5 Matching Results

Search Results

Advanced search parameters have been applied.

Validation Test Report For The CRWMS Analysis and Logistics Visually Interactive Model Calvin Version 3.0, 10074-Vtr-3.0-00

Description: This report describes the tests performed to validate the CRWMS ''Analysis and Logistics Visually Interactive'' Model (CALVIN) Version 3.0 (V3.0) computer code (STN: 10074-3.0-00). To validate the code, a series of test cases was developed in the CALVIN V3.0 Validation Test Plan (CRWMS M&O 1999a) that exercises the principal calculation models and options of CALVIN V3.0. Twenty-five test cases were developed: 18 logistics test cases and 7 cost test cases. These cases test the features of CALVIN in a sequential manner, so that the validation of each test case is used to demonstrate the accuracy of the input to subsequent calculations. Where necessary, the test cases utilize reduced-size data tables to make the hand calculations used to verify the results more tractable, while still adequately testing the code's capabilities. Acceptance criteria, were established for the logistics and cost test cases in the Validation Test Plan (CRWMS M&O 1999a). The Logistics test cases were developed to test the following CALVIN calculation models: Spent nuclear fuel (SNF) and reactivity calculations; Options for altering reactor life; Adjustment of commercial SNF (CSNF) acceptance rates for fiscal year calculations and mid-year acceptance start; Fuel selection, transportation cask loading, and shipping to the Monitored Geologic Repository (MGR); Transportation cask shipping to and storage at an Interim Storage Facility (ISF); Reactor pool allocation options; and Disposal options at the MGR. Two types of cost test cases were developed: cases to validate the detailed transportation costs, and cases to validate the costs associated with the Civilian Radioactive Waste Management System (CRWMS) Management and Operating Contractor (M&O) and Regional Servicing Contractors (RSCs). For each test case, values calculated using Microsoft Excel 97 worksheets were compared to CALVIN V3.0 scenarios with the same input data and assumptions. All of the test case results compare with the CALVIN V3.0 results within ...
Date: July 27, 2000
Creator: Gillespie, S.
Partner: UNT Libraries Government Documents Department

Operational Waste Stream Assumption for TSLCC Estimates

Description: This document provides the background and basis for the operational waste stream used in the 2000 Total System Life Cycle Cost (TSLCC) estimate for the Civilian Radioactive Waste Management System (CRWMS). This document has been developed in accordance with its Development Plan (CRWMS M&O 2000a), and AP-3.11Q, ''Technical Reports''.
Date: September 1, 2000
Creator: Gillespie, S.
Partner: UNT Libraries Government Documents Department

MODULAR CONSTRUCTION SYSTEM EVALUATION

Description: The purpose of this study is to respond to U.S. Department of Energy (DOE) Technical Direction Letter (TDL) 02-003 (Waisley 2001), which directs Bechtel SAIC Company, LLC (BSC) to complete a design study to recommend repository design options to support receipt and/or emplacement of any or all of the following: commercial spent nuclear fuel (CSNF), high-level radioactive waste (HLW), DOE-managed spent nuclear fuel (DSNF) (including naval spent nuclear fuel [SNF]), and immobilized plutonium (if available), as soon as practicable, but no later than 2010. From the possible design options, a recommended approach will be determined for further evaluation to support the preliminary design of the repository. This study integrates the results of the repository Design Evolution Study (Rowe 2002) with supporting studies concerning national transportation options (BSC 2002b) and Nevada transportation options (Gehner 2002). The repository Design Evolution Study documents the processes used to reevaluate the design, construction, operation, and cost of the repository in response to TDL 02-003 (Waisley 2001), and to determine possible repository conceptual design options. The transportation studies evaluate the national and Nevada transportation options that support the repository conceptual design options. An evaluation methodology was established, based on Program-level requirements developed for the study in reference BSC 2001a, to allow the repository and system design options to be evaluated on a consistent basis. The transportation options and the design components were integrated into system design implementation options, which were evaluated using receipt and emplacement scenarios. The scenarios tested the ability of the design concept to adapt to changes in funding, waste receipt rate, and Nevada rail transportation availability. The results of the evaluation (in terms of system throughput, cost, and schedule) were then compared to the Program-level requirements, and recommendations for design alternatives, requirements changes, or further evaluation were developed.
Date: August 8, 2002
Creator: Gillespie, S.
Partner: UNT Libraries Government Documents Department

Radiation analysis for a generic centralized interim storage facility

Description: This paper documents the radiation analysis performed for the storage area of a generic Centralized Interim Storage Facility (CISF) for commercial spent nuclear fuel (SNF). The purpose of the analysis is to establish the CISF Protected Area and Restricted Area boundaries by modeling a representative SNF storage array, calculating the radiation dose at selected locations outside the storage area, and comparing the results with regulatory radiation dose limits. The particular challenge for this analysis is to adequately model a large (6000 cask) storage array with a reasonable amount of analysis time and effort. Previous analyses of SNF storage systems for Independent Spent Fuel Storage Installations at nuclear plant sites (for example in References 5.1 and 5.2) had only considered small arrays of storage casks. For such analyses, the dose contribution from each storage cask can be modeled individually. Since the large number of casks in the CISF storage array make such an approach unrealistic, a simplified model is required.
Date: December 31, 1997
Creator: Gillespie, S. G.; Lopez, P. & Eble, R. G.
Partner: UNT Libraries Government Documents Department

Radiation analysis for a generic centralized interim storage facility

Description: This paper documents the radiation analysis performed for the storage area of a generic Centralized Interim Storage Facility (CISF) for commercial spent nuclear fuel (SNF) to establish the CISF Protected Area, Unrestricted Area, and Restricted Area boundaries. In order to model a large (6000 cask) storage array with a reasonable amount of analysis time and effort, a simplified calculational model was developed for the CISF. The CISF is designed to accommodate several different types of SNF storage systems. In order to simplify the calculation of dose rates from the storage area, the Westinghouse Large PWR Multi-Purpose Canister (MPC) is selected as a representative storage system, since sufficient information is contained in its Safety Analysis Report to allow accurate modeling, and the surface dose rates on the MPC are consistent with other storage systems.
Date: July 1, 1997
Creator: Gillespie, S. G.; Lopez, P. & Eble, R. G.
Partner: UNT Libraries Government Documents Department