512-S Facility, Actinide Removal Process Radiological Design Summary Report

Nathan, S.J.

Savannah River Site (S.C.)

关键词: Removal;    Radiation Protection;    Source Terms;    Dose Rates;    Actinides;   

DOI  :  10.2172/823119
RP-ID  :  WSRC-TR-2003-00167
RP-ID  :  AC09-96SR18500
RP-ID  :  823119

美国|英语

来源: UNT Digital Library

【 摘 要 】

This report contains top-level requirements for the various areas of radiological protection for workers. Detailed quotations of the requirements for applicable regulatory documents can be found in the Radiological Design Summary Report Implementation Guide. For the purposes of demonstrating compliance with these requirements, per Engineering Standard 01064, ''shall consider / shall evaluate'' indicates that the designer must examine the requirement for the design and either incorporate or provide a technical justification as to why the requirement is not incorporated. This report describes how the Building 512-S, Actinide Removal Process meets the required radiological design criteria and requirements based on 10CFR835, DOE Order 420.1A, WSRC Manual 5Q and various other DOE guides and handbooks. The analyses supporting this Radiological Design Summary Report initially used a source term of 10.6 Ci/gallon of Cs-137 as the basis for bulk shielding calculations. As the project evolved, the source term was reduced to 1.1 Ci/gallon of Cs-137. This latter source term forms the basis for later dose rate evaluations.