Calculated K-Effectives for Light Water Reactor Typical, U + Pu Nitrate Solution Critical

Conference · Mon May 17 00:00:00 EDT 1982

OSTI ID:5367375

Primm, III, R. T. ^[1]; Mincey, J. F. ^[1]

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1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

The Department of Energy's Consolidated Fuel Reprocessing Program has as a goal the design of nuclear fuel reprocessing equipment. In order to validate computer codes used for criticality analyses in the design of such equipment, k-effectives have been calculated for several U + Pu nitrate solution critical experiments. As of January 1981, descriptions of 45 unpoisoned, U + Pu solution experiments were available in the open literature. Twelve of these experiments were performed with solutions which have physical characteristics typical of dissolved, light water reactor fuel. This paper contains a discussion of these twelve experiments, a review of the calculational procedure used to determine k-effectives, and the results of the calculations.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Office of Nuclear Fuel Cycle
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5367375
• Report Number(s): CONF-820566-3; ON: DE82015698; TRN: 82-012808
• Resource Relation: Conference: Thermal Reactor Benchmark Calculations, Techniques, Results and Applications Seminar, Upton, NY (United States), 17-18 May 1982; Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
CONSOLIDATED FUEL REPROCESSING PROGRAM
PLUTONIUM NITRATES
CRITICALITY
URANIUM NITRATES
BWR TYPE REACTORS
CALCULATION METHODS
PWR TYPE REACTORS
ACTINIDE COMPOUNDS
COORDINATED RESEARCH PROGRAMS
NITRATES
NITROGEN COMPOUNDS
OXYGEN COMPOUNDS
PLUTONIUM COMPOUNDS
REACTORS
RESEARCH PROGRAMS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
WATER COOLED REACTORS
WATER MODERATED REACTORS
Nuclear Criticality Safety Program (NCSP)
Department of Energy Consolidated Fuel Reprocessing Program
KENO-IV
Monte Carlo
XSDRNPM
Criticality Safety Reference Library (CSRL)
Evaluated Nuclear Data File (ENDF)
Uranium
Plutonium
Nuclear Fuel Reprocessing Equipment
Light Water Reactor (LWR) Fuel
050800* - Nuclear Fuels- Spent Fuels Reprocessing
054000 - Nuclear Fuels- Health & Safety
420203 - Engineering- Handling Equipment & Procedures