L.B. Collard, 2000. Subsidence Sensitivity Study for Low-Level Waste in Slit Trenches; WSRC-RP-2000-00524, Rev. 0 (Aug.), Westinghouse Savannah River Company, Savannah River Site, Aiken, SC 29808.

Marek Zaluski, 2000. Modeling of Unsaturated Flow in Soil Solidified with Colloidal Silica. Advanced Simulation Technologies, Conference, Washington, D.C., April 16-20; Proc. Business and Industry Simulation Symposium, The Society for Computer Simulation International, ISBN: 1-5655-199-0.

Ron Collings and Jim Huddleston, 2000. Methane Emission Modeling And Gob Well Performance Forecasting For A Coal Mine In Carbon County, Utah. Raven Ridge Resources, Inc. Grand Junction, CO

L.M. McDowell-Boyer, A.D. Yu, J.R. Cook, D.C. Kocher, E.L. Wilhite, H. Holmes-Burnes, and K.E. Young, 2000. Radiological Performance Assessment for the E-Area Low-Level Waste Facility, WSRC-RP-94-218, Rev. 1 (January), Westinghouse Savannah River Company, Savannah River Site, Aiken, SC 29808.

Marek Zaluski, 2000. Impact of Colloidal-Silica Solidification on Unsaturated Flow Regime, the Modeling Study. Fifth International Symposium and Exhibition on Environmental Contamination in Central and Eastern Europe, 12-14 September, Prague, Czech Republic.

L.B. Collard, 2000. Special Analysis for Disposal of High-Concentration I-129 Waste in the Low-Activity Waste Vaults at the E-Area Low-Level Waste Facility,WSRC-RP-2000-00138, Rev. 0 (February), Westinghouse Savannah River Company, Savannah River Site, Aiken, SC 29808.

L.B. Collard, 2000. Special Analysis for Disposal of High-Concentration I-129 Waste in the Intermediate-Level Vaults at the E-Area Low-Level Waste Facility, WSRC-RP-01070, Rev. 1 (July), Westinghouse Savannah River Company, Savannah River Site, Aiken, SC 29808.

Ron Collings and Jim Marshall, 2000. Methane Recovery For Power Generation From Abandoned Coal Mines In The United Kingdom for Alkane Energy Ltd. Raven Ridge Resources, Inc. Grand Junction, CO

L.B. Collard, 2000. Fate and Transport in the Subsurface of Radioactive Waste, Advanced Simulation Technologies Conference (April), The Society for Computer Simulation International, Washington, D.C.

Ron Collings, Mike Cote and Jim Huddleston, 2000. Several Ongoing Studies Using PORFLOW For Atmospheric Methane Emissions Reduction And Utilization Of Captured Methane For The US EPA's Coalbed Methane Outreach Program. Raven Ridge Resources, Inc. Grand Junction, CO

Ron Collings & Mike Cote, 2000. A Study To Determine The Probable Range Of Methane Emissions To Be Encountered In A Planned Underground Coal Mine In New Mexico. Raven Ridge Resources, Inc Grand Junction, CO

NETEC/ KAERI, 2000. A Conceptual Report Of LLW & ILW Near-Surface Disposal Facility. Korean Electric Power Company, Report 2000-1300-9, Korea

J.W. Park, K.M. Chang, C.L.Kim and E.U.Lee, 2000. Groundwater Flow Modelling For Near Field Of A Hypothetical Near-Surface Disposal Facility. Proc. of Korean Nuclear Society

J.M. McCarthy, R.S. Garcia, R.L. Nitschke and C-L. Kim, 1999. Final Report: Performance Assessment Codes for Shallow Land Disposal and Transportation of Low Level Waste. INEEL report, September 1999. Joint Project between INEEL, Idaho and KEPCO, Korea.

Jacobs Engineering Group, Inc. (US Department of Energy), 1999. Retrieval Performance Evaluation Methodology for the AX Tank Farm. DOE/RI-98-72, Richland Operations Office, Hanford, WA, April, 1999.

