Nuclear reactor safety. Quarterly progress report October 1--December 31, 1978. [BWR; PWR; HTGR; LMFBR; GCFR]

Technical Report · Thu Mar 01 04:00:00 EST 1979

OSTI ID:6016057

Jackson, J F; Stevenson, M G ^[1]

---

1. comps.

The LWR safety computer code, TRAC-P1A, was completed during the quarter. A very coarse-node LOCA calculation was performed on a U.S. PWR model using TRAC. The results agreed surprisingly well with the initial phases of an earlier fine-node calculation. A series of TRAC calculations were performed to determine the influence of several operational parameters on the transient behavior of the proposed Japanese Slab Core Test Facility. Preliminary calculations for the Japanese Cylindrical Core Test Facility were also performed. A posttest calculation of LOFT Test L1-5 was completed, as well as a pretest prediction of the first LOFT nuclear test, L2-2. A numerical study of scale effects on ECC bypass was performed with the K-TIF code. A new momentum exchange formulation was implemented into K-TIF that accurately predicts the results from several CREARE bypass experiments. The SOLA-SPRAY code for analyzing dispersed droplet flow was improved by including compressibility and phase change effects. A seismic response capability was added to the SOLA-FLX code. SIMMER LMFBR disrupted core analysis code development and applications work includes improvements in the analytic equation-of-state and in the pressure and component density solution iteration technique. SIMMER testing and verification work reported includes analyses of UKAEA COVA and SRI International bubble expansion experiments and of Sandia (PBE-SG2) and ANL (AX-1) in-pile experiments investigating carbide fuel behavior under rapid transient conditions. In the HTGR safety researchwork, the last in a series of one-dimensional core block system model seismic response test were completed. Work continued in the design, fabrication, and analysis of the GCFR core disruptive test program. Postmortem analysis of the FLS 1 test indicated that 18 of the 34 rods failed.

• Research Organization: Los Alamos Scientific Lab., NM (USA)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 6016057
• Report Number(s): NUREG/CR-0762; LA-7769-PR
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
BWR TYPE REACTORS
COATED FUEL PARTICLES
COMPUTER CODES
CONTAINERS
CONTAINMENT
CONTAINMENT SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCT RELEASE
FLUID MECHANICS
FUEL PARTICLES
GAS COOLED REACTORS
GCFR TYPE REACTORS
GRAPHITE MODERATED REACTORS
HEAT TRANSFER
HTGR TYPE REACTORS
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PRESSURE VESSELS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
RESEARCH PROGRAMS
S CODES
SAFETY
SEISMIC EFFECTS
STRESS ANALYSIS
T CODES
TEST FACILITIES
TRANSIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS