CCC-0730 MCNP/MCNPX.

1. NAME OR DESIGNATION:  MCNP/MCNPX. This package contains MCNP5 1.4.0, MCNPX 2.5.0, MCNPDATA, and VISED 19L.

3. DESCRIPTION OF PROGRAM OR FUNCTION

MCNP5 1.40
==========
MCNP is a general-purpose, continuous-energy, generalized geometry, time-dependent, coupled neutron-photon-electron Monte Carlo transport code system.
The major new features of MCNP5 compared to MCNP4 include:
- Doppler Energy Broadening for Photon Transport
- Extended Random Number Package
- Neutral Particle Radiography
- New Source Options
- Variance Reduction: Time Importances
- Variance Reduction: Pulse-height Tally Enhancements
- Parallel Processing Support
- Mesh Tallies improvements
- Image Tallies, radiographs
- Sources: translate/rotate/repeat, Gaussian, particle type
- Time & energy splitting/rouletting
- Stochastic geometry for modeling HTGR fuel kernels
- Electron Transport improvements
- Positron sources
  
MCNPX 2.5.0
===========
MCNPX is a general purpose Monte Carlo radiation transport code that tracks all element particles up to GeV range energies. Version MCNPX 2.5.0 combines MCNP4C, a general purpose, continuous energy, generalised geometry, time dependent, coupled neutron-photon-electron Monte Carlo transport codesystem for energies up to 20 MeV and MCNPX 2.4 the previous version of MCNPX, LAHET 2.8 a code system for high energy particle transport calculations.
  
New features compared to previous versions are:
Physics:
Seamless transport of 34-particle types at nearly all energies by mixing and matching of nuclear data table and model physics; CEM2k calculating nuclear reactions in the framework of improved cascade-exciton model; INCL4/ABLA hadron interaction models; Extension of neutron model physics below 20 MeV; Fission multiplicity; Light-ion recoil; Inline generation of double differential cross sections and residuals; Photon Doppler broadening (from MCNP5); Weight-window generator (WWG) and exponential transform for model physics; Improved thermal scattering S(alpha,beta) physics .
  
Sources: Spontaneous fission; Multiple-source particle types; Repeated structures source-path improvement; Positron sources; Sources on cylindrical surfaces; Source particles that may be specified by character descriptors; translated sources with dependence.
    
Tallies: Pulse-height tallies with variance reduction; Default dose functions; Pulse-height light tally with anticoincidence; Coincidence capture tally; Residual nuclei tally; Lattice tally speedup by orders of magnitude; Proton reaction multipliers; Photonuclear reaction multipliers; Expanded radiography tally specification.
  
Graphics: Mesh tallies (tally grid superimposed over geometry) plotted within MCNPX; Two-dimensional (2D) color tally contour plots of lattice and radiography tallies; Enhanced color geometry plots; Geometry plot of WWG superimposed mesh; i,j,k lattice indexing in geometry plots; Proton and photonuclear cross-section plots; Pause command for tally and cross-section plots.
    
Current applications for the code include among others:
Design of accelerator spallation targets, particularly for neutron scattering facilities; Investigations for accelerator isotope production and destruction programs, including the transmutation of nuclear waste; Research into accelerator-driven energy sources; Medical physics, especially proton and neutron therapy; Investigations of cosmic-ray radiation backgrounds and shielding for high altitude aircraft and spacecraft; Accelerator-based imaging technology such as neutron and proton radiography; Design of shielding in accelerator facilities; Activation of accelerator components and surrounding groundwater and air; Investigation of fully coupled neutron and charged-particle transport for lower energy applications; High-energy dosimetry and neutron detection; Design of neutrino experiments; Comparison of physics-based and table-based data; Charged-particle tracking in plasmas; Charged-particle propulsion concepts for spaceflight; Single-event upset in semiconductors, from cosmic rays in spacecraft or from the neutron component on the earth's surface; Detection technology using charged particles (i.e., abandoned landmines); Nuclear safeguards; Nuclear criticality safety; Radiation protection and shielding; Oil well logging.
  
MCNPDATA
========
For more details, see 'Current Releases' in Data_Doc directory.
  
