RUSSIA NUCLEAR DATA CENTER - RNDC
Alias: CENTR JADERNYKH DANNYKH - CJD
Institute for Physics and Power Engineering - IPPE
Bondarenko Sq., 1, Obninsk 249033, Kaluga Region, RUSSIA
Telephone:+7 (48439)98779 (M.Mikhaylyukova)
Fax:+7 (48439)68225
Web-site:www.ippe.ru/podr/cjd

MEMO 4C-4/198
Date:
To:
From:
Subject:

12 April 2012
Distribution
M.Mikhaylyukova (CJD), N.Soppera (NEA DB)
INC-SOURCE coding. For NRDC2012 discussion.

According to the EXFOR manual:“INC-SOURCE. Gives information on the source of the incident particle beam used in the experiment.”
If there is no incident particles ( e.g. spontaneous fission), this code INC-SOURCE has not to be used.
Nicolas Soppera checked EXFOR-2011-12-15 master file in December 2011 and the latest EXFOR-2012-0328 for this rule – result is given in Table below.
From December 2011 – 11 Subentries were corrected for area 4:40472.002, .003; 40535.002; 40644.002; 41421.002, .003 , .004, .005; 41421.007; 41516.020, .021 .
Statistics of March 2012:
area 1 – 31 Subents,
area 2 – 118 Subents,
area 3 – 15 Subents,
area 4 – 51 Subents.
Proposal:
1. Correct (when time permits) these affected Entries by possible ways:a) move free text information in SAMPLE lines,b) move INC-SOURCE in relevant Subents, where it was used as incident beam source,c) delete INC-SOURCE, if there is no incident beam.
2. Add in EXFOR manual, chapter 7.15, INC-SOURCE:“4. INC-SOURCE has not to be used for reactions, where there is no incident particle (SF2=0), for examplespontaneous fission.”Table of affected Subents.
Subentry

REACTION

10125.006 (96-CM-244(0,F),PR,NU)/(98-CF252(0,F),PR,NU)
12856.003 ELEM/MASS(0,B-),,PN
12946.002
13075.004
13223.003
13981.002
14008.002
14008.003
14008.004
14055.002
14055.003
14055.004
14064.002
14065.002
14065.003
14065.004
14065.005
14065.006
14065.007
14065.008
14065.009
14065.010
14066.002
14066.003
14066.004

ELEM/MASS(0,B-),,PN
92-U-238(0,F)40-ZR-95,CUM,FY
92-U-238(0,F)ELEM/MASS,CUM,FY
104-RF-262(0,F)MASS,MAS,FY
103-LR-259(0,F),PRE,DE,LF/HF,REL
103-LR-259(0,F)MASS,PRE,FY
103-LR-259(0,F)MASS,CHN,FY
102-NO-256(0,F),TER,DE,A,REL
88-RA-214(0,F),TER,DE,A,REL
102-NO-256(0,F)MASS,PRE,DE,LF+HF,REL
98-CF-252(0,F)NPART,NUM,NU
98-CF-252(0,F)MASS,,NU
98-CF-252(0,F)MASS,,AKE,N
98-CF-252(0,F)MASS,PAR,NU,FF
98-CF-252(0,F),PAR,NU,FF
98-CF-252(0,F)MASS,PAR,NU,FF
98-CF-252(0,F),PAR,AKE,N/FF
98-CF-252(0,F)MASS,PAR,AKE,N/FF
98-CF-252(0,F)MASS,PAR,NU,FF,REL
98-CF-252(0,F)MASS,PAR,AKE,N/FF
98-CF-252(0,F),TER,DA,A,REL
98-CF-252(0,F),TER,DA/DE,A,REL
98-CF-252(0,F),TER,DE,A,REL

Code,[free text] of INC-SOURCE( “null” means that only free text is given)

