Pigford, T.H. 1990. Department of Nuclear Engineering University of California Berkeley. Letter to Archie L. Wood. National Research Council. November 19, 1990. Transmitting copy of paper entitled “Actinide Burning and Waste Disposal”. An Invited Review for the MIT International Conference on the Next Generation of Nuclear Power Technology. UCB-NE-4176. October 5, 1990.

Taylor, J. J. and K.E. Stahlkopf. 1988. (no title). Nuclear Engineering Design. 109:19(September-October).

Taylor, J. J. 1989. Improved and Safer Nuclear Power. Science. 244:318-325. April 21, 1989.

Till, C.E. 1989. The Liquid Metal Reactor. Overview of the Integral Fast Reactor Rationale and Basis for Its Development. Presentation to National Academy of Sciences Committee on Future Nuclear Power Development. Argonne National Laboratory. August 21-25, 1989.

Westinghouse Electric Corporation. 1989. Assessing the Merits of AP600 Advanced Reactor Technology for U.S. Electric Power Needs. Report to the Committee on Future U.S. Nuclear Power Development. (Energy Systems Business Unit, AP600 Program Office). August.

Williams, P.M., T.L. King, and J.N. Wilson. 1989. Draft Preapplication Safety Evaluation Report for the Modular High-Temperature Gas-Cooled Reactor. NUREG-1338. Division of Regulatory Applications. U.S. Nuclear Regulatory Commission. Washington, D.C. 20555. March.

Wolfe, B. and D.R. Wilkens. 1988. Improvements in Boiling Water Reactor Designs and Safety. Presented at the American Nuclear Society Topical Meeting. Seattle, WA. May 1-5, 1988.

Young, W. H., Assistant Secretary for Nuclear Energy, DOE. 1989. Letter to Eric Beckjord. Director. Office of Nuclear Regulatory Research. U.S. Nuclear Regulatory Commission. November 28, 1989. Enclosure entitled Summary - Containment Study for Modular High Temperature Gas-Cooled Reactor (MHTGR).

Young, W. H. Assistant Secretary for Nuclear Energy, DOE. Undated. Letter to Professor Thomas H. Pigford. (Letter was undated, but received by the Committee on March 5, 1991).

Front Matter (R1-R18)

Summary (1-14)

1 Introduction (15-18)

2 The Institutional Framework (19-90)

3 Assessment of Advanced Nuclear Reactor Technologies (91-160)

4 Federal Research and Development Alternatives (161-179)

5 Conclusions and Recommendations (180-198)

Individual Views of Committee Members (199-202)

Appendix A Committee Meetings (203-208)

Appendix B Criteria Developed for the Comparative Analysis of Advanced Reactor Technologies (209-213)

List of Acronyms (214-216)