CONTINUOUS-ENERGY NEUTRON DATA LIBRARIES:
-  t16_2003  - pre ENDF/B-VII evaluations from Los Alamos Group T-16 for 15 isotopes.
H-3, U-232, U-233, U-234, U-235, U-236, U-237, U-238, U-239, U-240, U-241, Np-237, Pu-239, Am-241, Am-243
Temperatures: 77, 293.6, 3000K
  
-  actia and actib - ENDF/B-VI Release 8 (42 nuclides)
H-1, He-4, Be-9, N-14, O-16, F-19, Na-23, Mg-nat, Al-27, Al-27 w/delayed, Si-28, Si-29, Si-30, S-nat, S-32, Cl-35, Cl-37, K-nat, Ca-nat, Sc-45, Ti-nat, V-nat, Cr-50, Cr-52, Cr-53, Cr-54, Mn-55, Fe-54, Fe-56, Fe-57, Fe-58, Ni-58, Ni-60, Ni-61, Ni-62, Ni-64, Cu-63, Cu-65, W-182, W-183, W-184, W-186
Temperatures: 77, 293.6, 3000K
  
-  endf66(a-e) - ENDF/B-VI Release 6  (173 nuclides)
endf66a, endf66b, endf66c 173 nuclides
H-1,H-2,H-3,He-3,He-4,Li-6,Li-7,Be-9,B-10,B-11,C-nat,N-14,N-15,O-16,O-17,F-19,Na-23,Mg-nat,Al-27,Si-28,Si-29,Si-30,P-31,S-nat,S-32,Cl-nat,K-nat,Ca-nat,Sc-45,Ti-nat,V-nat,Cr-50,Cr-52,Cr-53,Cr-54,Mn-55,Fe-54,Fe-56,Fe-57,Fe-58,Co-59,Ni-58,Ni-60,Ni-61,Ni-62,Ni-64,Cu-63,Cu-65,Ga-nat,Kr-78,Kr-80,Kr-82,Kr-83,Kr-84,Kr-86,Rb-85, Rb-87,Y-89,Zr-at,Zr-90,Zr-91,Zr-92,Zr-94,Zr-96,Nb-93,Mo-nat,Tc-099,Rh-103,Pd-102,Pd-104,Pd-105,Pd-106,Pd-108,Pd-110,Ag-107,Ag-109,Cd-106,Cd-108,Cd-110,Cd-111,Cd-112,Cd-113,Cd-114,Cd-116,In-nat,I-127,Xe-124,Xe-126,Xe-128,Xe-129,Xe-130,Xe-131,Xe-132,Xe-134,Xe-136,Cs-133,Ba-138,Sm-147,Sm-149,Eu-151,Eu-152,Eu-153,Eu-154,Eu-155,Gd-152,Gd-154,Gd-155,Gd-156,Gd-157,Gd-158,Gd-160,Ho-165,Lu-175,Lu-176,Hf-174,Hf-176,Hf-177,Hf-178,Hf-179,Hf-180,Ta-181,Ta-182,W-182,W-183,W-184, W-186, Re-185, Re-187, Ir-191, Ir-193, Au-197, Pb-206, Pb-207, Pb-208, Bi-209, Th-230, Th-232, Pa-231, Pa-233, U-232, U-233, U-234, U-235, U-236, U-237, U-238, Np-237, Np-239, Pu-236, Pu-237, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Pu-243, Pu-244, Am-241, Am-242, Am-243, Cm-241, Cm-242, Cm-243, Cm-244, Cm-245, Cm-246, Cm-247, Cm-248, Bk-249, Cf-249, Cf-250, Cf-251, Cf-252
Temperature: 293.6K
  
endf66d, 35 nuclides
Mg-nat, Al-27, Si-28, Si-29, Si-30, S-nat, S-32, Cl-nat, Ca-nat, Ti-nat, Cr-50, Cr-52, Cr-53, Cr-54,  Mn-55, Fe-54, Fe-56, Fe-57, Fe-58, Ni-58, Ni-60, Ni-61, Ni-62, Ni-64, Cu-63, Cu-65, Ta-181, Ta-182, W-182, W-183, W-184, W-186, U-235, U-238, Pu-239
Temperature: 77K
  
endf66e, 67 nuclides
Zr-91, Tc-99, Rh-103, Cd-106, Cd-108, Cd-110, Cd-112, Cd-114, Cd-116, Sm-147, Sm-149, Eu-151, Eu-152, Eu-153, Eu-154, Gd-152, Gd-154, Gd-155, Gd-157, Lu-175, Lu-176, Hf-174, Hf-176, Hf-177, Hf-178, Hf-179, Hf-180, Ta-182, W-182, W-183, W-184, W-186, Re-185, Re-187, Ir-191, Ir-193, Th-232, Pa-231, Pa-233, U-232, U-233, U-234, U-235, U-236, U-237, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Pu-243, Pu-244, Am-241, Am-242, Am-243, Cm-242, Cm-243, Cm-244, Cm-245, Cm-247, Cm-248, Bk-249, Cf-249, Cf-250, Cf-251, Cf-252
Temperature: 3000K
  