REAC,[Collimated thermal beam, 3.0*(10**7) neutrons/cm**2*sec]
REAC,[BNL
HIGH-FLUXBEAM
REACTOR-THERMAL
NEUTRON BEAM]
REAC,[ BNL HFBR]
D-T,[]
D-T,[]
null,[244Pu(22Ne,4n) reaction]
null,[248Cm(15N,4n) reaction.]null,[248Cm(15N,4n) reaction.]null,[248Cm(15N,4n) reaction.]null,[Target produced by 248Cm(12C,4n) reaction]
null,[Target produced by 248Cm(12C,4n) reaction]
null,[Target produced by 248Cm(12C,4n) reaction]
CF252,[ Spontaneous fission]
CF252,[ Spontaneous fission source]
CF252,[ Spontaneous fission source]
CF252,[ Spontaneous fission source]
CF252,[ Spontaneous fission source]
CF252,[ Spontaneous fission source]
CF252,[ Spontaneous fission source]
CF252,[ Spontaneous fission source]
CF252,[ Spontaneous fission source]
CF252,[ Spontaneous fission source]
CF252,[ Spontaneous fission]
CF252,[ Spontaneous fission]
CF252,[ Spontaneous fission]

Comment.
*
insertedalready inerror list at
NDS website

14066.005
14066.006
14079.002
14259.008

98-CF-252(0,F),TER,DA/DE,A,REL
98-CF-252(0,F),TER,DA/DE,A,REL
98-CF-252(0,F)ELEM/MASS,CUM,FY
98-CF-252(0,F)MASS,PRE,FY

14259.009 98-CF-252(0,F)MASS,SEC,FY

14259.010 98-CF-252(0,F),PRE,FY/DE

20401.002
20401.003
20401.004
20575.007

98-CF-252(0,F),PR,AKE,N
98-CF-252(0,F),PR,DE,N
98-CF-252(0,F),PR,DE,N
98-CF-252(0,F),,AKE,N

CF252,[ Spontaneous fission]
CF252,[ Spontaneous fission]
CF252,[ Spontaneous fission of Cf252]
PHOTO,[Neutrons were produced through a (gamma,n), reaction whenelectrons from the RPI 60-MeV electron, linac interact with a tantalum
target, placed in the, center of lead slowing down spectrometer.The
linac was, run at an average electron current of 8 mu-A,, delivering 58MeV electrons in a pulse width of 200 ns, at 180 Hz.The neutronenergy and flux are experimentaly, known functions of slowing downtime and electron beam, intensity. The neutron-energy resolution(FWHM)] in, the energy range of 0.1 eV to 1 keV was, approximately
35%.]
PHOTO,[Neutrons were produced through a (gamma,n), reaction whenelectrons from the RPI 60-MeV electron, linac interact with a tantalum
target, placed in the, center of lead slowing down spectrometer.The
linac was, run at an average electron current of 8 mu-A,, delivering 58MeV electrons in a pulse width of 200 ns, at 180 Hz.The neutronenergy and flux are experimentaly, known functions of slowing downtime and electron beam, intensity. The neutron-energy resolution(FWHM)] in, the energy range of 0.1 eV to 1 keV was, approximately
35%.]
PHOTO,[Neutrons were produced through a (gamma,n), reaction whenelectrons from the RPI 60-MeV electron, linac interact with a tantalum
target, placed in the, center of lead slowing down spectrometer.The
linac was, run at an average electron current of 8 mu-A,, delivering 58MeV electrons in a pulse width of 200 ns, at 180 Hz.The neutronenergy and flux are experimentaly, known functions of slowing downtime and electron beam, intensity. The neutron-energy resolution(FWHM)] in, the energy range of 0.1 eV to 1 keV was, approximately
35%.]
CF252,[SPONTANEOUS FISSION OF CF-252.]
CF252,[SPONTANEOUS FISSION OF CF-252.]
CF252,[SPONTANEOUS FISSION OF CF-252.]
P-LI7,[FOR THE MEASUREMENTS ON U-235 AND PU-239, AT
40 KEV, REACTION LI-7(P,N) INDUCED BY 2 MEV, PROTONSIN A THIN LITHIUM METAL TARGET WAS USED.]P-