C.K. Ho, R.G. Baca, S.H. Conrad, G.A. Smith, L-J. Shyr & T.A. Wheeler, 1999. Stochastic Parameter Development for PORFLOW Simulations of the Hanford AX Tank Farm. SAND98-2880 Sandia National Laboratories, Albuquerque, NM

J.R. Cook, E.L. Wilhite, and L.B. Collard, 1999. Addendum to the Composite Analysis for the E-Area Vaults and Saltstone Disposal Facilities; WSRC-RP-99-00844, Rev. 0. (September), Westinghouse Savannah River Company, Savannah River Site, Aiken, SC 29808.

L.B. Collard and G.P. Flach, 1999. High-Level Waste Tanks Multi-Dimensional Contaminant Transport Model Development, WSRC-TR-99-00100, Rev. 0 (Sep.), Westinghouse Savannah River Company, Savannah River Site, Aiken, SC 29808.

Jacobs Engineering Group, Inc. (US Department of Energy), 1998. Supplemental Performance Evaluation Methodology for the AX Tank Farm. DOE/RI-98-72, Richland Operations Office, Hanford, WA, September 1998.

US Department of Energy, 1998. Supplement Analysis for the Tank Waste Remediation System. DOE/EIS-0189-SA2. Richland Operations Office, Hanford, WA, January 1998.

Kline, N.W., 1997. Initial Acceptance Testing of PORFLOW Version 3.0. HNF-SD-WM-CSWD-085, Rev. 0, Lockheed Martin Services, Inc., Hanford, WA, December 1997.

Kline, N.W., 1997. Vadose Zone Flow Model: Validation with Experimental Data. American Nuclear Soc. 1997 Annual meeting, Orlando, FL, June 1-6.

R. Cook, R. H. Hsu, E. L. Wilhite and A. D. Yu, 1996. Performance Assessment for Low-Level Radioactive Waste Disposal.RadWaste Magazine, pp. 32-38, September.

U.S. Army Corps of Engineers, 1996. Final Remedial Design Submittal Contaminated Groundwater Remediation Explosives Washout Lagoons.Seattle District, U.S. Army Corps of Engineers Seattle, WA, January 1996.

N.W. Kline, 1996 Unit Cell Modeling in Support of Interim Performance Assessment of Low Level Tank Waste Disposal. WHC-SD-WM-RPT-225, Westinghouse Hanford Company, Richland, WA

H. Hsu, A. D. Yu and P. S. Lam, 1995. Effect of Saltstone Vault Roof Configuration on the Rate of Containment Release" Simulators International XII, Simulation Series Vol. 27, No. 3, 231-237, Phoenix, AZ, April 9-13.

Marivoet, J.G. Volckaert, J. Wibin, I. Wemaere, 1995. Sensitivity Analysis of a Geologic Repository for radioactive Waste Disposal in Clay. 5th Int. Conf. Radioactive Waste Management and Env. Remediation, ICEM '95, ASME, Sep 3-5,1995, Berlin, Germany.

N.W. Kline, 1995. Development of Unit Cell Model for Interim Performance Assessment of Vitrified Low Level Waste Disposal. WHC-SD-WM-RPT-189, Westinghouse Hanford Company, Richland, WA.

F.M. Mann, C.R. Eiholzer, N.W. Kline, B.P. McGrail and M.G. Piepho, 1995. Impacts of Disposal System Design Options on Low-Level Glass Waste Disposal System Performance. WHC-EP-0810, Westinghouse Hanford Company, Richland, WA.

Uros Bajzelj and Joze, Kortnik (1994). Modeling of particle transport through natural barriers in the Mine Zirovski vrh with computer program PORFLOW. University of Lubljana Report, 17 p., Ljubljana, Slovenia.

N.W. Kline, 1994. Certification of Version 1.2 of the PORFLOW-3 Code for the WHC Scientific and Computer Center. WHC-SD-WM-CSWD-069, Westinghouse Hanford Company, Richland, WA.

M.G. Piepho, 1994. Grout Performance Assessment Results of Benchmark, Base, Sensitivity and Degradation Cases. WHC-SD-WM-TI-561, Westinghouse Hanford Company, Richland, WA.

