![]() |
Definition of Data (MF) and Reaction (MT) Types used in the ENDF format
Definitions of data types (MF Numbers)
1 General information
2 Resonance parameter data
3 Reaction cross sections
4 Angular distributions for emitted particles
5 Energy distributions for emitted particles
6 Energy-angle distributions for emitted particles
7 Thermal neutron scattering law data
8 Radioactivity and fission-product yield data
9 Multiplicities for radioactive nuclide production
10 Cross sections for photon production
12 Multiplicities for photon production
13 Cross sections for photon production
14 Angular distributions for photon production
15 Energy distributions for photon production
23 Photo-atomic interaction cross sections
27 Atomic form factors or scattering functions for photo-atomic
interactions
30 Data Covariances obtained from parameter covariances and sensitivities
31 Data covariances for nubar
32 Data covariances for resonance parameters
33 Data covariances for reaction cross sections
34 Data covariances for angular distributions
35 Data covariances for energy distributions
39 Data covariances for radionuclide production yields
40 Data covariances for radionuclide production cross sections
Definition of reaction types (MT Numbers)
*mt* 1-100 reaction types in which secondary particles of the
same type as the incident particles are emitted
*mt* 101-150 reaction types in which no secondary particles of
the same type as the incident particles are emitted
*mt* 151-200 resonance region information
*mt* 201-450 quantities derived from the basic data
*mt* 451-699 miscellaneous quantities
*mt* 700-799 excitation cross sections for the reactions that emit
charged particles
1 (n,total) Neutron total cross section
2 (z,zO) elastic
3 (z, non-elastic) Nonelastic neutron cross section. Sum of MT=4, 5, 16-18,
22-26, 28-37, 41-42, 102-116
4 (z,n) Cross section for the production of one neutron in the exit channel. Sum
of the MT=50-91.
5 (z,anything) The cross section for the sum of all reactions not given
explicitly in another MT number.
6 (n,2n),L1 Not allowed in version 6 except for compatibility with JENDL-3.2
7 (n,2n),L2 Not allowed in version 6 except for compatibility with JENDL-3.2
8 (n,2n),L3 Not allowed in version 6 except for compatibility with JENDL-3.2
9 (n,2n),L4 Not allowed in version 6 except for compatibility with JENDL-3.2
10 (z,continuum) Total continuum cross section. This sum cross section includes
all continuum reactions and excludes all
16 (z,2n) Cross section for producing two neutrons and a residual.
17 (z,3n) Cross section for producing three neutrons and a residual.
18 (z,F) Total fission cross section for all incident particles. For neutrons
incident, MT=18 is the sum of MT19. 20. 21. and 38.
19 (n,f) First-chance fission cross section.
20 (n,nf) Second-chance fission cross section.
21 (n,2nf) Third-chance fission cross section.
22 (z,na) The cross section for the production of a neutron and alpha particle
plus a residual.
23 (z,n3a) The cross section for the production of a neutron and three alpha
particles plus a residual.
24 (z,2na) The cross section for the production of two neutrons and one alpha
particle plus a residual.
25 (z,3na) The cross section for the production of three neutrons and one alpha
particle plus a residual.
26 Not allowed in version 6.Was (n,2n) isomeric state cross section in version
5.
27 (n,abs) Absorption cross section. Sum of MT=18 and MT=102 through MT=1 1 6.
28 (z,np) Cross section for the production of a neutron and a proton plus a
residual.
29 (z,n2a) Cross section for the production of a neutron and two alpha particles
plus a residual.
30 (z,2n2a) Cross section for the production of two neutrons and two alpha
particles plus a residual.
31 Not allowed in version 6.
32 (z,nd) Cross section for the production of one neutron and one deuteron plus
a residual.
33 (z,nt) Cross section for the production of one neutron and one triton plus a
residual
34 (z,n3He) Cross section for the production of one neutron and one He particle
plus a residual.
35 (z,nd2a) Cross section for the production of a neutron and deuteron and two
alpha particles plus a residual.
36 (z,nt2a) Cross section for the production of a neutron and triton and two
alpha particles plus a residual.
37 (z,4n) Cross section for the production of four neutrons plus a residual.
38 (n,3nf) Fourth-chance fission cross section.
39 Not allowed in version 6. Use only as an LR
40 Not allowed in version 6. Use only as an LR
41 (z,2np) Cross section for the production of two neutrons and a proton plus a
residual.