-  la150n: 150-MeV Neutron Library for MCNP (42 nuclides)
H-1, H-2, Be-9, C-nat, N-14, O-16, Al-27, Si-28, Si-29, Si-30, P-31, Ca-nat, Cr-50, Cr-52, Cr-53, Cr-54, Fe-54, Fe-56, Fe-57, Ni-58, Ni-60, Ni-61, Ni-62, Ni-64, Cu-63, Cu-65, Nb-93, W-182, W-183, W-184, W-186, Hg-196, Hg-198, Hg-199, Hg-200, Hg-201, Hg-202, Hg-204, Pb-206, Pb-207, Pb-208, Bi-209
Temperature: 293.6K
  
-  uresa - ENDF/B-VI Release 4 with probability tables (27 nuclides)
Sm-149, Sm-150, Sm-152, Eu-151, Eu-152, Eu-153, Eu-154, Ta-182, W-182, W-183, W-184, W-186, Ir-191, Ir-193, Th-232, U-232, U-233, U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Cm-244
Temperature: 300K
  
-  endf6dn - ENDF/B-VI Release 2 with delayed-neutron data (20 nuclides)
Th-232, Pa-231, U-232, U-233, U-234, U-235, U-236, U-238, Np-237, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am-241, Am-243, Cm-242, Cm-245, Cf-249, Cf-251
Temperature: 293.6K
  
-  endf62mt - multitemperature ENDF/B-VI Release 2, (3 nuclides)
U-235, U-238, Pu-239
Temperatures: 77, 400, 500, 600, 800, 900, 1200K
  
-  endf60 - ENDF/B-VI Release 2 (122 nuclides)
H-1, H-2, H-3, He-3, He-4, Li-6, Li-7, Be-9, B-10, B-11, C-nat, N-14, N-15, O-16, O-17, F-19, Na-23, Mg-nat, Al-27, Si-nat, P-31, S-nat, S-32, Cl-nat, K-nat, Ca-nat, Sc-45, Ti-nat, V-nat, Cr-50, Cr-52, Cr-53, Cr-54, Mn-55, Fe-54, Fe-56, Fe-57, Fe-58, Co-59, Ni-58, Ni-60, Ni-61, Ni-62, Ni-64, Cu-63, Cu-65, Ga-nat, Y-89, Zr-nat, Nb-93, Mo-nat, Tc-99, Ag-107, Ag-109, In-nat, I-127, I-129, Cs-133, Cs-134, Cs-135, Cs-136, Cs-137, Ba-138, Eu-151, Eu-153, Gd-152, Gd-154, Gd-155, Gd-156, Gd-157, Gd-158, Gd-160, Ho-165, Hf-nat, Ta-181, Ta-182, W-182, W-183, W-184, W-186, Re-185, Re-187, Au-197, Pb-206, Pb-207, Pb-208, Bi-209, Th-230, Th-232, Pa-231, U-232, U-233, U-234, U-235, U-236, U-238, Np-237, Np-239, Pu-236, Pu-237, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Pu-243, Pu-244, Am-241, Am-243, Cm-241, Cm-242, Cm-243, Cm-244, Cm-245, Cm-246, Cm-247, Cm-248, Bk-249, Cf-249, Cf-250, Cf-251, Cf-252
Temperature: 300K
  
-  newxs - LANL based evaluations (6 nuclides)
B-11, Eu-151, Eu-153, Ho-165, Hf-nat, Au-197
Temperature: 293.6K
  
-  rmccs - ENDF/B-V and LANL based evaluations (63 nuclides)
H-1, H-2, H-3, He-3, He-4, Li-6, Li-7, Be-9, B-10, C-nat, C-12, N-14, O-16, F-19, Na-23, Mg-nat, Al-27, Si-nat, P-31, S-32, Cl-nat, K-nat, Ca-nat, Ti-nat, V-nat, Cr-nat, Mn-55, Fe-nat, Co-59, Ni-nat, Cu-nat, Ga-nat, Nb-93, Mo-nat, Rh-117, Pd-119, Cd-nat, Sn-120, Ba-138, Eu-151, Eu-153, Ta-181, W-nat, Pb-nat, Bi-209, Th-232, Pa-233, U-233, U-234, U-235, U-236, U-237, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am-241, Am-242, Am-243, Cm-242, Cm-244
Temperature: 293.6K
  
-  rmccsa - ENDF/B-V and LANL based evaluations (27 nuclides)
B-11, N-15, Ar-nat, As-75, Kr-78, Kr-80, Kr-82, Kr-83, Kr-84, Kr-86, Rh-103, Ag-nat, Ag-107, Ag-109, Eu-nat, Gd-nat, Ho-165, W-182, W-183, W-184, W-186, Re-185, Re-187, Pt-nat, Au-197, U-239, Np-237
Temperature: 293.6K
  
-  endf5p - ENDFB-V  (22 nuclides)
H-2, Li-7, B-11, F-19, Na-23, Si-nat, Cl-nat, Fe-nat, Nb-93, W-182, W-183, W-184, W-186, Au-197, U-234, U-236, U-237, Np-237, Pu-238, Pu-239, Pu-241, Pu-242
Temperature: 293.6K
  
