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Title: Validation of MCNP: SPERT-D and BORAX-V fuel

Abstract

This report discusses critical experiments involving SPERT-D{sup 1,2} fuel elements and BORAX-V{sup 3-8} fuel which have been modeled and calculations performed with MCNP. MCNP is a Monte Carlo based transport code. For this study continuous-energy nuclear data from the ENDF/B-V cross section library was used. The SPERT-D experiments consisted of various arrays of fuel elements moderated and reflected with either water or a uranyl nitrate solution. Some SPERT-D experiments used cadmium as a fixed neutron poison, while others were poisoned with various concentrations of boron in the moderating/reflecting solution. ne BORAX-V experiments were arrays of either boiling fuel rod assemblies or superheater assemblies, both types of arrays were moderated and reflected with water. In one boiling fuel experiment, two fuel rods were replaced with borated stainless steel poison rods.

Authors:
;
Publication Date:
Research Org.:
Westinghouse Idaho Nuclear Co., Inc., Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
10146373
Report Number(s):
WINCO-1112
ON: DE93012546; IN: CSS-92-015
DOE Contract Number:
AC07-84ID12435
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Nov 1992
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; FUEL ELEMENTS; TESTING; FUEL ASSEMBLIES; M CODES; VALIDATION; FUEL PLATES; SLABS; REACTOR LATTICES; URANIUM ALLOYS; ALUMINIUM ALLOYS; MODERATORS; COMPUTER CALCULATIONS; 220300; 990200; MATHEMATICS AND COMPUTERS

Citation Formats

Crawford, C., and Palmer, B. Validation of MCNP: SPERT-D and BORAX-V fuel. United States: N. p., 1992. Web.
Crawford, C., & Palmer, B. Validation of MCNP: SPERT-D and BORAX-V fuel. United States.
Crawford, C., and Palmer, B. Sun . "Validation of MCNP: SPERT-D and BORAX-V fuel". United States. doi:.
@article{osti_10146373,
title = {Validation of MCNP: SPERT-D and BORAX-V fuel},
author = {Crawford, C. and Palmer, B.},
abstractNote = {This report discusses critical experiments involving SPERT-D{sup 1,2} fuel elements and BORAX-V{sup 3-8} fuel which have been modeled and calculations performed with MCNP. MCNP is a Monte Carlo based transport code. For this study continuous-energy nuclear data from the ENDF/B-V cross section library was used. The SPERT-D experiments consisted of various arrays of fuel elements moderated and reflected with either water or a uranyl nitrate solution. Some SPERT-D experiments used cadmium as a fixed neutron poison, while others were poisoned with various concentrations of boron in the moderating/reflecting solution. ne BORAX-V experiments were arrays of either boiling fuel rod assemblies or superheater assemblies, both types of arrays were moderated and reflected with water. In one boiling fuel experiment, two fuel rods were replaced with borated stainless steel poison rods.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Nov 01 00:00:00 EST 1992},
month = {Sun Nov 01 00:00:00 EST 1992}
}

Technical Report:
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  • This report discusses critical experiments involving SPERT-D[sup 1,2] fuel elements and BORAX-V[sup 3-8] fuel which have been modeled and calculations performed with MCNP. MCNP is a Monte Carlo based transport code. For this study continuous-energy nuclear data from the ENDF/B-V cross section library was used. The SPERT-D experiments consisted of various arrays of fuel elements moderated and reflected with either water or a uranyl nitrate solution. Some SPERT-D experiments used cadmium as a fixed neutron poison, while others were poisoned with various concentrations of boron in the moderating/reflecting solution. ne BORAX-V experiments were arrays of either boiling fuel rod assembliesmore » or superheater assemblies, both types of arrays were moderated and reflected with water. In one boiling fuel experiment, two fuel rods were replaced with borated stainless steel poison rods.« less
  • The development of sensors for measurement of temperatures to 2760 deg C in the center of UO/sub 2/-fueled, boiling fuel rods for BORAX-V is discussed. Samples of tantalumsheathed thermocouples with BeO and MgO insulation were tested to failure. Tungsten vs tungsten-26% rhenium was utilized as the thermocouple pair. The first group of thermocouples tested failed at 1650 deg C. Evaluation of 8 other thermocouples showed that the maximum temperature that they can measure accurately is approximately 22OO deg C. The limiting factor is the temperature at which a reaction between BeO and Ta begins. (M.C.G.)
  • Infinite media calculations have been performed to validate the new MCNP ENDF/B-VI Library, ENDF60. All 124 nuclides have neutron flux and heating tallies compared against ENDF/B-V, as well as the MCNP Recommended Data Sets when these were not ENDF/B-V. For nuclides with photon production, photon flux and heating tallies have also been compared. All significant differences between the new ENDF60 results and those obtained with other data sets are discussed. This report provides a method for data comparison so that a better decision can be made as to the best data set to be used for a particular problem.