[en] Task analyses were used to assist in identifying improvements needed in the training curriculum for selected positions at the Power Burst Facility (PBF). Four positions were examined: Experiment Power Reactor Operator, Experiment (EPRO-Ex); Experiment Power Reactor Operator, Plant (EPRO-P); Experiment Power Reactor Operator, Console (EPRO-Co), and Shift Supervisor (SS). A complete position task listing and core of tasks defined in terms of (a) level of difficulty to perform, (b) severity of consequence if performed improperly, and (c) associated error probability were identified by each position. The systems, academic, and administrative knowledge needed by job incumbents to perform each task was noted. Strategies for teaching the knowledge associated with these tasks are presented

[en] This paper describes the unique and diverse test capabilities of the Power Burst Facility (PBF). The PBF test reactor, located at the Idaho National Engineering Laboratory (INEL), simulates normal, off-normal, and accident operating conditions of light water reactor fuel rods. Capabilities of the PBF are illustrated by brief discussions of the types of tests performed at the facility. These include a wide range of experiments to help resolve key safety issues concerning light water reactors, assess computer models, and confirm adequacy of specific Nuclear Regulatory Commission licensing regulations

No abstract available

[en] Differing opinions concerning the modification of the Power Burst Facility (PBF) at Idaho Falls to turn the facility into a research and cancer treatment center are reported. Energy Secretary James Watkins convened an independent panel to examine once again the merits of converting the PBF, and the committee concluded that there is neither enough information currently available sufficiently encouraging to convert the PBF or to maintain it for this purpose. Idaho legislators have used their influence to include $13 million in the Department of Energy 1991 budget for design studies, limited reactor modifications, and maintenance. After the report of the committee, Secretary Watkins must decide to either ask congress to rescind the $13 million appropriated for 1991 or spend money to close down the reactor in 1992

[en] The treatment of measurement uncertainty at the Power Burst Facility provides a means of improving data integrity as well as meeting standard practice reporting requirements. This is accomplished by performing the uncertainty analysis in two parts, test independent uncertainty analysis and test dependent uncertainty analysis. The test independent uncertainty analysis is performed on instrumentation used repeatedly from one test to the next, and does not have to be repeated for each test except for improved or new types of instruments. A test dependent uncertainty analysis is performed on each test based on the test independent uncertainties modified as required by test specifications, experiment fixture design, and historical performance of instruments on similar tests. The methodology for performing uncertainty analysis based on the National Bureau of Standards method is reviewed with examples applied to nuclear instrumentation

[en] Xe, Kr, and I fission-product release data from (a) Halden tests where release in intact rods was measured during irradiation at burnups to 18,000 MWd/t and fuel temperatures of 800 to 1800⁰K, and (b) Power Burst Facility (PBF) tests where trace-irradiated fuel (approx. = 90 MWd/t) was driven to temperatures of >2400⁰K and fuel liquefaction occurred are discussed and related to fuel morphology. Results from both indicate that the fission-product morphology and fuel restructuring govern release behavior. The Halden tests show low release at beginning of life with a 10-fold increase at burnups in excess of 10,000 MWd/t, due to the development of grain boundary interlinkage at higher burnups. Such dependence of release on morphology characteristics is consistent with findings from the PBF tests, where for trace-irradiated fuel, the absence of interlinkage accounts for the low release rates observed during initial fuel heatup, with subsequent enhanced Xe, Kr, and I release via liquefaction or quench-induced destruction of the grain structure. Morphology is also shown to influence the chemical release form of I and Cs fission products

[en] The 'End Points' methodology provides a systematic way to specify the conditions to be established for permanent shutdown of a contaminated facility. The steps to apply this method are described. The Power Burst Facility (PBF), a small research reactor, is included as an example to provide insights for using the method. (author)

[en] The first PBF-LOCA program nuclear blowdown experiment (LOC-11) consisted of three sequential tests conducted with four separately shrouded PWR 15 x 15 design fuel rods. The first test, LOC-11A, was facility checkout test during which no programmatic information was obtained. The test rod peak power prior to blowdown was 46 kW/m for the LOC-11B test and 68 kW/m for the LOC-11C test. Maximum measured peak surface temperatures were 890 K and 1030 K for LOC-11B and LOC-11C, respectively. RELAP4/MOD6 posttest analysis of LOC-11B and LOC-11C indicated that accurate predictions of measured peak cladding temperatures required the inclusion of the following models: (1) a low flow CHF prediction model to allow for relatively accurate prediction of the time to CHF, (2) an accurate fuel model to represent the initial stored energy, (3) a radiation heat transfer model to represent the radiant exchange of thermal energy between the fuel rod and the shroud

[en] Procedures are outlined for fabricating internally instrumented reactor fuel rods while maintaining the original quality assurance level of the rods. Instrumented fuel rods described contain fuel centerline thermocouples, ultrasonic thermometers, and pressure tubes for internal rod gas pressure measurements. Descriptions of the thermocouples and ultrasonic thermometers are also contained

No abstract available