Published March 1986 | Version v1
Report Restricted

Computational methodology for the Oak Ridge Research Reactor (ORR) and Bulk Shielding Reactor (BSR): cross-section and validation. Volume 1

Creators

Description

A neutronics library suitable for low-enrichment uranium (LEU) and high-enrichment uranium (HEU) fueled cores for both the Oak Ridge Research Reactor (ORR) and the Bulk Shielding Reactor (BSR) is documented herein. The library is obtained from version V of the Evaluated Nuclear Data File (ENDF/B-V) and contains 223 nuclides weighted over a variety of region-dependent neutron spectra. Self-shielding and zone-weighting effects are incorporated with 227-group calculations for several reactor-core configurations. Libraries are archived for both transport and diffusion theory seven-group calculations. Complete listings of processing details are included so that libraries with different specifications can be easily obtained. Results from validation calculations indicate that the neutronics libraries obtained from this effort are suitable for neutronics computations for the ORR and BSR. 12 refs., 5 figs., 15 tabs

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A05/MF A01 - GPO as TI86008415.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
83 p.
Report number
NUREG/CR--3064-Vol.1

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
17078881
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
BSR-1 REACTOR; BSR-2 REACTOR; CONTROL ELEMENTS; CROSS SECTIONS; DIFFERENTIAL EQUATIONS; FISSION PRODUCTS; HIGHLY ENRICHED URANIUM; MOCKUP; NEUTRON TRANSPORT THEORY; ORR REACTOR; REACTOR CORES; REACTOR KINETICS; SELF-SHIELDING; SLIGHTLY ENRICHED URANIUM
Descriptors DEC
ACTINIDES; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; EQUATIONS; ISOTOPE ENRICHED MATERIALS; ISOTOPES; KINETICS; MATERIALS; METALS; POOL TYPE REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; STRUCTURAL MODELS; TANK TYPE REACTORS; THERMAL REACTORS; TRANSPORT THEORY; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
ORNL/TM--9968-Vol.1.