Quantcast Methodology - s3007cn10078

 

Click here to make tpub.com your Home Page

Page Title: Methodology
Back | Up | Next

Click here for thousands of PDF manuals

Google


Web
www.tpub.com

Home

   
Information Categories
.... Administration
Advancement
Aerographer
Automotive
Aviation
Construction
Diving
Draftsman
Engineering
Electronics
Food and Cooking
Logistics
Math
Medical
Music
Nuclear Fundamentals
Photography
Religion
   
   

 

Share on Google+Share on FacebookShare on LinkedInShare on TwitterShare on DiggShare on Stumble Upon
Back
Requirements Documentation - s3007cn10077
Up
Guidelines For Preparing Criticality Safety Evaluations at Department of Energy Non-Reactor Nuclear Facilities
Next
Table 1. Results of ANISN benchmark calculations with Hansen-Roach 16-energy-group cross section data


DOE-STD-3007-93
This analysis is designated as Quality Level A (according to the EG&G Idaho Quality
Manual) and is intended to comply with NQA-1. As required by the Nuclear Engineering
Standard Practice, NE-SP-24, any operational limits or procedures that result from or are based
on information contained in this report must be reviewed by Reactor and Radiation Physics
personnel to ensure that the technical information given in this Criticality Safety Evaluation has
been properly incorporated into the limits or procedures.
[Note: Many of the requirements discussed in this evaluation are site specific and company
specific].
All calculations were performed with the one-dimensional Sn (n = 8) discrete-ordinates
transport theory code, ANISN5. Sixteen-energy-group Hansen-Roach6 cross section data were
used as input to the ANISN code. The calculations were performed on an IBM PS/2 Model 60
with a version of the ANISN code that was developed at the INEL, ANISN/PC.
Six thermal reactor benchmarks, PNL-1 through PNL-5 and PNL-7, were evaluated with
the ANISN code and the 16-energy-group Hansen-Roach data set. These experiments are
documented in Reference 7. PNL-1 through PNL-5 are experiments with unreflected spheres of
plutonium nitrate solutions with H/Pu-239 ratios ranging from 131 to 1204. PNL-7 is an
experiment with a water reflected (30-cm-thick) stainless steel sphere of plutonium nitrate with an
H/Pu ratio of 980. These PNL experiments provide adequate validation of the methods and cross
sections used to derive the limits established in this report for the following reasons:
1.
The geometric configurations of the fuel regions are spherical in both the
benchmark experiments and in this analysis.
2.
Both the benchmark experiments and the systems evaluated are hydrogen
moderated. The benchmarks are moderated with nitrate solution. A polyethylene
(60 vol.%) - water (40 vol.%) composition was assumed for this analysis.
4-9


Privacy Statement - Press Release - Copyright Information. - Contact Us

Integrated Publishing, Inc.