Argonne National Laboratory Report ANL-6847

Report concerning the study of the two-phase flow through the cooling channels of a natural-circulation boiling water nuclear reactor. "One-dimensional conservation equations describing the flow through each channel are written in the linearized perturbed form, and Laplace transformation in time is performed." (p. 5

Argonne National Laboratory Reports

From Introduction: "This report will present and discuss the results of a preliminary investigation for a facility which could be utilized to test nuclear rocket fuel elements at operating conditions.

Reactor physics division annual report /

Description based on ANL-7110: "AEC Research and Development Report" -t.p.Description based on ANL-7110: "Reactor Technology (TID-4500)" -t.p.Description based on ANL-7110: "ANL-7110" -t.p.Description based on ANL-7110: "July 1, 1964 to June 30, 1965" -t.p.Operated by The University of ChicagoMode of access: Internet

Argonne National Laboratory Reports

Report by the Argonne National Laboratory evaluating the Argonne Fast Critical Facility, ZPR-VI, under construction during the course of the study. The study addresses various functionalities and safety features of the facility

Use of depleted uranium in thermal reactors with slightly enriched fuel, to achieve high neutron economy and high burnup /

"Reactor Technology ; (TID-4500, 29th Ed.) ; AEC Research and Development and Report" -t.p.Includes bibliography references : p. 21.Operated by The University of ChicagoMode of access: Internet

Study of reflector-based control of fast nuclear rocket reactors /

"Based on a thesis submitted to Northwestern University as partial fulfillment of the requirements for a Master of Science Degree""Reactor Physics Division""AEC Research and Development Report""(TID-4500)""Propulsion Systems and Energy Conversion"Bibliography: p. 81-82.Operated by The University of ChicagoMode of access: Internet

Flux trap experiments in D₂O-moderated thoria-urania cores /

"Reactor Physics Division""AEC Research and Development Report""(TID-4500, 37th Ed.)""Reactor Technology"Bibliography: p. 33.Operated by The University of ChicagoMode of access: Internet

A new technique for experimental investigation of high-temperature thermal diffusivity of uranium dioxide under transient conditions /

"Reproduced in part from a thesis submitted to the Graduate Faculty of Iowa State University, Ames, Iowa in partial fulfillment of the requirements for the Degree of Master of Science. Major Subject: Nuclear Engineering.""Reactor Physics Division""AEC Research and Development Report""(TID-4500)""Metals, Ceramics, and Materials"Bibliography: p. 44-45.Operated by The University of ChicagoMode of access: Internet

Safety analysis of a nominal 3700-liter UO2 core in the ZPR-6 and -9 facility /

This report presents the results of a safety analysis performed for a nominal 3700-liter uranium dioxide core. (Oxygen will be introduced into the core in the form of depleted U3O8 plates. The number of uranium plates and U3O8 plates will be apportioned so as to simulate uranium dioxide.)"July 1968."Includes bibliographical references (p. 10).This report presents the results of a safety analysis performed for a nominal 3700-liter uranium dioxide core. (Oxygen will be introduced into the core in the form of depleted U3O8 plates. The number of uranium plates and U3O8 plates will be apportioned so as to simulate uranium dioxide.)Operated by the University of ChicagoMode of access: Internet

Weather modification /

"Reactor Engineering and Physics Divisions""AEC Research and Development Report""(TID-4500, 16th Ed., Amended)""Physics"Includes bibliographic references.Operated by The University of ChicagoMode of access: Internet