-  endf5u - ENDF/B-V (31 nuclides)
C-nat, P-31, S-32, K-nat, Ca-nat, Ti-nat, V-nat, Mn-55, Co-59, Y-89, Mo-nat, Cd-nat, Sm-149, Eu-152, Eu-154, Gd-152, Gd-154, Gd-155, Gd-156, Gd-157, Gd-158, Gd-160, Ta-181, Bi-209, Th-232, Pa-233, Am-241, Am-242, Am-243, Cm-242, Cm-244
Temperature: 293.6K
  
-  misc5xs - Contains a number of previously released small libraries (24 nuclides)
Ar-nat, Br-79, Br-81, Kr-82, Kr-83, Kr-84, Kr-86, Rb-85, Rb-87, Y-89, Zr-nat, I-127, Cs-133, Gd-152, Gd-154, Gd-155, Gd-156, Gd-157, Gd-158, Gd-160, Tm-169, Re-185, Re-187, Ir-nat
Temperatures: 300, 600K
  
-  kidman - fission product evaluations (25 nuclides)
Zr-093, Mo-095, Tc-099, Ru-101, Ru-103, Rh-105, Pd-105, Pd-108, I-135, Xe-131, Cs-133, Cs-135, Pr-141, Nd-143, Nd-145, Nd-147, Nd-148, Pm-147, Pm-148, Pm-149, Sm-147, Sm-150, Sm-151, Sm-152, Eu-155
Temperature: 293.6K
  
-  100xs - LANL based evaluations for a subset of isotopes up to 100 MeV (9 nuclides)
Be-9, C-12, O-16, Al-27, Si-nat, Ca-40, Fe-nat, W-nat, U-238
Temperature: 300K
  
-  endl92 and endl92fp - 1992 ENDL library from Lawrence Livermore National Lab (LLNL) (102 nuclides)
H-1, H-3, He-3, He-4, Li-6, Li-7, Be-7, B-10, B-11, C-12, C-13, N-14, N-15, O-16, F-19, Ne-20, Na-23, Mg-nat, Al-27, Si-nat, P-31, S-32, Cl-nat, Ar-nat, K-nat, Ca-nat, Ti-nat, V-51, Cr-nat, Mn-55, Fe-nat, Co-59, Ni-nat, Ni-58, Zn-nat, Ga-nat, As-74, As-75, Y-88, Y-89, Zr-nat, Nb-93, Mo-nat, Ag-107, Ag-109, Cd-nat, In-nat, In-120, In-125, Sn-nat, Sb-nat, I-127, Xe-nat, Xe-134, Eu-nat, Ho-165, Hf-nat, Ta-181, Re-185, Re-187, Pt-nat, Hg-nat, Pb-nat, Bi-209, Th-231, Th-232, Th-233, Pa-233, U-233, U-234, U-235, U-236, U-237, U-238, U-239, U-240, Np-235, Np-236, Np-237, Np-238, Pu-237, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Pu-243, Am-241, Am-242, Am-243, Cm-242, Cm-243, Cm-244, Cm-245, Cm-246, Cm-247, Cm-248, Bk-249, Cf-249, Cf-250, Cf-251, Cf-252
Temperature: 300K
  
-  endf5mt - Multitemperature data previously released as eprixs and u600k (6 nuclides)
H-1, B-10, O-16, Xe-135, U-235, U-238
Temperature: 293.6, 587.2, 880.8K
  
DISCRETE NEUTRON LIBRARIES: Discrete neutron cross sections are used with the DRXS input card in MCNP.
  
-  newxsd - discrete version of newxs (6 nuclides)
B-11, Eu-151, Eu-153, Ho-165, Hf-nat, Au-197
Temperature: 293.6K
  
-  drmccs - discrete version of rmccs and rmccsa (90 nuclides)
H-1, H-2, H-3, He-3, He-4, Li-6, Li-7, Be-9, B-10, B-11, C-nat, C-12, N-14, N-15, O-16, F-19, Na-23, Mg-nat, Al-27, Si-nat, P-31, S-32, Cl-nat, Ar-nat, K-nat, Ca-nat, Ti-nat, V-nat, Cr-nat, Mn-55, Fe-nat, Co-59, Ni-nat, Cu-nat, Ga-nat, As-75, Kr-78, Kr-80, Kr-82, Kr-83, Kr-84, Kr-86, Nb-93, Mo-nat, Rh-103, Rh-117, Pd-119, Ag-nat, Ag-107, Ag-109, Cd-nat, Sn-120, Ba-138, Eu-nat, Eu-151, Eu-153, Gd-nat, Ho-165, Ta-181, W-nat, W-182, W-183, W-184, W-186, Re-185, Re-187, Pt-nat, Au-197, Pb-nat, Bi-209, Th-232, Pa-233, U-233, U-234, U-235, U-236, U-237, U-238, U-239, Np-237, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am-241, Am-242, Am-243, Cm-242, Cm-244
Temperature: 293.6K
  
