Document: NUREG-0800
Document ID: 0c942a2c-afa6-4bbd-8f3f-4eede9dc146e
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350048.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
esign code; G3, a general purpose gamma ray scattering program; various versions of QAD and MORSE, a general purpose Monte Carlo multigroup neutron and gamma ray transport code, etc. SDC can calculate gamma ray shielding requirements, handling 12 source geometries (including point, line, disk, plane, slab, and sphere) and with cross sections and material compositions for 17 materials. As many as 12 gamma energy groups, covering the range from 0.1 to 10 MeV, may be used to describe the gamma spectrum. The staff may use these codes, as necessary, to calculate dose rates for given shield designs and source strengths, as a confirmation of the applicant's method. The applicant's shielding design is acceptable if the methods are comparable to commonly acceptable shielding calculations and if assumptions regarding source terms, cross sections, shield and source geometries, and transport methods are realistic. Acceptable shielding codes include but are not limited to ANISN, QAD, DOT, MORSE, SAM-CE, 05R, 06R, G3, SDC, and many others. This listing does not imply that all these codes are equivalent, since some are much more sophisticated -than others. The staff believes it is advantageous to use a good calculational procedure, since an effective shield design is essential to meeting the criteria that occupational radiation exposures will be as low as is reasonably achievable. Two documents provide additional guidance for acceptability of the shielding design. One is "Reactor Shielding for Nuclear Engineers," edited by N. M. Schaeffer, published by AEC-OIS, 1973." The second is the Stone & Webster Engineering Corporation topical report RP-8 entitled "Radiation Shielding Design and Analysis Approach for Light Water Reactor Power Plants;" These documents provide useful guidance regarding radiation shielding design. Some 12.3-8 Rev. 2 - July 1981 limitations are noted for RP-8, in that the labyrinth entrance ways may not provide dose rates at the outside entrance consistent with