42 (z,3np) Cross section for the production of three neutrons and a proton plus
a residual.
46 Not allowed in version 6. Cross section for describing the second neutron
from 9Be(n,2n) reactions for excited states in version 5.
47 Not allowed in version 6. Cross section for describing the second neutron
from 9Be(n,2n) reactions for excited states in version 5.
48 Not allowed in version 6. Cross section for describing the second neutron
from 9Be(n,2n) reactions for excited states in version 5.
49 Not allowed in version 6. Cross section for describing the second neutron
from 9Be(n,2n) reactions for excited states in version 5.
50 (y,nO) The cross section for the production of a neutron, leaving the
residual nucleus in the ground state.
51 (z,nl) Cross section to the first excited state of the residual nucleus.
52 (z,n2) Cross section to the 2nd excited state of the residual nucleus.
53 (n,n') 3rd inelastic level
54 (n,n') 4th inelastic level
55 (n,n') 5th inelastic level
56 (n,n') 6th inelastic level
57 (n,n') 7th inelastic level
58 (n,n') 8th inelastic level
59 (n,n') 9th inelastic level
60 (n,n') 10th inelastic level
61 (n,n') 11th inelastic level
62 (n,n') 12th inelastic level
63 (n,n') 13th inelastic level
64 (n,n') 14th inelastic level
65 (n,n') 15th inelastic level
66 (n,n') 16th inelastic level
67 (n,n') 17th inelastic level
68 (n,n') 18th inelastic level
69 (n,n') 19th inelastic level
70 (n,n') 20th inelastic level
71 (n,n') 21st inelastic level
72 (n,n') 22nd inelastic level
73 (n,n') 23rd inelastic level
74 (n,n') 24th inelastic level
75 (n,n') 25th inelastic level
76 (n,n') 26th inelastic level
77 (n,n') 27th inelastic level
78 (n,n') 28th inelastic level
79 (n,n') 29th inelastic level
80 (n,n') 30th inelastic level
81 (n,n') 31st inelastic level
82 (n,n') 32nd inelastic level
83 (n,n') 33rd inelastic level
84 (n,n') 34th inelastic level
85 (n,n') 35th inelastic level
86 (n,n') 36th inelastic level
87 (n,n') 37th inelastic level
88 (n,n') 38th inelastic level
89 (n,n') 39th inelastic level
90 (z,n40) Cross section to the 40th excited state of the residual nucleus.
91 (z,nc) Cross section for the production of a single neutron in the continuum
not included in the above discrete representation.
101 (n, disappearance) Neutron disappearance cross section. Rarely used. MT=101
is equal to the sum of MT=102-1 16.
102 (z,y) Radiative capture cross section.
103 (z,p) Cross section for the production of a proton and a residual. If
MT=600-649 are present, MT103 is their sum.
104 (z,d) Cross section for the production of a deuteron and a residual. If
MT=650-699 are present, MT104 is their sum.
105 (z,t) Cross section for the production of a triton plus a residual. If
MT=700-749 are present, MT105 is their sum.
106 (z,3He) Cross section for the production of an He particle plus a residual.
If MT=750-799 are present, MT106 is their sum.
107 (z,a) Cross section for the production of an alpha particle plus a residual.
If MT=800-849 are present, MT107 is their sum.
108 (z,2a) Cross section for the production of two alpha particles plus a
residual.
109 (z,30c) Cross section for the producton of three alpha particles plus a
residual.
111 (z,2p) Cross section for the production of two protons plus a residual.
112 (z,pa) Cross section for the production of a proton and an alpha particle
plus a residual.
113 (z,t2a) Cross section for the production of a triton and two alpha particles
plus a residual.
114 (Z,d2a) Cross section for the production of a deuteron and two alpha
particles, plus a residual.
115 (z,pd) Cross section for the production of a proton and deuteron plus a
residual.
116 (z,pt) Cross section for the production of a proton and triton plus a
residual.
120 Not allowed in version 6. Target destruction cross section in version 5
(non-elastic minus total (n,n'y).
151 (n,RES) Resonance parameters that can be used to calculate cross sections
at different temperatures in the resolved and unresolved energy ranges.
201 (z,Xn) Total neutron production cross section. Redundant. Derived files
only.
202 (z,Xy) Total gamma production cross section. Redundant. Derived files only.
203 (z,Xp) Total proton production cross section. Redundant. Derived files
only.
