Accumulation and head-loss characteristics of selected pressurized water reactor loca-generated debris

Nuclear Technology

Volumn 154, Issue 1, 2006, Pages 69-84

  Ghosh, Ashok K ^a   Maji, Arup K ^b   Leonard, Mark T ^c   Rao, Dasari V ^d   Letellier, Bruce C ^d   Urgessa, Girum S ^b   Ashbaugh, Scott G ^e  

^a NEW MEXICO INSTITUTE OF MINING AND TECHNOLOGY   (United States)

^b UNIVERSITY OF NEW MEXICO   (United States)

^c Dycoda   (United States)

^d LOS ALAMOS NATIONAL LABORATORY   (United States)

^e SANDIA NATIONAL LABORATORIES   (United States)

Author keywords

Accumulation; Calcium silicate; Head loss

Indexed keywords

CALCIUM COMPOUNDS; COMPUTATIONAL FLUID DYNAMICS; COMPUTER SIMULATION; FLOW CONTROL; LOSS OF COOLANT ACCIDENTS; THERMAL INSULATION; WATER PIPING SYSTEMS;

CALCIUM SILICATE; CLOSED-LOOP IMPINGEMENT; HEAD LOSS; LOCA-GENERATED DEBRIS;

PRESSURIZED WATER REACTORS;

EID: 33645916430     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT06-A3718     Document Type: Article

References (10)

1. "Potential for Degradation of the ECCS and the Containment Spray System after a LOCA because of Construction and Protective Coating Deficiencies and Foreign Material in Containment," Generic Letter 98-04, U.S. Nuclear Regulatory Commission (July 1998).
2. D. V. RAO, C. SHAFFER, B. CARPENTER, D. CREMER, J. BRIDEAU, G. HECKER, M. PADMANABHAM, and P. STACEY, "Drywell Debris Transport Study: Experimental Work," NUREG/CR-6369, U.S. Nuclear Regulatory Commission (Sep. 1999); see also V2 (SEA 97-3105-A:15), Science and Engineering Associates, Inc.
3. A. K. MAJI, D. V. RAO, B. LETELLIER, L. BARTLEIN, and B. MARSHALL, "Transport Characteristics of Selected Pressurized Water Reactor LOCA-Generated Debris," Nucl. Technol., 139, 145 (2002).
4. G. ZIGLER, J. BRIDEAU, D. V. RAO, C. SHAFFER, F. SOUTO, and W. THOMAS, "Parametric Study of the Potential for BWR ECCS Strainer Blockage Due to LOCA Generated Debris," NUREG/CR-6224, U.S. Nuclear Regulatory Commission (Jan. 1994); see also SEA No. 93-554-05-A: 1, Science and Engineers Associates, Inc.
5. D. V. RAO, B. C. LETELLIER, C. SHAFFER, S. ASHBAUGH, and L. S. BARTLEIN, "GSI- 191: Technical Assessment: Parametric Evaluations for Pressurized Water Reactor Recirculation Sump Performance," NUREG/ CR-6762, U.S. Nuclear Regulatory Commission; see also LA-UR-01-4083, (4 vols.), Los Alamos National Laboratory (Aug. 2002).
6. D. V. RAO, B. C. LETELLIER, A. K. MAJI, and B. MARSHALL, "GSI-191: Separate-Effects Characterization of Debris Transport in Water," NUREG/CR-6772, U.S. Nuclear Regulatory Commission; see also LA-UR-01-6882, Los Alamos National Laboratory (Aug. 2002).
7. D. V. RAO, C. SHAFFER, M. T. LEONARD, and K. W. ROSS, "Knowledge Base for the Effect of Debris on Pressurized Water Reactor Emergency Core Cooling Sump Performance," NUREG/CR-6808, U.S. Nuclear Regulatory Commission; see also LA-UR-03-0880, Los Alamos National Laboratory (Feb. 2003).
8. B. N. DOMINIQUE, "Transport and Head Loss Tests of Owens-Corning Nukon™ Fiberglas Insulation," Alden Research Laboratory, Worcester Polytechnic Institute (Sep. 1983).
9. D. V. RAO and F. J. SOUTO, "Experimental Study of Head Loss and Filtration for LOCA Debris," NUREG/CR-6367, U.S. Nuclear Regulatory Commission (1996).
10. C. SHAFFER, W. BERNAHL, J. BRIDEAU, and D. V. RAO, "BLOCKAGE 2.5 Reference Manual," NUREG/CR6371, U.S. Nuclear Regulatory Commission; see also SEA963104-A:4, Science and Engineering Associates, Inc. (Dec. 1996).