ACRi, 1994. PORFLOW: A Software Tool for Multiphase Fluid Flow, Heat and Mass Transport in Fractured Porous Media - Validation, Version 2.50. Analytic & Computational Research, Inc, Los Angeles, CA.

A.D. Yu, J.R. Cook, P.S. Lam, E.L. Wilhite and C.S. Smith, 1994. Radiological Performance Assessment for the E-Area Vaults at the Savannah River Site - Part I: Simulation of Radionuclides Migration in the Near-Field. XI Annual Simulators Conference, Simulation Series Vol. 26, No. 3, 315-322, San Diego, CA, April 11-14

R.A. Hiergesell, A.D. Yu, J.R. Cook, L.M. McDowell-Boyer, and P.M. Kearl, 1994 Radiological Performance Assessment for the E-Area Vaults at the Savannah River Site -Part II: Simulation of Contaminant Migration in the Far-Field. XI Annual Simulators Conference, Simulation Series Vol. 26, No. 3, 323-329, San Diego, CA, April 11-14.

Stetson-Harza, 1994. Preliminary Design Report - Whitestown Landfill Remediation, New York State Department of Environment.NYSDEC Site # 633013,February 9, 1994. Stetson-Harza, Utica, NY 13501.

ACRi, 1994. PORFLOW: A Software Tool for Multiphase Fluid Flow, Heat and Mass Transport in Fractured Porous Media - Validation, Version 2.50. Analytic & Computational Research, Inc, Los Angeles, CA.

Singleton, K.M. and K.A. Lindsey, 1994. Groundwater Impact Assessment Report for the 216-U-14 Ditch. WHC-EP-0698, Westinghouse Hanford Company, Richland, WA.

A. D. Yu, J. R. Cook, R. A. Hiergesell, C. A. Langton, and E. L. Wilhite, 1993. Control of Tritium Migration at the Savannah River Site. 4^th International Conf. on the Chemistry and Migration Behavior of Actinides and Fission Products in the Geosphere, Charleston, SC, Dec. 12-17.

Kline, N.W., 1993. Certification of Version 1.2 of the PORFLOW-3 Code for the Hanford Cray Computer, WHC-SD-ER-CSWD-003, Westinghouse Hanford Company, Richland, WA.

L. M. McDowell-Boyer and A. D. Yu, 1993. Performance Assessment of the Saltstone Wasteform: Potential Effects of the Degradation of Hydraulic and Diffusive Properties. Proceedings, 15^th Annual U. S. Department of Energy Low-Level Radioactive Waste Management Conf., 118-126, Phoenix, AZ, Dec.

Converse Consultants NW and Pacific Groundwater Group, 1993. Southwest Harbor Cleanup and Redevelopment Project Sediment Dredge Disposal Containment Model Study.Seattle, Washington.

A. D. Yu and S. O. Magnuson, 1993. Simulation of Contaminant Release from a Saltstone Vault.Simulators X, Proceedings of the 1993 International Simulators Conference, 505-511, Arlington, VA.

Franc Runovc and Joze Kortnik, 1993. Environmental Pollution Prognosis For Underground Waste Deposits.Mining conference at 33. Jump Over the Leather, 11 p., Ljubljana, Slovenia.

Vishnu Ranganathan, 1993. The Maintenance of High Salt Concentrations in Interstitial Waters Above the New Albany Shale of the Illinois Basin. Water Resources Research, 29, 11, 3659-3670.

S.P. Reidel, V.G. Johnson, N.W. Kline, 1993. Groundwater Impact Assessment for the 216-U-17 Crib, 200 West Area. WHC-EP-0664, Westinghouse Hanford Company, Richland, WA.

S.S. Lowe, W.C. Carlos, J.J. Irwin, R. Khaleel, N.W. Kline, J.D. Ludowise, R.M. Marusich, P.D. Rittman, 1993. Engineering Study of Tank Leaks Related to Hydraulic Retrieval of Sludge from Tank 241-C-106. WHC-SD-WM-ES-218, Westinghouse Hanford Company, Richland, WA.