204 (z,Xd) Total deuteron production cross section. Redundant. Derived files
only.
205 (z,Xt) Total triton production cross section. Redundant. Derived files only.
206 (z, X3He) Total 3He production cross section. Redundant. Derived files
only.
207 (z,Xa) Total alpha production cross section. Redundant. Derived files
only.
208 (z,Xpi+) Total pi+ production cross section. Redundant. Derived files only.
209 (z,Xpi0) Total pi0 production cross section. Redundant. Derived files only.
210 (z,Xpi-) Total pi- production cross section. Redundant. Derived files only.
211 (z,Xmu+) Total mu+ production cross section. Redundant. Derived files only.
212 (z,Xmu-) Total mu- production cross section. Redundant. Derived files only.
213 (Z,XK+) Total K+ production cross section. Redundant. Derived files only.
214 (z,XK0(long)) Total K0(long) production cross section. Redundant. Derived
files only.
215 (z,XK0(short)) Total K0(Short) production cross section. Redundant. Derived
files only.
216 (Z,XK-) Total K- production cross section. Redundant. Derived files only.
217 (z,Xanti-proton) Total anti-proton production cross section. Redundant.
Derived files only.
218 (z,Xanti-neutron) Total anti-neutron production cross section. Redundant.
Derived files only.
251 (n,....) mu bar, the average cosine of the scattering angle (laboratory
system) for elastic scattering of neutrons.
252 (n,....) Epsilon, the average logarithmic energy decrement for elastic
scattering of neutrons.
253 (n,....) y, the average of the square of the Iogarithmic energy decrement
for elastic scattering, divided by twice the average logarithmic decrement for
elastic
301 (z,....) Energy release parameters, E sigma, for total and partial cross
sections. Subtract 300 from this number to obtain the specific reaction type
451 (z,....) Heading or title information (given only in File 1).
452 (Z,....) nubar T, average total (prompt plus delayed) number of neutrons
released per fission event.
454 (z,....) Independent fission product yield data.
455 (z,....) nubar D, average number of delayed neutrons released per fission
event.
456 (z,....) nubar p, average number of prompt neutrons released per fission
event.
457 (z,....) Radioactive decay data.
458 (n,....) Energy release in fission for incident neutrons.
459 (z,....) Cumulative fission product yield data.
465 Not allowed in version 6. Delayed and prompt neutrons from spontaneous
fission in version 5.
466 Not allowed in version 6. Delayed and prompt neutrons from spontaneous
fission in version 5.