20575.008 98-CF-252(0,F),,DE,N,REL

20616.006 98-CF-252(0,F),PAR,AKE,N
20616.007 98-CF-252(0,F),,DE,N20711.004 (98-CF-250(0,F),CUM,FY)/(98-CF250(0,F),CHN,FY)
20878.002 (98-CF249(0,F)ELEM/MASS,CUM,FY,,MXW)/(98CF-249(0,F)MASS,CHN,FY,,MXW)
20878.003 (98-CF-250(0,F)ELEM/MASS,CUM,FY)/(98CF-250(0,F)MASS,CHN,FY)
20954.003 94-PU-240(0,F),,AKE,FF
21252.003 (94-PU-240(0,F),PR,NU)/(98-CF252(0,F),PR,NU)
94-PU-240(0,F),PR,NU

21393.004 92-U-235(0,F)ELEM/MASS,CUM,FY
21453.006 92-U-238(0,F),PR,NU

21454.009 98-CF-252(0,F),PR,NU

T ,[FOR THE MEASUREMENTS ON U-235 AT 1.5 MEV,,REACTION T(P,N) IN A THIN ADSORBED TRITIUM-TITANIUM,
TARGET.]
P-LI7,[FOR THE MEASUREMENTS ON U-235 AND PU-239, AT
40 KEV, REACTION LI-7(P,N) INDUCED BY 2 MEV, PROTONSIN A THIN LITHIUM METAL TARGET WAS USED.]PT ,[FOR THE MEASUREMENTS ON U-235 AT 1.5 MEV,,REACTION T(P,N) IN A THIN ADSORBED TRITIUM-TITANIUM,
TARGET.]THCOL,[ THERMAL COLUMN OF KFK RESEARCH REACTORFR2.]
THCOL,[ THERMAL COLUMN OF KFK RESEARCH REACTOR
FR2.]REAC,[TRIGA RESEARCH REACTOR OF MAINZ (3E+10,
THERMAL NEUTRONS PER CM2 AND SEC..]
REAC,[THERMAL MAXWELLIAN FLUX, EXCEPT FOR,SPONTANEOUS FISSION VALUES.]
REAC,[ THERMAL MAXWELLIAN FLUX, EXCEPT FOR,SPONTANEOUS FISSION VALUES.]THCOL,[ THERMAL COLUMN OF THE BR 1 REACTOR.]
P-T ,[ 1.3 MEV PROTONS ON TRITIUM-ZIRCONIUM TARGET,FOR 75 KEV DEUTERONS.]
D-D ,[ 1.0 MEV DEUTERONS ON DEUTERIUM-ZIRCONIUM,
TARGET FOR 2.5 MEV NEUTRONS.]
D-T ,[ 1.0 MEV DEUTERONS ON TRITIUM-ZIRCONIUM,
TARGET FOR 14.2 MEV NEUTRONS.
REAC,[ REACTOR NEUTRONS AND SPONTANEOUS FISSION.]
D-T,[DEUTERON-TRITIUM
REACTIONIN
TRITIUMTITANIUM, TARGET FOR THE PRODUCTION OF 14.2 MEV
NEUTRONS.]
REAC,[ FOR THE MAXWELLIAN NEUTRON SPECTRUM AND
FOR, THE EXTRACTION OF THE MONOCHROMATIC 0.0253
EV-BEAM., .U-235(N,F)-REACTION FOR THE CREATION OF
THE FISSION, NEUTRON SPECTRUM. A 3 MM THICK LAYER
OF 20 PERCENT, ENRICHMENT WAS USED.]REAC,[FOR THE THERMAL NEUTRONS.]

21454.010 98-CF-252(0,F),PR,NU

21465.002 98-CF-252(0,F),PR,DE,N21495.002 94-PU-240(0,F),PR,NU
21531.003 98-CF-252(0,F)MASS,CHN,FY
21531.005 (98-CF-252(0,F)ELEM/MASS,IND,FY)/(98CF-252(0,F)ELEM/MASS,CHN,FY)
21615.002 92-U-238(0,F),,AKE,FF

21686.003 (98-CF-250(0,F)ELEM/MASS,CUM,FY)/(98CF-250(0,F)MASS,CHN,FY)
21696.007 94-PU-240(0,F),PR,NU
21788.003 94-PU-242(0,F),SEC,AKE,LF+HF
21788.004 94-PU-244(0,F),SEC,AKE,LF+HF
21788.006 94-PU-242(0,F),SEC,AP,LF
21788.007 94-PU-244(0,F),SEC,AP,LF
21895.002
21895.004
21915.002
21915.003
21995.006