-  dre5 - discrete version of endf5u and endf5p (53 nuclides)
H-2, Li-7, B-11, F-19, Na-23, Mg-nat, Si-nat, P-31, S-32, Cl-nat, K-nat, Ca-nat, Ti-nat, V-nat, Mn-55, Fe-nat, Co-59, Y-89, Nb-93, Mo-nat, Cd-nat, Sm-149, Eu-152, Eu-154, Gd-152, Gd-154, Gd-155, Gd-156, Gd-157, Gd-158, Gd-160, Ta-181, W-182, W-183, W-184, W-186, Au-197, Bi-209, Th-232, Pa-233, U-234, U-236, U-237, Np-237, Pu-238, Pu-239, Pu-241, Pu-242, Am-241, Am-242, Am-243, Cm-242, Cm-244
Temperature: 293.6K
  
PHOTOATOMIC DATA LIBRARIES: There are now four photoatomic transport data libraries; mcplib, mcplib02, mcplib03, and mcplib04 from ENDF/B-IV, ENDF/B-IV/89, ENDF/B-VI.8
mcplib04, 100 elements from 1-H to 100-Fm
mcplib03, 94 elements from 1-H to 94-Pu
mcplib02, 94 elements from 1-H to 94-Pu
mcplib, 94 elements from 1-H to 94-Pu
  
MCNP MULTIGROUP DATA LIBRARIES:
The multigroup neutron and photon library mgxsnp is provided for use with MCNP, and is based primarily on ENDF/B-V evaluations. (95 nuclides/materials)
H, D, T, He-3, He-4, Li-6, Li-7, Be-7, Be-9, B-10, B-11, C, C-12, N-14, N-15, O-16, F-19, Na-23, Mg, Al-27, Si, P-31, S-32, Cl, Ar, K, Ca, Ti, V, Cr, Mn-55, Fe, Co-59, Ni, Cu, Ga, As-75, Kr-78, Kr-80, Kr-82, Kr-83, Kr-84, Kr-86, Zr, Nb-93, Mo, Rh-103, U235FP, Pu239FP, Ag, Ag-107, Ag-109, Cd, AveFP, FPP, FPA, Xe, Ba-138, Eu, Eu-151, Eu-153, Gd, Ho-165, Ta-181, W, W-182, W-183, W-184, W-186, Re-185, Re-187, Pt, Au-197, Pb, Bi-209, Th-232, Pa-233, U-233, U-234, U-235, U-236, U-237, U-238, U-239, Np-237, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am-241, Am-242m, Am-243, Cm-242, Cm-244
Temperature: 300K
Multi-group form: weight function is a combination of a Maxwellian thermal + 1/E + fission + fusion peak at 14.0 MeV. The data library contains no upscatter groups or self-shielding, and is most applicable for fast systems. P0 through P4 scattering matrices.
  
PHOTONUCLEAR DATA LIBRARIES: Photonuclear library, la150u (13 nuclides)
H-2, C-12, O-16, Al-27, Si-28, Ca-40, Fe-56, Cu-63, Ta-181, W-184, Pb-206, Pb-207, Pb-208
Temperature: 300K
  
THERMAL NEUTRON DATA LIBRARIES: S(alpha,beta) data are contained in the tmccs, therxs, and sab2002 libraries.
Beryllium Metal - Temperatures: 77, 294, 300, 400, 600, 800, 1000, 1200K
Benzene - Temperatures: 294, 300, 400, 500, 600, 800K
Beryllium Oxide - Temperatures: 294, 300 , 400, 600 , 800, 1000, 1200K
Ortho Deuterium - Temperatures: 19, 20K
Para Deuterium - Temperatures: 19, 20K
Graphite - Temperatures: 294, 300, 400, 600, 800, 1000, 1200, 1600, 2000K
Hydrogen in Zirconium Hydride : Temperatures: 294, 300, 400, 600, 800, 1000, 1200K
Ortho Hydrogen - Temperatures: 19, 20, 21, 22, 23, 24, 25K
Para Hydrogen - Temperatures: 19, 20, 21, 22, 23, 24, 25K
Deuterium in Heavy Water - Temperatures: 294, 300, 400, 500, 600, 800, 1000K
Hydrogen in Liquid Methane - Temperature: 100K
Hydrogen in Light Water - Temperatures: 294, 300, 400, 500, 600, 800, 1000K
Hydrogen in Polyethylene - Temperatures: 294, 300K
Hydrogen in Solid Methane - Temperature: 22K
Zirconium in Zirconium Hydride - Temperatures: 300, 400, 600, 800, 1200, 294, 400, 600, 800, 1000, 1200K
  
ELECTRON DATA LIBRARIES: el and el03 are the electron transport libraries.
el03, 100 elements from 1-H to 100-Fm
el, 94 elements from 1-H to 94-Pu
  
DOSIMETRY DATA LIBRARIES: 531dos, 532dos, and llldos are publicly released.
531dos, 18 nuclides based on ENDF/B-V.
532dos, 43 nuclides based on ENDF/B-V.
llldos, 348 nuclides based on LLNL ACTL library.
  
