Published 1992 | Version v1
Report Metadata-only

Spatial kinetics analysis of the loss of control-rod cooling accident for the Savannah River K-reactor

Creators

  • 1. Los Alamos National Lab., NM (United States)
  • 2. Dept. of Energy, Washington, DC (United States)

Description

A postulated loss of control-rod cooling (LCRC) accident for the Savannah River K-Reactor is analyzed using the advanced neutronics nodal code NEM and the TRAC system thermal-hydraulics model. This analysis demonstrates that there is a significant margin of safety for the LCRC accident at the anticipated restart power level for the K-Reactor. This study also constitutes the first application of a transient three-dimensional nodal neutronics code to an event included in Chapter 15 of the safety analysis report for the K-Reactor

Additional details

Publishing Information

Imprint Title
Proceedings of the 1992 topical meeting on advances in reactor physics. Volume 2
Imprint Pagination
618 p.
Journal Page Range
p. 2.411-2.420.
Report number
CONF-920308--Vol.2

Conference

Title
American Nuclear Society (ANS) topical meeting on advances in reactor physics.
Dates
8-11 Mar 1992.
Place
Charleston, SC (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
23067783
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCURACY; AFTER-HEAT REMOVAL; CONTROL ELEMENTS; D CODES; DELAYED NEUTRONS; FLUXMETERS; HEAT TRANSFER; HYDRAULICS; K REACTOR; LANL; LOSS OF COOLANT; N CODES; NODAL EXPANSION METHOD; POWER DENSITY; REACTIVITY INSERTIONS; REACTOR ACCIDENTS; REACTOR CONTROL SYSTEMS; REACTOR KINETICS; REACTOR SAFETY; REACTOR START-UP; SAVANNAH RIVER PLANT; SCRAM RODS; SPACE DEPENDENCE; STEADY-STATE CONDITIONS; T CODES; THREE-DIMENSIONAL CALCULATIONS; TRANSIENTS
Descriptors DEC
ACCIDENTS; BARYONS; CALCULATION METHODS; COMPUTER CODES; CONTROL SYSTEMS; ELEMENTARY PARTICLES; ENERGY TRANSFER; FERMIONS; FISSION NEUTRONS; HADRONS; HEAVY WATER MODERATED REACTORS; KINETICS; MEASURING INSTRUMENTS; NATIONAL ORGANIZATIONS; NEUTRONS; NUCLEONS; PRODUCTION REACTORS; REACTOR COMPONENTS; REACTORS; REMOVAL; SAFETY; SPECIAL PRODUCTION REACTORS; START-UP; US AEC; US DOE; US ERDA; US ORGANIZATIONS

Optional Information

Contract/Grant/Project number
Contract W-7405-ENG-36