94-PU-240(0,F),SEC,AKE,LF+HF
94-PU-240(0,F),PRV,AP,LF
94-PU-242(0,F),SEC,AKE,LF+HF
94-PU-242(0,F),PRV,AP,LF
94-PU-240(0,F),SEC,AKE,LF+HF

21995.008 94-PU-240(0,F),PRE,AKE,LF

P-T,[ PROTON-TRITIUM REACTION AND]P-LI7,[PROTON-LITHIUM REACTION FOR FAST NEUTRONS.]
REAC,[FOR THE THERMAL NEUTRONS.]
P-T,[PROTON-TRITIUM REACTION AND]P-LI7,[PROTON-LITHIUM REACTION FOR FAST NEUTRONS.]
CF252,[ THE IAEA CF-252 NEUTRON SOURCE CONSISTS OF,A CYLINDRICAL CAPSULE WITH AN OUTER LENGTH OF 22.0,
MM AND AN EXTERNAL DIAMETER OF 2.80 MM, STRENGTH,CALIBRATED AGAINST A STANDARD CF-252 SOURCE.]
null,[.NO DETAILS GIVEN.]
REAC,[THERMAL NEUTRON SPECTRUM FOR U-235,
SPONTANEOUS, FISSION FOR CF-252.]
REAC,[THERMAL NEUTRON SPECTRUM FOR U-235,
SPONTANEOUS, FISSION FOR CF-252.]
A-BE,[AN AM-BE NEUTRON SOURCE, THERMALIZED BY A,
PARAFFIN WALL OF 30 CM THICKNESS, USED FOR
SATURATIONCHARACTERISTICSAND
ENERGYCALIBRATION.]REAC ,[]*
D-T,[ 500 KEV DEUTERON BEAM ON TRITIUM TARGET.]
null,[.Thermal neutrons were selected by time-of-flight, out of themoderated N-spectrum produced by GELINA.]
null,[.Thermal neutrons were selected by time-of-flight, out of themoderated N-spectrum produced by GELINA.]
null,[.Thermal neutrons were selected by time-of-flight, out of themoderated N-spectrum produced by GELINA.]
null,[.Thermal neutrons were selected by time-of-flight, out of themoderated N-spectrum produced by GELINA.]
REAC,[]REAC,[]REAC,[A well-thermalized and collimated beam from, the reactor.]
REAC,[A well-thermalized and collimated beam from, the reactor.]
PU240,[ Spontaneous Fission]REAC,[ Well Thermalized Neutron
Beams 10**6, Neutrons/Cm2 Sec]PU240,[Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]

21995.009 94-PU-240(0,F),PRE,AP,LF
21995.013 94-PU-240(0,F),PRE,AKE,LF+HF
21995.015 94-PU-240(0,F),PRE,AKE,HF
21995.017 94-PU-240(0,F),PRE,AP,HF
21995.020 94-PU-240(0,F),SEC,AKE,LF+HF,,DERIV
21995.021 94-PU-240(0,F),PRE,AKE,LF+HF,,DERIV
21995.022 94-PU-240(0,F),PRE,AKE,LF,,DERIV
21995.023 94-PU-240(0,F),PRE,AKE,HF,,DERIV
21995.024 94-PU-240(0,F),PRE,AP,LF,,DERIV
21995.025 94-PU-240(0,F),PRE,AP,HF,,DERIV
21995.027 94-PU-240(0,F)MASS,PRE,FY
21995.029 94-PU-240(0,F),PRE,FY/DE
21995.031 94-PU-240(0,F)MASS,PRE,FY/DE
21995.032 94-PU-240(0,F)MASS,PRE,FY/DE
21995.033 94-PU-240(0,F),PRE,FY/DE,,,DERIV
21995.037 94-PU-240(0,F)MASS,PRE,KE,FF
21995.039 94-PU-240(0,F)MASS,PRE,KE,FF
22137.002 94-PU-236(0,F),PRE,AKE,FF
22137.003 94-PU-236(0,F),PRE,AP,HF
22137.004 94-PU-236(0,F),PRE,AP,LF

PU240,[Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]PU240,[Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]PU240,[Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]PU240,[Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]PU240,[Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]PU240,[ Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]PU240,[ Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]PU240,[ Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]PU240,[ Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]PU240,[ Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]PU240,[ Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]PU240,[ Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]PU240,[ Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]PU240,[ Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]PU240,[ Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]PU240,[ Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]PU240,[ Spontaneous Fission]
REAC,[Well Thermalized Neutron Beams 10**6 Neutrons/Cm2 Sec]REAC ,[ Thermal neutrons, used for the calibration.]
REAC ,[ Thermal neutrons, used for the calibration.]
REAC ,[ Thermal neutrons, used for the calibration.]