PROTON DATA LIBRARIES: la150h, 41 nuclides
H-1, H-2, C-12, N-14, O-16, Al-27, Si-28, Si-29, Si-30, P-31, Ca-40, Cr-50, Cr-52, Cr-53, Cr-54, Fe-54, Fe-56, Fe-57, Ni-58, Ni-60, Ni-61, Ni-62, Ni-64, Cu-63, Cu-65, Nb-93, W-182, W-183, W-184, W-186, Hg-196, Hg-198, Hg-199, Hg-200, Hg-201, Hg-202, Hg-204, Pb-206, Pb-207, Pb-208, Pb-209
  
The data libraries, as distributed, are in ASCII.

4. METHODS

  
MCNP5 1.40
==========
The MCNP5 code treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces and fourth-degree elliptical tori. Pointwise cross-section data are used. For neutrons, all reactions given in a particular cross-section evaluation (such as ENDF/B-VI) are accounted for. Thermal neutrons are described by both the free gas and S(alpha, beta) models. For photons, the code accounts for incoherent and coherent scattering, the possibility of fluorescent emission after photoelectric absorption, and absorption in electron-positron pair production. Electron/positron transport processes account for angular deflection through multiple Coulomb scattering, collisional energy loss with optional straggling, and the production of secondary particles including K x-rays, knock-on and Auger electrons, bremsstrahlung, and annihilation gamma rays from positron annihilation at rest. Electron transport does not include the effects of external or self-induced electromagnetic fields. Photonuclear physics is available for a limited number of isotopes. Important standard features that make MCNP very versatile and easy to use include a powerful general source, criticality source, and surface source; both geometry and output tally plotters; a rich collection of variance reduction techniques; a flexible tally structure; and an extensive collection of cross-section data. Energy ranges are from 10e-11 to 20 MeV for neutrons with data up to 150 MeV for some nuclides, 1 keV to 1 GeV for electrons, and 1 keV to 100 GeV for photons.
  
MCNPX 2.5.0
===========
MCNPX treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces and some special fourth-degree surfaces. Pointwise continuous-energy cross section data are used, although multigroup data may also be used. Fixed-source adjoint calculations may be made with the multigroup data option. For neutrons, all reactions in a particular cross-section evaluation are accounted for. Both free gas and S(alpha, beta) thermal treatments are used. Criticality sources as well as fixed and surface sources are available. For photons, the code takes account of incoherent and coherent scattering with and without electron binding effects, the possibility of fluorescent emission following photoelectric absorption, and absorption in pair production with local emission of annihilation radiation. A very general source and tally structure is available. The tallies have extensive statistical analysis of convergence. Rapid convergence is enabled by a wide variety of variance reduction methods. Energy ranges are 0-60 MeV for neutrons (data generally only available up to 20 MeV) and 1 keV - 1 GeV for photons and electrons.
  
MCNPDATA
========
The continuous energy libraries were generated by using the NJOY (Data Processing System of Evaluated Nuclear Data Files ENDF Format) ACER module.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

MCNP5 1.4.0: None noted.
  
MCNPX 2.5.0
===========
All standard MCNP neutron libraries over their stated ranges.
Neutrons in the LA150 library from 0.0 - 150.0 MeV in tabular range for 42 isotopes
(except for 9Be to 100 MeV).
Neutrons from 1.0 MeV in physics model regime.
Protons from 1.0 to 150.0 MeV in tabular range for 41 isotopes.
Protons from 1.0 MeV in physics model regime.
Pions, muons, and kaons are treated only by physics models.
Photons from 1 keV - 100 GeV.
Electrons from 1 keV - 1 GeV.
Neutrons do not create delayed photons.
Photonuclear interactions from 1.0 to 150.0 MeV in tabular range for 12 isotopes.
Photonuclear interactions from 1.0 MeV in the CEM physics model.

6. TYPICAL RUNNING TIME

MCNP5 1.4.0: On a 2 GHz Pentium 4, compilation of MCNP5 takes about 3 minutes, and the 42 test cases run in about 2 minutes.
  
