RSICC DATA PACKAGE DLC-207

1. NAME AND TITLE OF DATA LIBRARY

MENDL-2P: Proton Reaction Data Library for Nuclear Activation (Medium Energy Nuclear Data Library).

2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

None included.

3. CONTRIBUTORS

Institute of Physics and Power Engineering, Obninsk, Russia, and NRG Nuclear Research and Consultancy Group, Petten, The Netherlands, through the OEC NEA Data Bank, Issy-les-Moulineaux, France.

4. HISTORICAL BACKGROUND AND INFORMATION

This distribution contains the NEA Data Bank packages identified as IAEA-1376/01 and IAEA-1376/02. The IAEA-1376/01 Medium Energy Nuclear Data Library MENDL-2P proton induced intermediate energy cross sections were generated by Shubin, Lunev, Konobeyev and Dityuk at IPPE.

The library is also available in version IAEA1376/02 which has been converted to ENDF-6 format and verified through the ENDF-6 format utility codes (CHECKR, FIZCON and PSYCHE). This work was done by A.J. Koning, ECN Petten.

5. APPLICATION OF THE DATA

This neutron reaction data library can be used for nuclear activation and transmutation applications at energies up to 100 MeV.

6. SOURCE AND SCOPE OF DATA

This package is an ENDF6 activation library including proton cross-sections for 504 nuclei with atomic number from 13 to 84 at the energies up to 200 MeV. It is based on the Medium Energy Nuclear Data Library (MENDL-2). MENDL-2 proton cross-sections are calculated on the base of ALICE-IPPE which differs from the ALICE-91 as follows: The algorithm for the level density calculation according to the generalized superfluid model was tested, corrected and improved. The pre-equilibrium cluster emission calculation is included in the code. Calculation of the alpha-particle spectra is performed taking into account the pick-up and knock-out processes. The phenomenological approach is used to describe direct channel for the deuteron emission. The triton and He-3 spectra are calculated according to the coalescence pick-up model of Sato, Iwamoto, Harada.

Double precision calculations are used in all code. Corrections were made for cross-sections calculations taking into account gamma-ray emission. The contribution for residual Z-XX-A nucleus production due to photon emission for residual Z-Xx-(A-1) or (Z-1)-XX-(A-1) is considered.

The corrections were made for the algorithm of multiple precompound proton emission spectra calculation near threshold, Kalbach systematic treatment, angular distribution printing algorithm, gamma-spectra printing and for some other instructions.

NUCLIDES:

AG105, AG107, AG109, AG111, AL26, AL27, AR36, AR37, AR38, AR39, AR40, AR42, AS71, AS72, AS73, AS74, AS75, AS76, AS77, AU194, AU195, AU196, AU197, AU198, AU199, BA128, BA130, BA131, BA132, BA133, BA134, BA135, BA136, BA137, BA138, BA140, BI205, BI206, BI207, BI208, BI209, BR77, BR79, BR81, BR82, CA40, CA41, CA42, CA43, CA44, CA45, CA46, CA47, CA48, CD106, CD108, CD109, CD110, CD111, CD112, CD113, CD114, CD115, CD116, CE136, CE138, CE139, CE140, CE141, CE142, CE143, CE144, CL35, CL36, CL37, CO56, CO57, CO58, CO59, CO60, CR50, CR51, CR52, CR53, CR54, CS129, CS131, CS132, CS133, CS134, CS135, CS136, CS137, CU63, CU65, CU67, DY154, DY156, DY158, DY159, DY160, DY161, DY162, DY163, DY164, DY166, ER162, ER164, ER166, ER167, ER168, ER169, ER170, ER172, EU145, EU146, EU147, EU148, EU149, EU151, EU152, EU153, EU154, EU155, EU156, FE53, FE54, FE55, FE56, FE57, FE58, FE59, FE60, GA67, GA69, GA71, GD146, GD147, GD148, GD149, GD150, GD151, GD152, GD153, GD154, GD155, GD156, GD157, GD158, GD160, GE68, GE69, GE70, GE71, GE72, GE73, GE74, GE76, HF173, HF174, HF175, HF176, HF177, HF178, HF179, HF180, HF181, HF182, HG194, HG196, HG197, HG198, HG199, HG200, HG201, HG202, HG203, HG204, HO163, HO165, HO166, I124, I125, I126, I127, I129, I131, IN111, IN113, IN115, IR188, IR189, IR190, IR191, IR192, IR193, K39, K40, K41, KR78, KR79, KR80, KR81, KR82, KR83, KR84, KR85, KR86, LA137, LA138, LA139, LA140, LU169, LU170, LU171, LU172, LU173, LU174, LU175, LU176, LU177, MN52, MN53, MN54, MN55, MO100, MO92, MO93, MO94, MO95, MO96, MO97, MO98, MO99, NB91, NB92, NB93, NB94, NB95, ND140, ND142, ND143, ND144, ND145, ND146, ND147, ND148, ND150, NI56, NI57, NI58, NI59, NI60, NI61, NI62, NI63, NI64, NI66, OS184, OS185, OS186, OS187, OS188, OS189, OS190, OS191, OS192, OS193, OS194, P31, P32, P33, PB202, PB203, PB204, PB205, PB206, PB207, PB208, PD100, PD102, PD103, PD104, PD105, PD106, PD107, PD108, PD110, PM143, PM144, PM145, PM146, PM147, PM148, PM149, PM151, PO206, PO208, PO209, PR141, PR143, PT190, PT191, PT192, PT193, PT194, PT195, PT196, PT198, RB83, RB84, RB85, RB86, RB87, RE182, RE183, RE184, RE185, RE186, RE187, RE189, RH101, RH102, RH103, RH105, RH99, RU100, RU101, RU102, RU103, RU104, RU106, RU96, RU97, RU98, RU99, S32, S33, S34, S35, S36, SB119, SB121, SB122, SB123, SB124, SB125, SB126, SB127, SC45, SC46, SC47, SC48, SE72, SE74, SE75, SE76, SE77, SE78, SE79, SE80, SE82, SI28, SI29, SI30, SI32, SM144, SM145, SM146, SM147, SM148, SM149, SM150, SM151, SM152, SM153, SM154, SN112, SN113, SN114, SN115, SN116, SN117, SN118, SN119, SN120, SN121, SN122, SN123, SN124, SN125, SN126, SR82, SR83, SR84, SR85, SR86, SR87, SR88, SR89, SR90, TA177, TA179, TA180, TA181, TA182, TA183, TB153, TB155, TB156, TB157, TB158, TB159, TB160, TB161, TC96, TC97, TC98, TC99, TE118, TE120, TE121, TE122, TE123, TE124, TE125, TE126, TE128, TE130, TE132, TI44, TI46, TI47, TI48, TI49, TI50, TL200, TL201, TL202, TL203, TL204, TL205, TM165, TM167, TM168, TM169, TM170, TM171, TM172, V48, V49, V50, V51, W178, W180, W181, W182, W183, W184, W185, W186, W188, XE124, XE126, XE127, XE128, XE129, XE130, XE131, XE132, XE133, XE134, XE136, Y87, Y88, Y89, Y90, Y91, YB166, YB168, YB169, YB170, YB171, YB172, YB173, YB174, YB175, YB176, ZN64, ZN65, ZN66, ZN67, ZN68, ZN70, ZN72, ZR88, ZR89, ZR90, ZR91, ZR92, ZR93, ZR94, ZR95, ZR96.

7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM

No retrieval program is included. The data are in ENDF-6 format and were verified through the ENDF-6 format utility codes CHECKR, FIZCON and PSYCHE (PSR-333/CHENDF 6.12).

8. DATA FORMAT AND COMPUTER

ASCII format; IBM PC (D00207MNYCP00).

9. TYPICAL RUNNING TIME

Not applicable.

10. REFERENCES

Documentation available with library in electronic PDF format in D207.PDF:

Yu. N. Shubin, V. P. Lunev, A. Yu. Konobeyev, A. I. Dityuk, "MENDL-2P Proton Reaction Data Library for Nuclear Activation (Medium Energy Nuclear Data Library)," IAEA-NDS-204 (January 1998). Summary description by P. K. McLaughlin and V. G. Pronyaev.

Yu. N. Shubin, et al., "MENDL-2 Neutron Reaction Data Library for Nuclear Activation and Transmutation at Intermediate Energies," IAEA-NDS-136 Rev. 1 (July 1995). Summary description by H. D. Lemmel.

Yu.N. Shubin, V. P. Lunev, A.Yu. Konobeyev, A. I. Dityuk, "Cross-Secton Data Library MENDL-2 Study Activation and Transmutation of Materials Irradiated by Nucleons of Intermediate Energies," INDC(CCP)-385 (May 1995).

11. CONTENTS OF LIBRARY

The package is transmitted on a CD which contains a self-extracting compressed Windows file with the data libraries and documents in PDF format. After decompression, the MENDL-2P libraries require approximately 136MB and 50MB of disk space.

12. DATE OF ABSTRACT

March 2002.

KEYWORDS: ACTIVATION; ENDF FORMAT; REACTION CROSS SECTIONS