04
ce-N+, gamma 9 9.1110-04 7.56310-02 a 6.8910-05
gamma 10 2.2510-02 7.79010-02 1.7510-03
ce-K, gamma 10 4.8410-02 2.76610-02 1.3410-03
ce-L, gamma 10 7.5610-02 6.95210-02 a 5.2610-03
ce-M, gamma 10 1.7710-02 7.60210-02 a 1.3510-03
ce-N+, gamma 10 4.8810-03 7.75210-02 a 3.7910-04
gamma 11 9.9010-03 9.33410-02 9.2410-04
ce-K, gamma 11 1.4010-02 4.31010-02 6.0210-04
ce-L, gamma 11 1.4410-02 8.49610-02 a 1.2210-03
ce-M, gamma 11 3.3610-03 9.14610-02 a 3.0710-04
ce-N+, gamma 11 9.4110-04 9.29610-02 a 8.7410-05
gamma 12 9.9010-03 9.33410-02 9.2410-04
gamma 13 6.3010-03 1.26810-01 7.9910-04
ce-K, gamma 13 3.8210-03 7.66110-02 2.9310-04
ce-L, gamma 13 2.2910-03 1.18510-01 a 2.7110-04
ce-M, gamma 13 5.2910-04 1.25010-01 a 6.6110-05
gamma 1 3.0610-01 1.83010-03 5.6010-04
gamma 2 9.9910-01 1.83010-03 1.8310-03
gamma 3 5.2210-01 2.80010-03 1.4610-03
gamma 4 9.0010-02 4.15610-02 3.7410-03
gamma 5 9.0010-02 4.15610-02 3.7410-03
gamma 6 4.5010-02 5.17810-02 2.3310-03
ce-K, gamma 6 5.1710-01 1.54110-03 7.9710-04
ce-L, gamma 6 1.0110-01 4.34010-02 a 4.3910-03
ce-M, gamma 6 2.2410-02 4.99010-02 a 1.1210-03
ce-N+, gamma 6 6.4410-03 5.14010-02 a 3.3110-04
gamma 7 4.5010-02 5.17810-02 2.3310-03
gamma 8 3.6010-02 7.50710-02 2.7010-03
ce-K, gamma 8 1.1210-01 2.48310-02 2.7710-03
ce-L, gamma 8 8.2810-02 6.66910-02 a 5.5210-03
ce-M, gamma 8 1.8010-02 7.31910-02 a 1.3210-03
ce-N+, gamma 8 5.4010-03 7.46910-02 a 4.0310-04
gamma 9 1.8910-01 7.60110-02 1.4410-02
ce-K, gamma 9 9.6810-02 2.57710-02 2.4910-03
ce-L, gamma 9 1.5210-02 6.76310-02 a 1.0310-03
ce-M, gamma 9 3.2710-03 7.41310-02 a 2.4210-04
ce-N+, gamma 9 9.1110-04 7.56310-02 a 6.8910-05
gamma 10 2.2510-02 7.79010-02 1.7510-03
ce-K, gamma 10 4.8410-02 2.76610-02 1.3410-03
ce-L, gamma 10 7.5610-02 6.95210-02 a 5.2610-03
ce-M, gamma 10 1.7710-02 7.60210-02 a 1.3510-03
ce-N+, gamma 10 4.8810-03 7.75210-02 a 3.7910-04
gamma 11 9.9010-03 9.33410-02 9.2410-04
ce-K, gamma 11 1.4010-02 4.31010-02 6.0210-04
ce-L, gamma 11 1.4410-02 8.49610-02 a 1.2210-03
ce-M, gamma 11 3.3610-03 9.14610-02 a 3.0710-04
ce-N+, gamma 11 9.4110-04 9.29610-02 a 8.7410-05
gamma 12 9.9010-03 9.33410-02 9.2410-04
gamma 13 6.3010-03 1.26810-01 7.9910-04
ce-K, gamma 13 3.8210-03 7.66110-02 2.9310-04
ce-L, gamma 13 2.2910-03 1.18510-01 a 2.7110-04
ce-M, gamma 13 5.2910-04 1.25010-01 a 6.6110-05
Kalpha1 X-ray 1.8210-03 4.30010-02 7.8410-05
Kalpha2 X-ray 1.0110-03 4.23110-02 4.2910-05

Listed X, gamma, and gamma Radiations 3.7610-02
Omitted X, gamma, and gamma Radiations** 4.1410-05
Listed beta, ce, and Auger Radiations 3.1710-02
Omitted beta, ce, and Auger Radiations** 5.0010-05
Listed Radiations 6.9210-02
Omitted Radiations** 9.1410-05

a   Maximum Energy (MeV) for subshell.
** Each omitted transition contributes <0.100% to Sumof y(i)E(i).


Gadolinium-153 Daughter is radioactive.
Gadolinium-153 Daughter is radioactive.





This program and the accompanying data base have been produced by the National Nuclear Data Center located at the Brookhaven National Laboratory, Upton, N.Y., USA, with funding from the U.S. Department of Energy. Neither the BNL nor the USDOE make any warranty or assume any legal responsibility for the contents of the data base.
Generated by MIRD Wed May 17 9:28:10 2000

Additional Views or Possible Data for the Parent 153Gd
CSISRS Experimental neutron-induced reaction data in the Exchange Format (EXFOR)
153Gd CS List production cross section datasets
ENSDF Evaluated Nuclear Structure Data File
ENSDF All decay datasets for the parent. Isotope Explorer may be used as a helper to view these data on Win95/98/NT platforms. (22.4 kbytes)
Table Simple HTML tables of information contained in the decay datasets (Est. size: 19.3 kbytes.)
Drawing PostScript file of the decay schemes in the Nuclear Data Sheets style (Est. size: 79.6 kbytes.)
MIRD PostScript files of the tables and decay schemes in the MIRD format
NSR Nuclear Science References
NuDat Nuclear Data File
Wallet Ground and metastable state properties
Radiations Decay Radiations

Parent Decays Feeding 153Gd
Parent Mode
153Gd IT
153Tb beta+/EC