Mark D. Williams, 1993. Two and Three Dimensional Numerical Simulations of Continuous and Episodic Basin Dewatering Around a Salt Dome with the Formation of Thermal and Brine Plumes. Thesis, Master of Science, Dept of Geological Sciences, Indiana University

U.S. Department of Energy, 1993. Hanford Site Risk Assessment Methodology. DOE/RL-91-45 Rev. 2, US DOE, P.O. Box 550, Richland, WA 99352.

A.K. Runchal and B. Sagar, 1993. PORFLOW: A Multifluid Multiphase Model for Simulating Flow, Heat Transfer and Mass Transport in Fractured Porous Media, User's Manual - Version 2.41. NUREG/CR-5991; CNWRA 92-003, U.S. Nuclear Regulatory Commission, Washington, DC.

Franc Runovc and Joze Kortnik (1992). Estimation of pollutant migration from underground spaces. Mining & Metallurgy Quarterly - RMZ, Vol. 39, No. 3-4, p. 433-446, Ljubljana, Slovenia. (ISSN 0035-9645)

R.T. Green, A.C. Bagtzoglou, G.W. Wittmeyer, B. Sagar, and R.G. Baca, 1992. Computational Analyses of Groundwater Travel Time - A Preliminary Study.Prepared for the Nuclear Regulatory Commission, Contract NRC-02-88-005, CNWRA, SwRI, San Antonio, TX.

A. D. Yu and S. O. Magnuson, 1992. PORFLOW Modeling of Nitrate Release from a Saltstone Vault. Workshop on Groundwater Modeling for Environmental Applications, Santa Barbara, CA, September.

Mikko Ahola and Budhi Sagar, 1992 Regional groundwater modeling of the saturated zone in the vicinity of Yucca Mountain, Nevada. NUREG/CR-5890; CNWRA92-001, U.S. Nuclear Regulatory Commission, Washington, DC.

Swen O. Magnuson and Andrew D. Yu, 1992. Mechanisms of Contaminant Migration from Grouted Waste. 14^th Annual US Department of Energy Low-Level Radioactive Waste Management Conf., 118-126, Phoenix, AZ, November.

Martin Marietta Energy Systems, Inc., EG&G Idaho, Inc., Westinghouse Hanford Company and Westinghouse Savannah River Company, 1992. Radiological Performance Assessment for the Z-Area Saltstone Disposal Facility. WSRC-RP-92-1360, Westinghouse Savannah River Company, Aiken, SC.

Mark Stephens, 1992. Effluent Disposal Assessment Fedhaven-Nalcrest Subdivision for Lake Wales Utilities Company. Job # 2286, Atlanta Testing & Engineering, Imperial Lakes Crown Centre, Suite 218, P.O. Box 5527, Lakeland, Florida 33807, June 5.

R.G. Baca, S.O. Magnuson, H.D. Nguyen and P. Martian, 1992. A Modeling Study of Water Flow in the Vadose Zone beneath the Radioactive Waste Management Complex. EGG-GEO-10068, Idaho National Engineering Lab., Idaho Falls, ID.

A.K. Runchal and B. Sagar, 1992 PORFLOW: A Multifluid Multiphase Model for Simulating Flow, Heat Transfer and Mass Transport in Fractured Porous Media, User's Manual - Version 2.41. NUREG/CR-; CNWRA 92-003, U.S. Nuclear Regulatory Commission, Washington, DC.

M.L. Rockhold, and S.K. Wurstner, 1991. Simulation of Unsaturated Flow and Solute Transport at the Las Cruces Trench Site Using the PORFLOW-3 Computer Code. PNL-7562/UC-702, Pacific Northwest Laboratory, Richlnad, WA 99352.

A. D. Yu, J. R. Cook and B. T. Butcher, 1991. Performance Assessment and Design of an Intermediate-Level Tritium Disposal Vault. Trans. Amer. Nucl. Soc., 64, 119-120.

M.G. Piepho and A.K. Runchal, 1991. A Comparison of Three Methods for Solving Flow Equations of Two-Immiscible Fluids in Variably-saturated Media. WHC-SA-1289-FP, Westinghouse Hanford Company, Richland, WA.

J.C Walton and R. Seitz, 1991. Performance of Intact and Partially Degraded Concrete Barriers in Limiting Fluid Flow. NUREG-CR-5614, U.S. Nuclear Regulatory Commission.

Principia, S.A., 1991. Impacto Hidrogeologico de la Ampliacion del Metro de Valencia. Informe no. 189/91, Proyecto P-80, Principia, S.A., Velazquez, 94, 28006 Madrid, Spain.

S.O. Magnuson, R.G. Baca and A.J. Sondrup, 1990. Independent Verification and Benchmark Testing of the PORFLO-3 Computer Code, Version 1.0.EGG-BG-9175, Idaho National Engineering Lab., Idaho Falls, ID.

Golder Associates, Inc., 1990. Phase 1 Remedial Investigation Report for the Hanford Site - 1100-EM-1 Operable Unit, Volume I. DOE-R-90-8, U.S. Department of Energy, Richland, WA.

B. Sagar and Runchal, A. K., 1990. PORFLOW-3: A mathematical model for fluid flow, heat and mass transport in variably saturated geologic media -Theory and Numerical Methods, Version 1.0. WHC-EP-0042, WestinghouseHanford Company, Richland, WA.

J.C. Walton and B. Sagar, 1990. Fluid flow through small flaws in impermeable liners: Importance of isolation for hazardous waste. Environmental Science & Technology, Vol 24, 6, p 920-924.

J.C. Walton. 1990. Mathematical Modeling of Mass Transport and Chemical Reaction in Crevice and Pitting Corrosion. Corrosion Science, Vol 30, 8/9, p. 915-928.

J.C. Walton, R.G. Baca, J.B. Sisson and T.R. Wood, 1990. Application of Soil Venting at a Large Scale: A Data and Modeling Analysis. Fourth Nat'l Outdoor Action Conference on Aquifer Restoration, National Water Well Association, Dublin, Ohio, p 619-632.

J.L. Smoots and B. Sagar, 1990. Three-Dimensional Plume Dynamics in the Vadose Zone: PORFLO-3 Modeling of the Defense Waste Leak at Hanford. 1st Int'l High Level Radioactive Waste Management Conf., Las Vegas, April 8-12, p 537-543.

M.L. Rockhold, B. Sagar and M.P. Connelly, 1990. Multi-Dimensional Modeling of Unsaturated Flow in the Vicinity of Exploratory Shafts and Fault Zones at Yucca Mountain, Nevada. 1st Int'l High Level Radioactive Waste Management Conf., Las Vegas, April 8-12, p 1192-1199.

J.C. Walton. 1990. Theoretical Modeling of Crevice and Pitting Corrosion Processes in Relation to Corrosion of Radioactive Waste Containers. Materials Research Society, Vol 176, p 509-516.

J.C. Walton and M.D. Otis, 1990. Concrete Barrier Performance in Radioactive Waste Disposal in the Unsaturated Zone. Materials Research Society, Vol 176, p 711-717.

J.L. Smoots and B. Sagar, 1990. Three-Dimensional Contaminant Plume Dynamics in the Vadose Zone: Simulation of the 241-T-106 Single-Shell Tank Leak at Hanford. PNL-7221, Battelle Pacific Northwest Lab, Richland, WA.

J.L. Smoots, J.E. Szecsody, B. Sagar, G.W. Gee and C.T. Kincaid, 1989. Simulations of Infiltration of Meteoric Water and Contaminant Plume Movement in the Vadose Zone at Single-Shell Tank 241-T-106 at the Hanford Site. WHC-EP-0332, Westinghouse Hanford Company, Richland, WA.

A.K. Runchal and B. Sagar, 1989. PORFLOW-3: A mathematical model for fluid flow, heat and mass transport in variably saturated geologic media -User's Manual, Version 1.0. WHC-EP-0041, Westinghouse Hanford Company, Richland, WA.

