Resurrecting the MSRE

We will build a new 200 MW denatured molten salt research reactor with three validation test intermediate loops.  Dr. Ralph Moir and Dick Engel have urged us to access the myriad vellum engineering illustrations generated in support of the original MSRE as a primary resource to follow in our building of the first 200 MW DMSR.  Quite recently, however, an ORNL executive has undertaken a review of the design origins of the MSRE in response to our inquiries.  While a number of engineering drawings have been located both in the MSRE building and elsewhere within ORNL, the consensus has come back to access a different, and more thorough resource.  A series of documents that went into great detail in describing the decisions and their background on the design and operation of the Molten-Salt Reactor Experiment.

1ORNL-2796_1960 MSR Design Study

These documents were published under the collective title of “MSRE Design and Operations Report”.  They represent an invaluable repository that we present here to  instruct the ‘learning curve’ we negotiate as we build a new, operational molten salt reactor.

“MSRE Design and Operations Report,” Part I, Description of Reactor Design, by R. C. Robertson, 575 pages

1ORNL-TM-0728

“MSRE Design and Operations Report,” Part IIA, Nuclear and Process Instrumentation, by J. R. Tallackson, 405 pages

1ORNL-TM-0729A

MSRE Design and Operations Report,” Part IIB, Nuclear and Process Instrumentation, by J. R. Tallackson, 505 pages

1ORNL-TM-0729B

“MSRE Design and Operations Report,” Part III, Nuclear Analysis, By P. N. Baubenreich, J. R. Engel, B. E. Prince, and H. C. Claiborne, 209 pages

1ORNL-TM-0730

“MSRE Design and Operations Report,” Part IV, Chemistry and Materials, by F. F. Blankenship and A. Taboada

To Be Located  [ORNL indicates this Part IV report was never issued]

“Chemical Aspects of MSRE,” by Roy E. Thoma, 151 pages

1MSRE Chemical Aspects_ORNL-4658

“MSRE Design and Operations Report,” Part V, Reactor Safety Analysis Report, By S. E. Beall, F. N. Baubenreich, R. B. Lindauer, and J. H. Tallackson, 314 pages

1ORNL-TM-0732

“MSRE Design and Operations Report,” Part V-A, Safety Analysis of Operations with 233-U, by P. N. Haubenreich, J. R. Engel, C. H. Gabbard, R. H. Geymon, and B. E. Prince, 90 pages

1ORNL-TM-732A

“MSRE Design and Operations Report,” Part VI, Operating Limits, by S. E. Beall and R H. Guymon, 9 pages

1ORNL-TM-0733

“MSRE Design and Operations Report,” Part VI REVISED, Operating Limits, by S. E. Beall and R H. Guymon, 9 pages

1ORNL-TM-0733REV

“MSRE Design and Operations Report,” Part VI – Second Revision, Operating Limits, by S. E. Beall and R H. Guymon, 9 pages

1ORNL-TM-0733REV2

“MSRE Design and Operations Report,” Part VI – Third Revision, Operating Limits, by P.N. Haubenreich and R H. Guymon, 11 pages

1ORNL-TM-0733REV3

“MSRE Design and Operations Report,” Part VII, Fuel Handling and Processing Plant, by R. B. Lindauer, 108 pages

1ORNL-TM-0907

“MSRE DEsign and Operations Report,” Part VII- Revised, Fuel Handling and Processing Plant, by R. B. Lindauer, 71 pages

1ORNL-TM-0907REV

“MSRE Design and Operations Report,” Part VIII – A, Operating Procedures, by R. H. Guymon,

To Be Located [ORNL-TM-908A]

“MSRE Design and Operations Report,” Part VIII – B, Operating Procedures, by R. H Guymon,

MSRE-Design-Ops-Rpt_ORNL-TM-908-Vol-II  Download

“MSRE Operator Training and Operating Techniques”, by R .H. Guymon, 149 Pages

1ORNL-TM-3041 MSR Operating Procedures

“MSRE Design and Operations Report,” Part IX, Safety Procedures and Emergency Plans, by R. H. Guymon, 58 pages

1ORNL-TM-0909

“MSRE Design and Operations Report,” Part X, Maintenance Equipment and Procedures, by E. C. Hise and R. Blumberg, 95 pages

1ORNL-TM-0910

“MSRE Design and Operations Report,” Part XI, Test Program, J. R. Engel, 100 pages

1ORNL-TM-0911

“MSRE Design and Operations Report,” Part XI-A, Test Program for 233-U Operation, J. R. Engel, 26 pages

1ORNL-TM-2304

“Critique of the Molten-Salt Reactor Experiment:  A Collection of Comments Submitted by Persons Associated with the Reactor,” R. H. Guymon, 89 pages

1CF-70-9-3_Afteraction Critique of MSRE