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 Power 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.
- Research Organization:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5101840
- Report Number(s):
- PNL-7178; ON: DE90006379; TRN: 90-006143
- Country of Publication:
- United States
- Language:
- English
Similar Records
Reactor Physics Quarterly Report (April, May, June 1970)
Evaluation of temperature coefficients of reactivity for /sup 233/U--thorium fueled HTGR lattices. Final report
Related Subjects
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