B. Sagar, M.P. Connelly and P.E. Long, 1989. Modeling of hydrologic perturbations during reverse circulation drilling. J. Ground Water, American Assoc. of Ground Water Hydrologists.

R.G. Baca, J.C. Walton, A.S. Rood and M.D. Otis, 1988. Organic contaminant release from a mixed waste disposal site: A computer simulation study of transport through the vadose zone and site remediation. Proc. Tenth Annual DOE Low-level Waste Management Conf.

O. Hembise and P. Loiseau, 1988. Etude tridimensionnelle d'une fuite de gaz: Gaz de France. Principia Recherche Developpement, Report 88.11.279b.

O. Hembise and P. Loiseau, 1988. Etude bidimensionnelle d'une fuite de gaz: Gaz de France.  Principia Recherche Developpement, Report 88.11.279.

P. Loiseau, 1988. PORFLOW: Uncode de calcul pour simuler les transferts en milieu poreux. M.Sc. Thesis, Institute National Polytechnique de Toulouse, Ecole Nationale Superieure, Toulouse, France.

J.C. Walton and B. Sagar, 1988. Modeling performance of steel containers in high-level waste repository environments: Implications for waste isolation. Radioactive Waste Management and the Nuclear Fuel Cycle, Vol 9 (4), pp. 323-347, Harwood Academic Publishers.

J.C. Walton and B. Sagar, 1988. Mathematical modeling of Copper Container Corrosion: the Transport Limited Approach. Ed. R.G. Post, Proc. Symposium on Waste Management '88, p. 711-717, Univ. of Arizona, Tucson, Arizona.

Gough, J.M., 1988. Validation Test of the Well Simulation Program PORFLOW3.Principia Mechanica Ltd., London, U.K.

Aimo, N.J., 1987. Preliminary numerical study of the effects of fluctuating river level on solute transport within riverbank aquifers.M.SC. Thesis, Washington State University.

Runchal, A.K., 1987. Theory and application of the PORFLOW model for analysis of coupled fluid flow, heat and radionuclide transport in porous media, in Coupled Processes Associated with Nuclear Waste Repositories, pp. 495-516, Academic Press, 1987, Ed. C-F. Tsang.

Walton, J.C. and B. Sagar, 1987. A Corrosion model for nuclear waste containers.Materials Research Society, Symp. Proc. Vol 84, p 271-282.

P. Bardey, V. Perrin and G. Barrot, 1987. Etude de Taux de Fuite d'une Enceinte de Confinement: CEA.Principia Recherche Developpement, Report 86.02.074.

A.K. Runchal, B. Sagar, R. G. Baca, and N. W. Kline, 1985. PORFLO - A continuum model for fluid flow, heat transfer, and mass transport in porous media: model theory, numerical methods and computational tests.RHO-BW-CR-150P, Rockwell Hanford Operations, Richland, WA.

L.L. Eyler and M.J. Budden, 1984. Verification and Benchmarking of PORFLO: An Equivalent Porous Continuum Code for Repository Scale Analysis. Report # PNL-5044, UC-70, Battelle Pacific Northwest Lab., Richland, WA.

M.R. Fujioka and A.K. Runchal, 1983. Cooling water supply disposal in coastal aquifer. J. Energy Eng., Vol. 109, No. 2, pp. 88-102, June 1983.

N.W. Kline, A.K. Runchal and R.G. Baca, 1983. PORFLOW computer code: Users guide.RHO-BW-CR-138P, Rockwell Hanford Operations, Richland, WA.

A.K. Runchal, 1982. PORFLOW: A mathematical model for coupled ground water flow, heat transfer and radionuclide transport in porous media. ACRi/TN-006.

A.K. Runchal, 1982. PORFREEZ: A general purpose ground water flow, heat and mass transport model with freezing, thawing and surface water interaction.ACRi/TN-005

A.K. Runchal, P. Bardey, B. Sagar and R.G. Baca, 1982. An equivalent continuum model for flow and transport in basalt medium: Volume I - Theory and Benchmarking. Rockwell Hanford Operations, Basalt Waste Isolation Project, Richland, Washington.