22137.005
22137.006
22137.007
22137.008
22137.009
22137.010
22137.011
22137.012
22137.013
22202.003

22268.004
22268.005
22273.004
22273.005
22273.006
22273.007
22273.008
22273.009
22369.002

94-PU-238(0,F),PRE,AKE,FF
94-PU-238(0,F),PRE,AP,HF
94-PU-238(0,F),PRE,AP,LF
94-PU-240(0,F),PRE,AKE,FF
94-PU-240(0,F),PRE,AP,HF
94-PU-240(0,F),PRE,AP,LF
94-PU-242(0,F),PRE,AKE,FF
94-PU-242(0,F),PRE,AP,HF
94-PU-242(0,F),PRE,AP,LF(98-CF-252(0,F),PR,DE,N,,EXP)/(98-CF252(0,F),PR,DE,N,,CALC)(98-CF-252(0,F),PR,DE,N,,EXP)/(98-CF252(0,F),PR,DE,N,,CALC)
98-CF-252(0,F)MASS,IND,FY/DE,,REL(98-CF252(0,F)ELEM/MASS,IND,FY/DE)/(98-CF252(0,F)MASS,CHN,FY/DE)
98-CF-252(0,F)ELEM,IND,FY/DE,,RAW
98-CF-252(0,F)MASS,IND,FY/DE,,RAW94-PU-238(0,F),PRE,AP,HF
94-PU-238(0,F),PRE,AKE,HF
94-PU-240(0,F),PRE,AP,HF
94-PU-240(0,F),PRE,AKE,HF
94-PU-242(0,F),PRE,AP,HF
94-PU-240(0,F),PRE,AKE,HF
98-CF-252(0,F)ELEM/MASS,IND,FY,,REL

22476.002
22476.003
22476.004
22695.002
22695.003
22695.004
22695.005
22695.006
22695.007

98-CF-251(0,F)ELEM/MASS,PAR,POL,G
98-CF-251(0,F),PAR,POL,G
98-CF-252(0,F),PAR,POL,G,AV
98-CF-252(0,F),PRE,AP,LF
98-CF-252(0,F),PRE,AP,HF
98-CF-252(0,F),PRE,AKE,FF
98-CF-252(0,F),PRE,AKE,LF
98-CF-252(0,F),PRE,AKE,HF
98-CF-252(0,F),PRE,AP,LF

22202.004
22268.002
22268.003

REAC ,[ Thermal neutrons, used for the calibration.]
REAC ,[ Thermal neutrons, used for the calibration.]
REAC ,[ Thermal neutrons, used for the calibration.]
REAC ,[ Thermal neutrons, used for the calibration.]
REAC ,[ Thermal neutrons, used for the calibration.]
REAC ,[ Thermal neutrons, used for the calibration.]
REAC ,[ Thermal neutrons, used for the calibration.]
REAC ,[ Thermal neutrons, used for the calibration.]
REAC ,[ Thermal neutrons, used for the calibration.]
CF252,[]
CF252,[]
CF252,[]
CF252,[]**

CF252,[]*
CF252,[]*REAC,[]REAC,[]REAC,[]REAC,[]REAC,[]REAC,[]
CF252,[PREPARED
BY
ELECTRODEPOSITIONONA
PLATINUM DISK, INTENSITY OF THE SOURCE IS ABOUT 500
kBq]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]

22695.008
22695.009
22695.010
22695.011
22695.012
22695.013
22695.014
22695.015
22695.016
22746.002
22900.002
22900.003
22900.004
22900.005
22900.006
22900.007
22900.008
22900.009
22900.010
22900.011
22900.012
22900.013
22900.014
22900.015
22900.016
22900.017
22900.018
23048.002
23118.002
23118.004
23118.005
23118.006

