Reactor safety issues resolved by the 2D/3D Program. International Agreement Report

Technical Report · Thu Jul 01 04:00:00 EDT 1993

DOI:https://doi.org/10.2172/10177080· OSTI ID:10177080

Damerell, P S; Simons, J W ^[1]

---

1. eds.; MPR Associates, Inc., Washington, DC (United States)

The 2D/3D Program studied multidimensional thermal-hydraulics in a PWR core and primary system during the end-of-blowdown and post-blowdown phases of a large-break LOCA (LBLOCA), and during selected small-break LOCA (SBLOCA) transients. The program included tests at the Cylindrical Core Test Facility (CCTF), the Slab Core Test Facility (SCTF), and the Upper Plenum Test Facility (UPTF), and computer analyses using TRAC. Tests at CCTF investigated core thermal-hydraulics and overall system behavior while tests at SCTF concentrated on multidimensional core thermal-hydraulics. The UPTF tests investigated two-phase flow behavior in the downcomer, upper plenum, tie plate region, and primary loops. TRAC analyses evaluated thermal-hydraulic behavior throughout the primary system in tests as well as in PWRs. This report summarizes the test and analysis results in each of the main areas where improved information was obtained in the 2D/3D Program. The discussion is organized in terms of the reactor safety issues investigated.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States); Japan Atomic Energy Research Inst., Tokyo (Japan); Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Koeln (Gemany); Siemens AG Unternehmensbereich KWU, Erlangen (Germany); Los Alamos National Lab., NM (United States); MPR Associates, Inc., Washington, DC (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 10177080
• Report Number(s): NUREG/IA--0127; GRS--101; MPR--1346; ON: TI93018782
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
COORDINATED RESEARCH PROGRAMS
DEPRESSURIZATION
ECCS
HEAT TRANSFER
HYDRAULICS
INTERNATIONAL AGREEMENTS
JAPAN
LOSS OF COOLANT
MATHEMATICS AND COMPUTERS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
REACTOR SAFETY
STEAM
T CODES
TEST FACILITIES
TESTING
TWO-PHASE FLOW