Published January 26, 2001 | Version v1
Report

Analysis in Response to CSER Review Team Report of 06/28/1999

Description

In early 1999, Fluor Daniel Hanford, Inc. contracted with the Pacific Northwest National Laboratory (PNNL) to conduct an assessment of the 300 Area Fuel Supply Shutdown (FSS) Facility and their technical basis for criticality safety (Larson, et al. 1999). Their final report contained a number of issues that have now been addressed. This calculation note contains the results of analyses performed to respond to these issues. The issues addressed in this calculation note are: (1) The effect of interspersed moderation on finite fuel box arrays of different sizes. The PNNL Review Team wanted to see the effect of optimum moderator density shifting to larger values for smaller fuel box arrays. This effect has, in fact, been shown in this calculation note. (2) The hemispherical safe masses were to be recalculated using the more detailed Monte Carlo method. The previous values were obtained from deterministic codes (lattice transport theory for the generation of few-group constants, followed by diffusion theory for the calculation of finite geometry radii)

Availability note (English)

Available from PURL: https://www.osti.gov/servlets/purl/805927-OdCZGu/native/

Additional details

Publishing Information

Imprint Pagination
79 p.
Report number
HNF--7275

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
34016209
Subject category
S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
CRITICALITY; HANFORD RESERVATION; MODERATORS; MONTE CARLO METHOD; NUCLEAR FUELS; SAFETY ANALYSIS
Descriptors DEC
CALCULATION METHODS; ENERGY SOURCES; FUELS; MATERIALS; NATIONAL ORGANIZATIONS; REACTOR MATERIALS; US DOE; US ERDA; US ORGANIZATIONS

Optional Information