98-CF-252(0,F),PRE,AP,HF
98-CF-252(0,F),PRE,AKE,FF
98-CF-252(0,F),PRE,AKE,LF
98-CF-252(0,F),PRE,AKE,HF
98-CF-252(0,F),PRE,AP,LF
98-CF-252(0,F),PRE,AP,HF
98-CF-252(0,F),PRE,AKE,FF
98-CF-252(0,F),PRE,AKE,LF
98-CF-252(0,F),PRE,AKE,HF
98-CF-252(0,F)MASS,CHN,FY
96-CM-246(0,F),TER/BIN,FY/RAT,T
96-CM-248(0,F),TER/BIN,FY/RAT,T
98-CF-250(0,F),TER/BIN,FY/RAT,T
98-CF-252(0,F),TER/BIN,FY/RAT,T
100-FM-256(0,F),TER/BIN,FY/RAT,T
94-PU-238(0,F),TER/BIN,FY/RAT,T,,DERIV
94-PU-240(0,F),TER/BIN,FY/RAT,T,,DERIV
94-PU-242(0,F),TER/BIN,FY/RAT,T,,DERIV
94-PU-244(0,F),TER/BIN,FY/RAT,T,,DERIV
96-CM-242(0,F),TER/BIN,FY/RAT,T,,DERIV
96-CM-244(0,F),TER/BIN,FY/RAT,T,,DERIV
96-CM-246(0,F),TER/BIN,FY/RAT,T,,DERIV
96-CM-248(0,F),TER/BIN,FY/RAT,T,,DERIV
98-CF-250(0,F),TER/BIN,FY/RAT,T,,DERIV
98-CF-252(0,F),TER/BIN,FY/RAT,T,,DERIV
100-FM256(0,F),TER/BIN,FY/RAT,T,,DERIV
100-FM257(0,F),TER/BIN,FY/RAT,T,,DERIV
96-CM-244(0,F)1-H-3,TER,FY
98-CF-252(0,F)MASS,PRE,FY
98-CF-252(0,F),PR,DA,N,REL
98-CF-252(0,F),PR/PAR,NU
98-CF-252(0,F)MASS,PR,NU

30046.006 98-CF-252(0,F),PR,NU

CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
PHOTO,[ White Neutron source of IRMM.]
REAC,[]REAC,[]REAC,[]REAC,[]REAC,[]REAC,[]REAC,[]REAC,[]REAC,[]REAC,[]REAC,[]REAC,[]REAC,[]REAC,[]REAC,[]REAC,[]REAC,[]REAC,[PF1B cold neutron guide at ILL -for neutron induced fission.]null,[
Resonance neutrons .]null,[
Resonance neutrons .]null,[
Resonance neutrons .]null,[
Resonance neutrons .]THCOL,[Collimated beam of thermal neutrons 1 inch, in diameter.
Maximum flux 2.5X10**3 n/cm2/sec]

30516.002 (98-CF-252(0,F)ELEM/MASS,CUM,FY)/(98CF-252(0,F)MASS,CHN,FY)
30516.004 98-CF-252(0,F)MASS,,ZP
30536.002 98-CF-252(0,F),PR,NU
30597.002 98-CF-252(0,F),PR/TER,NU/DE,A
30598.002 98-CF-252(0,F),PR/TER,NU
30600.003 94-PU-240(0,F),PR,NU

30968.002 98-CF-252(0,F)ELEM,,FY,G30976.002
30976.003
30976.004
30976.005
30976.006
30976.007
30980.003

98-CF-252(0,F)46-PD-111-M/T,IND,FY/RAT
98-CF-252(0,F)52-TE-131-M/T,IND,FY/RAT
98-CF-252(0,F)52-TE-133-M/T,IND,FY/RAT
98-CF-252(0,F)53-I-134-M/T,IND,FY/RAT
98-CF-252(0,F)55-CS-138-M/T,IND,FY/RAT
98-CF-252(0,F)48-CD-117-M/T,IND,FY/RAT
98-CF-252(0,F)48-CD-115M/T,CUM,FY/RAT