500 Total charged particle stopping power.
501 Total photon interaction cross section.
502 Photon coherent scattering.
504 Photon incoherent scattering.
505 Imaginary scattering factor.
506 Real scattering factor.
515 Pair production, electron field.
516 Pair production. Sum of MT=515, 517. Redundant.
517 Pair production, nuclear field.
518 Not allowed in version 6.
522 Photoelectric absorption. Was MT=602 in version 5.
532 Not allowed in version 6. (r,n) reaction in version 5.
533 Not allowed in version 6. Total photonuclear cross section in version 5
534 K (1s1/2) Subshell photoelectric cross section.
535 L1 (2s1/2) Subshell photoelectric cross section.
536 L2 (2p1/2) Subshell photoelectric cross section.
537 L3 (2p3/2) Subshell photoelectric cross section.
538 M1 (3s1/2) Subshell photoelectric cross section.
539 M2 (3p1/2) Subshell photoelectric cross section.
540 M3 (3p3/2) Subshell photoelectric cross section.
541 M4 (3d3/2) Subshell photoelectric cross section.
542 M5 (3d5/2) Subshell photoelectric cross section.
543 N1 (4s1/2) Subshell photoelectric cross section.
544 N2 (4p1/2) Subshell photoelectric cross section.
545 N3 (4p3/2) Subshell photoelectric cross section.
546 N4 (4d3/2) Subshell photoelectric cross section.
547 N5 (4d5/2) Subshell photoelectric cross section.
548 N6 (4f5/2) Subshell photoelectric cross section.
549 N7 (4f7/2) Subshell photoelectric cross section.
550 O1 (5s1/2) Subshell photoelectric cross section.
551 O2 (5p1/2) Subshell photoelectric cross section.
552 O3 (5p3/2) Subshell photoelectric cross section.
553 O4 (5d3/2) Subshell photoelectric cross section.
554 O5 (5d5/2) Subshell photoelectric cross section.
555 O6 (5f5/2) Subshell photoelectric cross section.
556 O7 (5f7/2) Subshell photoelectric cross section.
557 O8 (5g7/2) Subshell photoelectric cross section.
558 O9 (5g9/2) Subshell photoelectric cross section.
559 P1 (6s1/2) Subshell photoelectric cross section.
560 P2 (6p1/2) Subshell photoelectric cross section.
561 P3 (6p3/2) Subshell photoelectric cross section.
562 P4 (6d3/2) Subshell photoelectric cross section.
563 P5 (6d5/2) Subshell photoelectric cross section.
564 P6 (6f5/2) Subshell photoelectric cross section.
565 P7 (6f7/2) Subshell photoelectric cross section.
566 P8 (6g7/2) Subshell photoelectric cross section.
567 P9 (6g9/2) Subshell photoelectric cross section.
568 P10 (6h9/2) Subshell photoelectric cross section.
569 P11 (6h11/2) Subshell photoelectric cross section.
570 Q1 (7s1/2) Subshell photoelectric cross section.
571 Q2 (7p1/2) Subshell photoelectric cross section.
572 Q3 (7p3/2) Subshell photoelectric cross section.
600 (z,P0) Cross section for production of a proton leaving the residual nucleus
in the ground state.
601 (Z,P1) Cross section for the 1st excited state of the residual nucleus.
602 (Z,P2) Cross section for the 2nd state of the residual nucleus. Was
photoelectric absorption in version 5. See MT=522.
603 (Z,P3) Cross section for the 3rd state of the residual nucleus.
604 (Z,P4) Cross section for the 4th excited state of the residual nucleus.
605 (z,p5)
606 (z,p6)
607 (z,p7)
608 (z,p8)
609 (z,p9)
610 (z,p10)
611 (z,p11)
612 (z,p12)
613 (z,p13)
614 (z,p14)
615 (z,p15)
616 (z,p16)
617 (z,p17)
618 (z,p18)
619 (z,p19)
620 (z,p20)
621 (z,p21)
622 (z,p22)
623 (z,p23)
624 (z,p24)
625 (z,p25)
626 (z,p26)
627 (z,p27)
628 (z,p28)
629 (z,p29)
630 (z,p30)
631 (z,p31)
632 (z,p32)
633 (z,p33)
634 (z,p34)
635 (z,p35)
636 (z,p36)
637 (z,p37)
638 (z,p38)
639 (z,p39)
640 (z,p40)
641 (z,p41)
642 (z,p42)
643 (z,p43)
644 (z,p44)
645 (z,p45)
646 (z,p46)
647 (z,p47)
648 (z,p48)
649 (Z,Pc) Cross section for the production of a single proton in the continuum.
650 (z,d0) Cross section for production of a deuteron leaving the residual
nucleus in the ground state.
651 (z,d1) Cross section for the 1st excited state of the residual nucleus.
652 (z,d2) Cross section for the 2nd excited state of the residual nucleus.
653 (z,d3)
654 (z,d4)
655 (z,d5)
656 (z,d6)
657 (z,d7)
658 (z,d8)
659 (z,d9)
660 (z,d10)
661 (z,d11)
662 (z,d12)
663 (z,d13)
664 (z,d14)
665 (z,d15)
666 (z,d16)
667 (z,d17)
668 (z,d18)
669 (z,d19)
670 (z,d20)
671 (z,d21)
672 (z,d22)
673 (z,d23)
674 (z,d24)
675 (z,d25)
676 (z,d26)
677 (z,d27)
678 (z,d28)
679 (z,d29)
680 (z,d30)
681 (z,d31)
682 (z,d32)
683 (z,d33)
684 (z,d34)
685 (z,d35)
686 (z,d36)
687 (z,d37)
688 (z,d38)
689 (z,d39)
690 (z,d40)
691 (z,d41)
692 (z,d42)
693 (z,d43)
694 (z,d44)
695 (z,d45)
696 (z,d46)
697 (z,d47)
698 (z,d48)
699 (z,dc) Cross section for the production of a single deuteron in the
continuum.
700 (z,t0) Cross section for production of a triton leaving the residual nucleus
in the ground state.
701 (z,t1) Cross section for the 1st excited state of the residual nucleus.
702 (z,t2) Cross section for the 2nd excited state of the residual nucleus.
