Published June 23, 2004 | Version v1
Report

Preliminary optimization study for NGNP fuel block design

Description

An advanced gas reactor fuels development and qualification program is being undertaken by the USDOE to address the need for data in support of the licensing operation of the Next Generation Nuclear Power Plant (NGNP). Reactor physics tasks have been defined and are being conducted to support this program. As part of this effort, a preliminary assessment of deterministic lattice codes (WIMS8 and DRAGON) was performed. It was found that the results from these deterministic codes generally agree well with the reference Monte Carlo results. Based on these results, parametric studies were performed with the WIMS8 code to develop an optimum design of the NGNP fuel block. The design goal is to discharge burnup greater than 100 GWd/t and a cycle length of about 18 to 24 months are targeted. As a first step, the effects of fuel kernel size, particle packing fraction, and uranium enrichment have been investigated, while using the NGNP reference design values for the other design parameters such as the fuel compact size and coating thicknesses

Availability note (English)

Available from Trans. Am. Nucl. Soc. 91: 547-48 2004

Additional details

Publishing Information

Imprint Pagination
[vp.]
Report number
ANL/NE/CP--113711

Conference

Title
ANS Winter Meeting and Nuclear Technology Expo
Dates
14-18 Nov 2004
Place
Washington, DC (United States)

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
36095122
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTER CODES; DESIGN; NUCLEAR FUELS; OPTIMIZATION; US DOE
Descriptors DEC
ENERGY SOURCES; FUELS; MATERIALS; NATIONAL ORGANIZATIONS; REACTOR MATERIALS; US ORGANIZATIONS

Optional Information

Contract/Grant/Project number
W--31-109-ENG-38
Funding organization
US Department of Energy (United States)