40176.002
40176.003
40176.004
40176.005
40194.002

96-CM-244(0,F)MASS,PRE,FY/DE,,RAW96-CM-244(0,F)MASS,PR,NU/DE,HF,AV
96-CM-244(0,F),PR,NU/DE,HF,AV
96-CM-244(0,F)MASS,PR,NU,,AV
94-PU-242(0,F)MASS,PRE,KE,FF

40194.004 94-PU-242(0,F),PRE,FY/DE
40194.007 94-PU-242(0,F),,AKE,FF,RAW
40194.008 94-PU-242(0,F)MASS,PRE,FY
40282.007 94-PU-242(0,F),SEC,FY
40284.007 94-PU-242(0,F),PRE,FY
40284.010 94-PU-242(0,F),,KE,FF

REAC,[ Flux= 10**12 n/cm2*sec approx.]
REAC,[.Flux= 10**12 n/cm2*sec approx.]
D-D,D-T,[]
CF252,[]
CF252,[]
P-LI7,[For 0.186 and 0.258 MeV neutrons,, Li-F thicknesses 0.51 and
0.67 mg/cm2.]
P-T,[ for 0.385 to 1.440 MeV neutrons,, T-Ti target, thickness of 0.96
mg/cm2.]
CF252,[ Source with strength of 4*10**5 fissions/min, on analuminum backing]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[ Electrodeposited source (about 5 micro gram)]

CM244,[]
CM244,[]
CM244,[]
CM244,[]
P-T,[THERMAL NEUTRONS WERE OBTAINED BY SLOWINDDOWN OF FAST NEUTRONS IN A BLOCK OF POLYETHILENE]
P-T,[THERMAL NEUTRONS WERE OBTAINED BY SLOWINDDOWN OF FAST NEUTRONS IN A BLOCK OF POLYETHILENE]
P-T,[THERMAL NEUTRONS WERE OBTAINED BY SLOWINDDOWN OF FAST NEUTRONS IN A BLOCK OF POLYETHILENE]
P-T,[THERMAL NEUTRONS WERE OBTAINED BY SLOWINDDOWN OF FAST NEUTRONS IN A BLOCK OF POLYETHILENE]
null,[PROTON-HELIUM
REACTION,
DEUTERON-HELIUM
REACTION]
D-D,[DEUTERON-DEUTERIUM REACTION]
D-D,[DEUTERON-DEUTERIUM REACTION]

40423.002 98-CF-252(0,F),TER,DA,N,REL
40450.002 98-CF-252(0,F),PR,DA,N,REL
40459.002 (98-CF-252(0,F)ELEM/MASS,CUM,FY)/(98CF-252(0,F)60-ND-147,CUM,FY)
40479.004 94-PU-240(0,F)MASS,PRE,FY/DE,,RAW40523.003 96-CM-244(0,F),PR,NU
40523.004 96-CM-246(0,F),PR,NU
40523.005 96-CM-248(0,F),PR,NU
40555.002 98-CF-252(0,F),PR,DA,N,REL
40555.003 98-CF-252(0,F),PR,DA,N,REL
40674.002 92-U-238(0,F),,NU
40674.003 92-U-236(0,F),,NU
40895.002 98-CF-252(0,F)ELEM/MASS,CUM,FY,,RAW40895.003 98-CF-252(0,F)ELEM/MASS,CUM,FY
40895.004 98-CF-252(0,F)ELEM/MASS,IND,FY
40899.002 98-CF-252(0,F),PR,DA/DE,N,REL
40899.003 98-CF-252(0,F),PR,DA/DE,N,REL
41030.002 98-CF-252(0,F),TER,AKE,T
41030.003 98-CF-252(0,F),TER,AKE,A
41030.004 98-CF-252(0,F)2-HE-3,TER,AKE,LCP
41030.005 98-CF252(0,F)ELEM/MASS,TER,FY,LCP,REL
41030.006 98-CF-252(0,F)ELEM,TER,FY,LCP,REL
41030.007 98-CF-252(0,F),TER,AKE,FF
41042.002 (92-U-236-M(0,F),PRE,FY)/(92-U-236M(0,F)2-HE-4,PRE/TER,FY)
41042.006 (92-U-238-M(0,F),PRE,FY)/(92-U-238M(0,F)2-HE-4,PRE/TER,FY)
41042.010 92-U-238-M(0,F)2-HE-4,TER,AKE,A
41061.006 92-U-238-M(0,F)2-HE-4,TER,AKE,A
41061.007 (92-U-238-M(0,F),PRE,FY)/(92-U-238M(0,F)2-HE-4,PRE/TER,FY)
41308.002 96-CM-248(0,F)2-HE-4,PRE/TER,FY,,REL
41308.003 (96-CM-248(0,F)ELEM/MASS,PRE/TER,FY)/(96-CM-248(0,F)2-HE-4,PRE/TER,FY)
41308.004 96-CM-248(0,F)ELEM/MASS,,AKE
41308.005 98-CF-252(0,F)2-HE-4,PRE/TER,FY,,REL