MCNPX 2.5.0: Runtime for the test cases was 17 minutes for the test cases on a Dell PowerEdge6400 running Linux, 37 minutes on an IBM RS/6000 Model 270, and 43 minutes on a HP B1000 (PA 8500).

8. RELATED OR AUXILIARY PROGRAMS

MCNP5 1.4.0:
===========
Included in the distribution:
- MAKXSF: Prepares MCNP Cross-Section Libraries.
- VISED 19L: Visual Editor for interactively constructing & visualizing MCNP geometry (runs on Windows PCs only). More VISED information is on the web at the Visual Consultants website http://www.mcnpvised.com/.
    
MCNPX 2.5.0:
===========
Included in the distribution:
- GRIDCONV: Converts output of mesh and radiography tallies to input for external graphics programs.
- HTAPE3X: Postprocessor for MCNPX HISTP output.
- MAKXSF: Prepares MCNPX Cross-Section Libraries.
- HCNV and TRX: Convert LAHET ASCII data to binary.
- XSEX3: Analyzes a HISTP history file and generates double-differential particle production cross sections for primary beam interactions
  
MCNPDATA: NJOY (Data Processing System of Evaluated Nuclear Data Files ENDF Format)

10. REFERENCES

MCNPX 2.5.0
===========
Background references:
- L. S. Waters, Ed.: MCNPX User's Manual, Version 2.4.0, LA-CP-02-408 (Sept. 2002).
- L. S. Waters, Ed.: MCNPX User's Manual, Version 2.3.0, LA-UR-02-2607 (April
2002).
- J. F. Briesmeister, Ed.: MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C, LA-13709-M (April 2000).
- M. B. Chadwick, P. G. Young, S. Chiba, S. C. Frankle, G. M. Hale, H. G. Hughes, A. J. Koning, R. C. Little, R. E. MacFarlane, R. E. Prael, and L. S. Waters: Cross Section Evaluations to 150 MeV for Accelerator-Driven Systems and Implementation in MCNPX, (Nuclear Science and Engineering 131, Number 3 (March 1999) 293).
- M. B. Chadwick, P. G. Young, R. E. MacFarlane, P. Moller, G. M. Hale, R. C. Little, A. J. Koning and S. Chiba: LA150 Documentation of Cross Sections, Heating, and Damage: Part A (Incident Neutrons) and Part B (Incident Protons), LA-UR-99-1222 (1999).
- S. G. Mashnik, A. J. Sierk, O. Bersillon, and T. A. Gabriel: Cascade-Exciton Model Detailed Analysis of Proton Spallation at Energies from 10 MeV to 5 GeV, (Nucl. Instr. Meth. A414 (1998) 68) (Los Alamos National Laboratory Report LA-UR-97-2905).
- R. E. Prael and H.Lichtenstein: User Guide to LCS: The LAHET Code System, LA-UR-89-3014, Revised (September 15, 1989).

11. HARDWARE REQUIREMENTS

MCNP is operable on workstations or PC's running Windows or Linux, Unix workstations (Sun, IBM, and Alpha), Macintosh computers with MacOSX, and Itanium computers. Expanding and compiling the code system requires 270 MB, and the ASCII cross sections require 2.6 GB of hard disk space.
  
MCNPX runs under Unix, Linux, OS X, and Windows operating systems and has been implemented on various 32-bit and 64-bit workstations and personal computers. The compiled version of the code tends to run approx. 8 Mbytes. Dynamic allocation makes memory demands variable on all platforms.
  
MCNPDATA: At least 3.5 Gigabytes of free hard drive space is needed to uncompress and install the entire library.

13. SOFTWARE REQUIREMENTS

MCNP5 1.4.0
===========
MCNP 5 1.40 has improved support for newer Fortran 90 compilers. The compilers
supported are listed below. The c compilers listed are those used in making the executables for distribution.
- Fortran 90 compilers supported for Linux: Absoft 9.0 (seq, mpi) ; Intel 9.0 (seq, mpi) ; Lahey 6.2c (seq, mpi, omp) Pathscale 2.1 (64-b Opteron) (seq, mpi) ; Portland Group 6.0 (seq, mpi, omp)
- C compilers used for Linux executable: Intel compiler executable: gcc version 3.2.3 20030502 (Red Hat Linux 3.2.3-53); Opteron executable: gcc version 3.4.4 20050721 (Red Hat 3.4.4-2) iii
- Fortran 90 compilers supported for Mac OSX: Absoft Pro 9.0 (seq, mpi) ; IBM XL 8.1 (seq, mpi)
- C compilers used for Mac OSX executable: gcc 3.3
- Fortran 90 compilers supported for Windows 2000/XP: Absoft 9.0 (seq) ; Compaq 6.6b (seq, mpi) ; Intel 9.0 (seq,mpi) ; Lahey 7.1 (seq) -MPI Parallel versions can be built using cygwin: For PCs, parallel versions of MCNP5 can be built from the cygwin command line with the Intel and Compaq fortran compilers. Add 'mpi' to the config options or use the install script.
- C compilers used for Windows 2000/XP executable:
gcc compiler on cygwin, version 3.4.4; Microsoft Visual Studio .NET 2003 C/C++ compiler (with Compaq and Intel Fortran compilers)
  
