1. NAME AND TITLE OF DATA LIBRARY
LUMP: Evaluated Lumped Fission Product Cross Sections for Fast Reactor Analysis--Based on ENDF/B-V Data.
2. NAME AND TITLE OF DATA RETRIEVAL PROGRAMS
No retrieval program is included in the package.
Argonne National Laboratory, Argonne, Illinois.
4. HISTORICAL BACKGROUND AND INFORMATION
It is standard practice in fast reactor analysis to employ a lumped time-independent cross section set to simulate fission products over a burnup cycle. Various lumping schemes have been used in the past; in order to assess the relative merits of various models it is necessary to consider basic issues such as the dependence on burnup history, fuel composition and neutron spectrum, the impact of data base used, the proper application of the lumped data, the effects of scattering matrix, and the impact of the lumped data on reactor performance.
Recent fast reactor analysis studies at ANL relied on the ENDF/B-III lumped fission product data
which are based on the Garrison-Roos model. In an attempt to update this information, an attempt was
made to develop a lumped fission product cross section library from the ENDFB-V files. Both one-lump and two-lump models ere investigated in detail.
5. APPLICATION OF THE DATA
The inventory of fission products in a reactor is determined by the operating history of the reactor
and the nuclear processes which affect the fission products. The latter include direct yield from fission,
several possible modes of radioactive decay, and neutron absorptions. Because there are roughly 100
possible fission product chains consisting of about 800 nuclides, a complete description of all decay
and coupling mechanisms which relate the fission product chains is complicated.
6. SOURCE AND SCOPE OF DATA
The EPRI-CINDER-2 computer code was used in this study. Its basic function is to solve the large
set of coupled differential equations which describe the temporal concentrations of fission products and
actinides in a nuclear reactor. It uses the "linear chain" technique to reduce the complexity of the chain
structures. It is suitable for mixed oxide core fast reactor applications. Data are in ENDF/B-V format
and the MERGE retrieval program is included to the format of the cross sections.
7. DISCUSSION OF THE DATA RETRIEVAL PROGRAM
8. DATA FORMAT AND COMPUTER
EBCDIC card images; IBM 360/370.
9. TYPICAL RUNNING TIME
J. R. Liaw and H. Henryson II, "Evaluation of Lumped Fission Product Cross Sections for Fast Reactor Analysis - An Update," Intra-Laboratory Memo (May 1981).
J. R. Liaw and H. Henryson II, "Evaluation of Lumped Fission Product Cross Sections for Fast
Reactor Analysis," FRA-TM-134 (February 1981).
11. CONTENTS OF LIBRARY
Included are the referenced documents and one (1.2MB) DOS diskette which contains the LUMP
JCL and sample problem, the MERGER source, the LUMP cross section data, and the LUMP merged
cross sections, plus output from the sample problem.
12. DATE OF ABSTRACT
KEYWORDS: FISSION PRODUCT CROSS SECTIONS