RSIC DATA LIBRARY DLC‑223

 

 

1.   NAME AND TITLE OF DATA LIBRARY

FSXLIB-J33:     Continuous Energy Neutron Cross Section Library for MCNP Based on JENDL 3.3.

 

2.   NAME AND TITLE OF DATA RETRIEVAL PROGRAMS

MAKXSF:         Code for converting cross sections to binary form.

 

3.   CONTRIBUTOR

Nuclear Data Center at Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki-ken, Japan, through Research Organization for Information Science & Technology, Tokai-mura, Naka-gun, Japan.

 

4.   HISTORICAL BACKGROUND AND INFORMATION

The newest of the FSXLIB libraries based on JENDL-3.3 was released in Japan in May 2002. It is called FSXLIB-J33 and is a continuous energy cross section library for use with MCNP. Two problems were identified in the original JENDL-3.3 in Am-241 data.  One is the missing of MF/MT=4/18, and the other is incorrect neutron spectra for MT=18 below 500 keV. The updated data were designated JENDL-3.3u. These modifications, plus some corrections to the mass table in xsdir for some missing nuclei, were reflected in the previous release, which was distributed by RSICC with package identifier D00223MNYCP00. In the current release, RSICC ID: D00223MNYCP01, index files xsdir.fsxlb331 and xsdir.fsxlb332 were updated to include atomic weights, which were missing for 23 nuclides.

 

5.   APPLICATION OF THE DATA

FSXLIB-J33 was developed for solving neutron transport calculations with the CCC-700/MCNP4C code system. The data can also be used with other versions of MCNP. Reliability of the library was confirmed by solving several benchmark problems.

 

6.   SOURCE AND SCOPE OF DATA

A modified version of the NJOY 99.67 processing code from LANL was used to produce ACE type cross section data from JENDL 3.3. Modifications are noted in the JAERI-Data/Code 2003-011 report, which is included in this package. The format conforms to the continuous energy neutron cross section table as defined in the MCNP4C manual.  Photon production data are supplied for some nuclides in the expanded photon production format. Kerma factors are provided. The processing temperature of cross section is 300 K. Upper limit of thermal region: 4.6 eV. Accuracy of pointwise cross-section reconstruction: 0.1%. The FSXLIB-J33 library includes 337 nuclides.

 

H - 1, H - 2, HE- 3, HE- 4, LI- 6, LI- 7, BE- 9, B - 10, B - 11, C - nat, N - 14, N - 15, O - 16, F - 19, NA- 23, MG- 24, MG- 25, MG- 26, AL- 27, SI- 28, SI- 29, SI- 30, P - 31, S - 32, S - 33, S - 34, S - 36, CL- 35, CL- 37, AR- 40, K - 39, K - 40, K - 41, CA- 40, CA- 42, CA- 43, CA- 44, CA- 46, CA- 48, SC- 45, TI- 46, TI- 47, TI- 48, TI- 49, TI- 50, 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- 69, GA- 71, GE- 70, GE- 72, GE- 73, GE- 74, GE- 76, AS- 75, SE- 74, SE- 76, SE- 77, SE- 78, SE- 79, SE- 80, SE- 82, BR- 79, BR- 81, KR- 78, KR- 80, KR- 82, KR- 83, KR- 84, KR- 85, KR- 86, RB- 85, RB- 87, SR- 86, SR- 87, SR- 88, SR- 89, SR- 90, Y - 89, Y - 91, ZR- 90, ZR- 91, ZR- 92, ZR- 93, ZR- 94, ZR- 95, ZR- 96, NB- 93, NB- 94, NB- 95, MO- 92, MO- 94, MO- 95, MO- 96, MO- 97, MO- 98, MO- 99, MO-100, TC- 99, RU- 96, RU- 98, RU- 99, RU-100, RU-101, RU-102, RU-103, RU-104, RU-106, RH-103, RH-105, PD-102, PD-104, PD-105, PD-106, PD-107, PD-108, PD-110, AG-107, AG-109, AG-110m,CD-106, CD-108, CD-110, CD-111, CD-112, CD-113, CD-114, CD-116, IN-113, IN-115, SN-112, SN-114, SN-115, SN-116, SN-117, SN-118, SN-119, SN-120, SN-122, SN-123, SN-124, SN-126, SB-121, SB-123, SB-124, SB-125, TE-120, TE-122, TE-123, TE-124, TE-125, TE-126, TE-127m,TE-128, TE-129m,TE-130, I -127, I -129, I -131, XE-124, XE-126, XE-128, XE-129, XE-130, XE-131, XE-132, XE-133, XE-134, XE-135, XE-136, CS-133, CS-134, CS-135, CS-136, CS-137, BA-130, BA-132, BA-134, BA-135, BA-136, BA-137, BA-138, BA-140, LA-138, LA-139, CE-140, CE-141, CE-142, CE-144, PR-141, PR-143, ND-142, ND-143, ND-144, ND-145, ND-146, ND-147, ND-148, ND-150, PM-147, PM-148, PM-148m,PM-149, SM-144, SM-147, SM-148, SM-149, SM-150, SM-151, SM-152, SM-153, SM-154, EU-151, EU-152, EU-153, EU-154, EU-155, EU-156, GD-152, GD-154, GD-155, GD-156, GD-157, GD-158, GD-160, TB-159, ER-162, ER-164, ER-166, ER-167, ER-168, ER-170, HF-174, HF-176, HF-177, HF-178, HF-179, HF-180, TA-181, W -182, W -183, W -184, W -186, HG-196, HG-198, HG-199, HG-200, HG-201, HG-202, HG-204, PB-204, PB-206, PB-207, PB-208, BI-209, RA-223, RA-224, RA-225, RA-226, AC-225, AC-226, AC-227, TH-227, TH-228, TH-229, TH-230, TH-232, TH-233, TH-234, PA-231, PA-232, PA-233, U -232, U -233, U -234, U -235, U -236, U -237, U -238, NP-235, NP-236, NP-237, NP-238, NP-239, PU-236, PU-237, PU-238, PU-239, PU-240, PU-241, PU-242, PU-244, PU-246, AM-241, AM-242, AM-242m,AM-243, AM-244, AM-244m, CM-240, CM-241, CM-242, CM-243, CM-244, CM-245, CM-246, CM-247, CM-248, CM-249, CM-250, BK-247, BK-249, BK-250, CF-249, CF-250, CF-251, CF-252, CF-254, ES-254, ES-255, FM-255.