Filenames of the distributed executables reflect the compilers used to create them:
mcnp5_rsicc_1.40_linux_intel.exe
mcnp5_rsicc_1.40_linux_pathscale32bit_omp.exe
mcnp5_rsicc_1.40_linux_pathscale64bit_omp.exe
mcnp5_rsicc_1.40_osf_cpq.exe [runs on HP/Compaq Alpha OSF1]
mcnp5_rsicc_1.40_osx_xlf.exe [runs on Mac OSX]
mcnp5_rsicc_1.40_sun_sun.exe [runs under Solaris 9]
MCNP5_rsicc_1.40_Windows_CVF_mpi.exe [Windows XP with MPI]
mcnp5_rsicc_1.40_Windows_Intel.exe [Windows XP]
  
Compilation of the MCNP5 source code in the C00730MNYCP00 distribution requires both Fortran 90 and ANSI C standard compilers. Dynamic storage allocation is available on all supported systems. MCNP5 has also run on SGI IRIX64 and IBM AIX. Additional information may be posted to the MCNP Forum archives in the electronic notebook on the RSICC website.
  
MPI, OpenMP or PVM based parallelism has been tested on some systems, using the vendor-supplied MPI, MPICH (on Linux and Windows), or PVM 3.4.3. It should be noted that while the developers still support PVM, using MPI is highly recommended. Applications on the LANL parallel computers use MPI, and that is the basis for nearly all parallel development and testing for MCNP5; PVM is tested only sporadically.
  
For compiling MCNP5 on Windows PCs, the Cygwin environment must first be installed. The Cygwin environment is a collection of GNU-based Unix utilities which have been ported to the Windows environment. The Cygwin environment may be obtained at no cost from the web site http://www.cygwin.com.
  
For plotting geometry, cross-sections, or results, X11 must be installed on your PC. An X-windows server is required to display the X11 graphics. Suggested servers include ReflectionX, Exceed, and XFree86.

MCNPX 2.5.0
===========
C and Fortran 90 compilers are required to compile. The GNU make utility is required to build the system on Unix and Linux platforms. The GNU make.exe utility is included for vii Windows users. The only graphics support for this release is X11 http://www.x.org/. This is a Fortran 90 version of MCNPX which uses standard F90 allocation schemes for dynamic variables on all platforms. The LANL developers ran MCNPX 2.5.0 on the systems listed below. Their executables are included in the distribution. Installation may fail with different compilers.
  
Sun-Solaris (5.8 & 5.9) with WorkShop Pro F95 6.2
HP-HPUX (10.20) with HP F90 2.4.10
IBM-AIX (4.3) with XL Fortran 7.1
Intel-Linux RedHat Enterprise (3.2) with Portland Group 5.2
Intel-Linux RedHat Enterprise (3.2) with Intel Fortran 8.0
Intel-Linux RedHat (7.2) with Portland Group 3.3
Intel-Windows XP with Intel Fortran 8.1 and MS VC++ 7.1
Intel-Windows XP with Compaq Visual Studio 6.6 and MS VC++ 7.1
  
The developers also tested MCNPX on Mac-OS X (Darwin 7.8) with XL Fortran 8.1, but this executable is not included in the package. RSICC tested this release on the following systems:
  
AIX 4.3.3 (IBM 43P-260) with XL C/C++ 4.4; XL Fortran 6.1.
Dell PowerEdge6400 running RedHat Linux 7.0 with PGF90 4.0-2 & gcc.
Intel Pentium running RedHat Linux 6.1 with PGF90 3.3-2 and pgcc.
Sun UltraSparc 60 under SunOS5.6 with F90 2.0 and C++ 5.0.
Pentium 4 running Windows2000 SP4 with CVF 6.6B

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

WinZIP 8.0 is required to expand the GNU compressed Unix tar files under Windows.
  
Parallel Processing
- Distributed memory multiprocessing for all particles and energies,
- Message passing interface (MPI) multiprocessing,
- Significant speedup of criticality problems run with MPI.
  
Compiling, Configuration, and Installation
- FORTRAN90 modularity and dynamic memory allocation,
- 64-bit integer support,
- NAG/IBM/INTEL compiler extensions for Unix, Linux, and Windows.

15. NAME AND ESTABLISHMENT OF AUTHORS

Contributed by:
                Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U. S. A.

Developed by:   Los Alamos National Laboratory,
                Los Alamos, New Mexico, U.S.A.