skip to main content

Title: Summary of HTGR (high-temperature gas-cooled reactor) benchmark data from the high temperature lattice test reactor

The High Temperature Lattice Test Reactor (HTLTR) was a unique critical facility specifically built and operated to measure variations in neutronic characteristics of high temperature gas cooled reactor (HTGR) lattices at temperatures up to 1000{degree}C. The Los Alamos National Laboratory commissioned Pacific Northwest Laboratory (PNL) to prepare this summary reference report on the HTLTR benchmark data and its associated documentation. In the initial stages of the program, the principle of the measurement of k{sub {infinity}} using the unpoisoned technique (developed by R.E. Heineman of PNL) was subjected to extensive peer review within PNL and the General Atomic Company. A number of experiments were conducted at PNL in the Physical Constants Testing Reactor (PCTR) using both the unpoisoned technique and the well-established null reactivity technique that substantiated the equivalence of the measurements by direct comparison. Records of all data from fuel fabrication, the reactor experiments, and the analytical results were compiled and maintained to meet applicable quality assurance standards in place at PNL. Sensitivity of comparisons between measured and calculated k{sub {infinity}}(T) data for various HTGR lattices to changes in neutron cross section data, graphite scattering kernel models, and fuel block loading variations, were analyzed by PNL for the Electric Powermore » Research Institute. As a part of this effort, the fuel rod composition in the dilute {sup 233}UO{sub 2}-ThO{sub 2} HTGR central cell (HTLTR Lattice {number sign}3) was sampled and analyzed by mass spectrometry. Values of k{sub {infinity}} calculated for that lattice were about 5% higher than those measured. Trace quantities of sodium chloride were found in the fuel rod that were equivalent to 22 atom parts-per-million of natural boron.« less
Authors:
Publication Date:
OSTI Identifier:
5101840
Report Number(s):
PNL-7178
ON: DE90006379; TRN: 90-006143
DOE Contract Number:
AC06-76RL01830
Resource Type:
Technical Report
Research Org:
Pacific Northwest Lab., Richland, WA (USA)
Sponsoring Org:
DOE/NE
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; HTLTR REACTOR; REACTOR LATTICES; BENCHMARKS; COMPARATIVE EVALUATIONS; CONTROL ELEMENTS; DECISION MAKING; DEMONSTRATION PROGRAMS; EXPERIMENTAL DATA; FUEL ELEMENTS; HTGR TYPE REACTORS; IMPURITIES; REACTIVITY COEFFICIENTS; REACTOR KINETICS; RESEARCH PROGRAMS; TECHNOLOGY ASSESSMENT; TEMPERATURE EFFECTS; TEST FACILITIES; DATA; ENRICHED URANIUM REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; INFORMATION; KINETICS; NITROGEN COOLED REACTORS; NUMERICAL DATA; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TEST REACTORS 220400* -- Nuclear Reactor Technology-- Control Systems; 220600 -- Nuclear Reactor Technology-- Research, Test & Experimental Reactors; 210300 -- Power Reactors, Nonbreeding, Graphite Moderated; 220100 -- Nuclear Reactor Technology-- Theory & Calculation