B. Sagar, 1982. Estimation of drawdown due to dewatering of an open pit mine.ACRi Job # 001-05-01, Kaman Tempo, Denver, CO.

B. Sagar and A.K. Runchal, 1982. GEOFORM: A mathematical model for flow, heat transfer and mass transport in consolidating porous media under conditions of sedimentation and erosion.ACRi/REP/013 & ACRi Job # 001-03-01, Exxon Production Research Company, Houston, Texas.

A.K. Runchal, 1981. Numerical modeling of some geotechnical considerations associated with underground isolation of nuclear wastes at the Savannah River Plant, South Carolina.National Academy of Sciences, Washington, D.C., ACRi Job #008-01-01.

A.K. Runchal, and G. Hocking, 1981. An equivalent continuum model for fluid flow, heat and mass transport in geologic materials. ASME/AIChE National Heat Transfer Conf., Milwaukee, Aug. 2-5, 1981, ASME publication 81-HT-54.

A.K. Runchal, B. Sagar, J. Treger, R.G. Baca and Arnett, R.C., 1981. Theoretical analysis of waste isolation in a basalt media: an evaluation of postulated release scenarios. ACRi Job # 003-01-01, Rockwell Hanford Operations, Richland, Washington.

A.K. Runchal, 1980. A porous media fluid flow, heat & mass transport model with rock stress coupling. Proc. Workshop on Numerical Modeling of Thermohydrological Flow in Fractured Rock Masses, Lawrence Berkeley Laboratory Report# 11566.

A.K. Runchal, 1980. Mathematical modeling for ground water flow with heat transfer, freezing, thawing and atmospheric heat exchange. ACRi Job # 004-02-01, Northern Technical Services, Anchorage, AK.

A.K. Runchal, 1980. A description of panther computer program for transient analysis of heat transfer & fluid flow with chemical reaction in porous media.ACRi/REP-001, British Nuclear Fuels Limited, Risley, U.K.

A.K. Runchal and T. Maini, 1980. The impact of a high level nuclear waste repository on the regional ground water flow.Int. J. of Rock Mechanics and Mining Science Oct.

Hocking G. and A.K. Runchal, 1979. Numerical modeling of rock stresses within a basaltic nuclear waste repository. Dames & Moore Job #10731-001/002-86, Rockwell Hanford Operations, Richland, WA.

A.K. Runchal, 1979. Modelling of processes occurring in the magnox swarf silos.Dames & Moore Job #11334-003-60, British Nuclear Fuels Limited, Risley, U.K.

A.K. Runchal and T. Maini, 1979. Regional ground water flow near a high-level radioactive waste repository.Engineering Bulletin 50, Dames & moore, December 1979, pp. 11-20.

A.K. Runchal, G.S. Segal and A. Mills, 1979. Proceedings of the workshop on ground water flow model GWTHERM.Dames & Moore ATG/TN-LA-45.

A.K. Runchal, J. Treger and G. Segal, 1979. Two-dimensional fluid flow, heat and mass transport in porous media.Dames & Moore ATG/TN-LA-34.

A.K. Runchal, 1978. Ground water movement and nuclide transport. Technical support for geis: radioactive waste isolation in geologic formations.Y/OWI/TM-36/21, U.S. Dept. of Energy Contract W-7405 Eng 26, Union Carbide Subcontract 62Y-45701C, Dames & Moore Job # 00822-107-23, April, 1978. Office of Waste Isolation, Union Carbide, Oak Ridge, TN.

A.K. Runchal and T. Maini, 1978. The impact of a high level radioactive waste repository on the regional ground water flow.Dames & Moore ATG/TN-LA-30, October 16, 1978, Abstract Appeared in 1978 Joint Annual Meeting GSA, GAC and MAC, Toronto, Ontario, Canada, October 23-26.

A.K. Runchal and G.S. Segal, 1978. Two-dimensional fluid flow analysis in porous media with temperature and density variations.Dames & Moore, ATG/TN-LA-36.

Last Updated: October 2000