703 (z,t3)
704 (z,t4)
705 (z,t5)
706 (z,t6)
707 (z,t7)
708 (z,t8)
709 (z,t9)
710 (z,t10)
711 (z,t11)
712 (z,t12)
713 (z,t13)
714 (z,t14)
715 (z,t15)
716 (z,t16)
717 (z,t17)
718 (z,t18)
719 (z,t19)
720 (z,t20)
721 (z,t21)
722 (z,t22)
723 (z,t23)
724 (z,t24)
725 (z,t25)
726 (z,t26)
727 (z,t27)
728 (z,t28)
729 (z,t29)
730 (z,t30)
731 (z,t31)
732 (z,t32)
733 (z,t33)
734 (z,t34)
735 (z,t35)
736 (z,t36)
737 (z,t37)
738 (z,t38)
739 (z,t39)
740 (z,t40)
741 (z,t41)
742 (z,t42)
743 (z,t43)
744 (z,t44)
745 (z,t45)
746 (z,t46)
747 (z,t47)
748 (z,t48)
749 (z,tc) Cross section for the production of a single triton in the continuum.
750 (z,3He0) Cross section for production of a 3He particle leaving the residual
nucleus in the ground state.
751 (z,3He1) Cross section for the 1st excited state of the residual nucleus.
752 (z,3-He2)
753 (z,3-He3)
754 (z,3-He4)
755 (z,3-He5)
756 (z,3-He6)
757 (z,3-He7)
758 (z,3-He8)
759 (z,3-He9)
760 (z,3-He10)
761 (z,3-He11)
762 (z,3-He12)
763 (z,3-He13)
764 (z,3-He14)
765 (z,3-He15)
766 (z,3-He16)
767 (z,3-He17)
768 (z,3-He18)
769 (z,3-He19)
770 (z,3-He20)
771 (z,3-He21)
772 (z,3-He22)
773 (z,3-He23)
774 (z,3-He24)
775 (z,3-He25)
776 (z,3-He26)
777 (z,3-He27)
778 (z,3-He28)
779 (z,3-He29)
780 (z,3-He30)
781 (z,3-He31)
782 (z,3-He32)
783 (z,3-He33)
784 (z,3-He34)
785 (z,3-He35)
786 (z,3-He36)
787 (z,3-He37)
788 (z,3-He38)
789 (z,3-He39)
790 (z,3-He40)
791 (z,3-He41)
792 (z,3-He42)
793 (z,3-He43)
794 (z,3-He44)
795 (z,3-He45)
796 (z,3-He46)
797 (z,3-He47)
798 (z,3-He48)
799 (z,3Hec) Cross section for the production of a single 3He particle in the
continuum.
800 (z,a0) Cross section forproduction of an alpha particle leaving the residual
nucleus in the ground state.
801 (z,a1) Cross section for the 1st excited state of the residual nucleus.
802 (z,(a)2)
803 (z,(a)3)
804 (z,(a)4)
805 (z,(a)5)
806 (z,(a)6)
807 (z,(a)7)
808 (z,(a)8)
809 (z,(a)9)
810 (z,(a)10)
811 (z,(a)11)
812 (z,(a)12)
813 (z,(a)13)
814 (z,(a)14)
815 (z,(a)15)
816 (z,(a)16)
817 (z,(a)17)
818 (z,(a)18)
819 (z,(a)19)
820 (z,(a)20)
821 (z,(a)21)
822 (z,(a)22)
823 (z,(a)23)
824 (z,(a)24)
825 (z,(a)25)
826 (z,(a)26)
827 (z,(a)27)
828 (z,(a)28)
829 (z,(a)29)
830 (z,(a)30)
831 (z,(a)31)
832 (z,(a)32)
833 (z,(a)33)
834 (z,(a)34)
835 (z,(a)35)
836 (z,(a)36)
837 (z,(a)37)
838 (z,(a)38)
839 (z,(a)39)
840 (z,(a)40)
841 (z,(a)41)
842 (z,(a)42)
843 (z,(a)43)
844 (z,(a)44)
845 (z,(a)45)
846 (z,(a)46)
847 (z,(a)47)
848 (z,(a)48)
849 (z,ac) Cross section for the production of a single alpha particle in the
continuum.
851 For describing lumped-reaction covariances.
Navigation| NEA Home Page >> Activities >> Data Bank >> Nuclear Data Services >> By Data Type
|