CF252,[]
CF252,[]
CF252,[]
PU240,[]
null,[Spontaneous Fission Of Cm-244,Cm-246,Cm-248.]
null,[Spontaneous Fission Of Cm-244,Cm-246,Cm-248.]
null,[Spontaneous Fission Of Cm-244,Cm-246,Cm-248.]
CF252,[]
CF252,[]
null,[SPONTANEUS FISSION OF U-238 AND U-236]
null,[SPONTANEUS FISSION OF U-238 AND U-236]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
CF252,[]
D-D,[]
D-D,[]
D-D,[]
D-D,[]
D-D,[]
CM248,[]
CM248,[]
CM248,[]
CM248,[]

*
*
*

*
*

*
*
*
*
*
*
*
*
*
*
*

41310.002 (96-CM-248(0,F)ELEM/MASS,PRE/TER,FY)/(96-CM-248(0,F)2-HE-4,PRE/TER,FY)
41310.003 96-CM-248(0,F)ELEM/MASS,TER,AKE,LCP
41310.004 (96-CM-248(0,F)2-HE-4,PRE/TER,FY)/(96CM-248(0,F)2-HE-4,PRE/BIN,FY)
41310.005 (98-CF-252(0,F)2-HE-4,PRE/TER,FY)/(98CF-252(0,F)2-HE-4,PRE/BIN,FY)
41421.006 94-PU-240(0,F),PR,KEM,N
41421.006 94-PU-240(0,F),PR,KEM,N
41442.004 98-CF-252(0,F)2-HE-4,TER,FY/DE,,REL
41442.005 (98-CF-252(0,F)1-H-3,TER,FY)/(98-CF252(0,F)2-HE-4,TER,FY)
41442.006 (98-CF-252(0,F)1-H-1,TER,FY)/(98-CF252(0,F)2-HE-4,TER,FY)

CM248,[]
CM248,[]
CM248,[]
CM248,[]
CF252,[ Standard Neutron Source]
PU240,[]
P-T,[]
P-T,[]
P-T,[]**

Distribution list:
blokhin@ippe.ru,
chiba@earth.sgu.ac.jp,
emmeric.dupont@oecd.org,
exfor@nea.fr,
ganesan@barc.gov.in,
gezg@ciae.ac.cn,
hongwei@ciae.ac.cn,
jhchang@kaeri.re.kr,
j.roberts@iaea.org,
kaltchenko@kinr.kiev.ua,
katakura.junichi@jaea.go.jp,
kato@nucl.sci.hokudai.ac.jp,
kiralyb@atomki.hu,
l.vrapcenjak@iaea.org,
manuel.bossant@oecd.org,
manokhin@ippe.ru,
mwherman@bnl.gov,
nklimova@kinr.kiev.ua,
nicolas.soppera@oecd.org,
n.otsuka@iaea.org,
ogritzay@kinr.kiev.ua,
otto.schwerer@aon.at,pronyaev@ippe.ru,
r.forrest@iaea.org,
samaev@obninsk.ru,
sbabykina@yandex.ru,
scyang@kaeri.re.kr,
V.Semkova@iaea.org
stakacs@atomki.hu,

stanislav.hlavac@savba.sk,
taova@expd.vniief.ru,
tarkanyi@atomki.hu,
varlamov@depni.sinp.msu.ru,
vlasov@kinr.kiev.ua,
vmclane@optonline.net,
v.zerkin@iaea.org,
yolee@kaeri.re.kr