 

7.   DISCUSSION OF THE DATA RETRIEVAL PROGRAMS

MAKXSF, which is distributed with MCNP code packages, can be used to convert MCNP Type 1 (ASCII) data to Type 2 (binary). MAKXSF is not included in this distribution; it is distributed in MCNP(X) code packages.

 

8.   DATA FORMAT AND COMPUTER

ASCII card images and 32-bit x86 CPU binary; Windows, Linux or Unix. A Type 2 (binary, 32 bit x86 PC) file is also included. (RSICC package id: D00223/MNYCP/01).

 

9.   TYPICAL RUNNING TIME

The running time for MAKXSF depends on the size of library treated, and usually ranges from several seconds to several minutes.

10.  REFERENCES

a. included in the documentation:

K. Kosako, N. Yamano, T. Fukahori, K. Shibata and A. Hasegawa, “The Libraries FSXLIB and MATXSLIB based on JENDL-3.3,” JAERI-Data/Code 2003-011 (July 2003). Note that the MATXS library is not included in the DLC-222 package.

b. background information:

K. Shibata, T. Kawano, T. Nakagawa, O. Iwamoto, J. Katakura, T. Fukahori, S. Chiba, A. Hasegawa, T. Murata,H. Matsunobu, T. Ohsawa, Y. Nakajima, T. Yoshida, A. Zukeran, M. Kawai, M. Baba, M. Ishikawa, T. Asami, T. Watanabe, Y. Watanabe, M. Igashira, N. Yamamuro, H. Kitazawa, N. Yamano and H. Takano: "Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3," J. Nucl. Sci. Technol. 39, 1125 (2002).

J. F. Briesmeister, Ed., "MCNP - A Gener¬al Monte Carlo N-Particle Transport Code, Version 4C," LA-13709-M (April 2000).

R. E. MacFarlane and D. W. Muir, “The NJOY Nuclear Data Processing System Version 91,” LA-12740-M (October 1994).

 

11.  CONTENTS OF LIBRARY

Included are the referenced document in 10.a, data library, and xsdir in a Unix compressed tar file. The package is transmitted on a CD-ROM. The uncompressed ascii file is about 1 GB.

 

12.  DATE OF ABSTRACT

July 2005, revised December 2006.

 

KEYWORDS:   BASED ON JENDL; EVALUATED NEUTRON CROSS SECTIONS; MCNP FORMAT; NEUTRON CROSS SECTIONS