Feasibility of Isotopic Measurements: Graphite Isotopic Ratio Method

Wood, Thomas W. ; Gerlach, David C. ; Reid, Bruce D. ; Morgan, W. C.

Pacific Northwest National Laboratory (U.S.)

关键词: C Reactor;    Isotope Ratio;    Graphite Moderated Reactors;    Data;    G-2 Reactor;   

DOI  :  10.2172/967937
RP-ID  :  PNNL-13488
RP-ID  :  AC05-76RL01830
RP-ID  :  967937

美国|英语

来源: UNT Digital Library

【 摘 要 】

This report addresses the feasibility of the laboratory measurements of isotopic ratios for selected trace constituents in irradiated nuclear-grade graphite, based on the results of a proof-of-principal experiment completed at Pacific Northwest National Laboratory (PNNL) in 1994. The estimation of graphite fluence through measurement of isotopic ratio changes in the impurity elements in the nuclear-grade graphite is referred to as the Graphite Isotope Ratio Method (GIRM). Combined with reactor core and fuel information, GIRM measurements can be employed to estimate cumulative materials production in graphite moderated reactors. This report documents the laboratory procedures and results from the initial measurements of irradiated graphite samples. The irradiated graphite samples were obtained from the C Reactor (one of several production reactors at Hanford) and from the French G-2 Reactor located at Marcoule. Analysis of the irradiated graphite samples indicated that replicable measurements of isotope ratios could be obtained from the fluence sensitive elements of Ti, Ca, Sr, and Ba. While these impurity elements are present in the nuclear-grade graphite in very low concentrations, measurement precision was typically on the order of a few tenths of a percent to just over 1 percent. Replicability of the measurements was also very good with measured values differing by less than 0.5 percent. The overall results of this initial proof-of-principal experiment are sufficiently encouraging that a demonstration of GIRM on a reactor scale basis is planned for FY-95.