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Title: Porflow modeling supporting the FY14 salstone special analysis

PORFLOW related analyses supporting the Saltstone FY14 Special Analysis (SA) described herein are based on prior modeling supporting the Saltstone FY13 SA. Notable changes to the previous round of simulations include: a) consideration of Saltstone Disposal Unit (SDU) design type 6 under “Nominal” and “Margin” conditions, b) omission of the clean cap fill from the nominal SDU 2 and 6 modeling cases as a reasonable approximation of greater waste grout fill heights, c) minor updates to the cementitious materials degradation analysis, d) use of updated I-129 sorption coefficient (Kd) values in soils, e) assignment of the pH/Eh environment of saltstone to the underlying floor concrete, considering down flow through an SDU, and f) implementation of an improved sub-model for Tc release in an oxidizing environment. These new model developments are discussed and followed by a cursory presentation of simulation results. The new Tc release sub-model produced significantly improved (smoother) flux results compared to the FY13 SA. Further discussion of PORFLOW model setup and simulation results will be presented in the FY14 SA, including dose results.
Authors:
 [1] ;  [1]
  1. Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)
Publication Date:
OSTI Identifier:
1174128
Report Number(s):
SRNL-STI--2014-00083
DOE Contract Number:
AC09-08SR22470
Resource Type:
Technical Report
Research Org:
Savannah River Site (SRS), Aiken, SC (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES