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State of New York'S Motion for Leave to File Additional Bases for Previously-Admitted Contention NYS-25 in Response to Entergy'S July 14, 2010 Proposed Aging Management Program for Reactor Pressure Vessels & Internal Components
	ML103050402
Person / Time
Site:	Indian Point
Issue date:	09/15/2010
From:	Sipos J; State of NY, Office of the Attorney General
To:	; Atomic Safety and Licensing Board Panel
	SECY RAS
References
	50-247-LR, 50-286-LR, ASLBP 07-858-03-LR-BD01, RAS E-410
	Download: ML103050402 (96)
	v • d • e

DOCKETED September 16, 2010 (8:30am).

OFFICE OF 'SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF UNITED STATES NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD

. .. -. . .X In re: Docket Nos. 510-247-LR; 50-286-LR License Renewal Application Submitted by ASLBP No. 0' 7-858-03-LR-BDO1 Entergy Nuclear Indian Point 2, LLC, DPR-26, DPR -64 Entergy Nuclear Indian Point 3, LLC, and Entergy Nuclear Operations, Inc. September 15, 2010

x STATE OF NEW YORK'S MOTION FOR LEAVE TO FILE ADDITIONAL BASES FOR PREVIOUSLY-ADMITTED CONTENTION NYS-25 IN RESPONSE TO ENTERGY'S JULY 14, 2010 PROPOSED AGING MANAGEMENT PROGRAM FOR REACTOR PRESSURE VESSELS AND INTERNAL COMPONENTS A. Introduction Pursuant to 10 C.F.R. § 2.309(f)(2) the State of New York seeks leaveto file the attached Additional Bases for Previously-Admitted Contention NYS-25. The Additional Bases are based on Entergy's filing with the Board of a proposed aging management program concerning the embrittlement of reactor pressure vessels (or RPV) and internal components, which was filed in an attempt to meet its obligations under 10 C.F.R. § 54.51 (c)(1)(iii) with regard to RPV and internal components. 1 Entergy's initial License Renewal Application did not contain an aging management program concerning the embrittlement of reactor pressure vessels and internal components. On July 14, 2010 Entergy provided NRC Staff with the Ninth Amendment to the Indian Point License Renewal Application. That amendment, denominated NL-10-063, contained a description of an entirely new aging management program that did not exist before.

Entergy's submission to the Board and the parties in this proceeding was dated July 15, 2010.

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The State of New York's Additional Bases (as well as the accompanying Additional Supporting Evidence and the September 15, 2010 declaration of Dr. Richard Lahey) are based on, and address deficiencies in, Entergy's July 14, 2010 NL- 10-063 filing. Pursuant to the Scheduling Order issued by the Board on August 12, 2010, the filing of the proposed Additional Bases is timely, as they are being filed on September 15, 2010 -- the date by which the Board permitted the State to file new or supplemental contentions arising from Entergy's Ninth Amendment to the License Renewal Application concerning embrittlement of reactor pressure vessel components. See Scheduling Order dated August 12, 2010. Thus, the remainder of this pleading addresses the other factors in 10 C.F.R. § 2.309(f)(2) as well as the requirements of 10 C.F.R. § 2.309(f(1) as required by the Board's July 1, 2010 Order.

B. The Contention Meets All The Requirements of 10 C.F.R. § 2.309(f)(2)

The contention fully meets 10 C.F.R. § 2.309(f)(2) which requires for admissibility, in pertinent part, a showing that:

(i) The information upon which the amended or new contention is based was not previously available; (ii) The information upon which the amended or new contention is based is materially different than information previously available; and (iii) The amended or new contention has been submitted in a timely fashion based on the availability of the subsequent information.

Id.

1. Information Not Previously Available Since the Additional Bases are based upon a document first filed with the parties to this proceeding in July 2010 and on the new information contained in that document regarding a 2

proposed aging management program concerning the embrittlement of RPV internals, the State's submission relies on information not previously available and thus meets the first prong of the test set forth in 10 C.F.R. § 2.309(f)(2)(i).

2. The New Information Is Materially Different Than Previously Available Information Before July 14, 2010 Entergy had not submitted an aging management program for reactor pressure vessels and internal components and embrittlement. As Entergy itself acknowledges in NL-10-063, "The Reactor Vessel Internals Program is a new plant-specific program." NL-10-063 at 84. Entergy's new July 2010 proposal and its contents differ materially from Entergy's previous proposal in its 2007 LRA. There, Entergy proposed to "manage loss of fracture toughness, cracking, change in dimensions (void swelling), and loss of preload in vessel internals" by participating in industry programs investigating aging effects of reactor internals and subsequently preparing an inspection plan for NRC review. Entergy LRA §§ A.2.1.41 (Reactor Vessel Internals Aging Management Activities (for IP2)); A.3.1.41 Reactor Vessel Internals Aging Management Activities (for IP3)).

2 C. The New Bases Meet All the Requirements of 10 C.F.R. § 2.309(f)(1)

1. The Bases Are Within the Scope of License Renewal New York State Contention NYS-25 claims that:

Entergy's License Renewal Application Does Not Include An Adequate Plan To Monitor And Manage The Effects Of Aging Due To Embrittlement Of The Reactor Pressure Vessels ("RPVs")

And The Associated Internals 2 It is not clear that a showing needs to be made that new bases are allowable under 10 C.F.R. § 2.309(f)(1). Out of an abundance of caution, the State of New York provides the following demonstration that the new bases meet any requirements of § 2.309(f)(1) that might arguably be relevant to bases.

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This contention and its bases have already been admitted by the Board. Entergy Nuclear Operations,Inc., (Indian Point Nuclear Generating Units 2 and 3), Memorandum and Order (Ruling on Petitions to Intervene and Requests for Hearing) LBP-08-13 at 103-104, 68 NRC 43 (July 31, 2008). Now that Entergy has proposed a program, which it states will address aging management of the reactor pressure vessels and their internals due to embrittlement, the State of New York is expanding its original bases to address specific shortcomings in the newly offered plan. The RPV and internal components that are the subject of the recently-proposed AMP are plainly within the scope of Part 54. Thus the State's additional bases, which continue the challenge to Entergy's now-modified attempt to provide an adequate AMP for RPV and internals related to embrittlement, remain within the scope of this license renewal proceeding.

2. The Issues Raised Are Material to the Findings that the NRC Must Make to Support the Action that is Involved in this Proceeding The issue of embrittlement of the Indian Point RPVs and their internals is material to this relicensing proceeding because, if the State is correct in its contention, the NRC must make certain findings to protect the public health and safety and the environment, and either deny the license renewal, or impose significant modifications on the applicant's operations. See 10 C.F.R.

§§ 54.4(a)(1)and (3), 54.2 1(c)(1)(iii), and 54.29(a). The State has demonstrated in the Additional Bases, which are supported by the September 15, 2010 Declaration of Dr. Richard Lahey,.that embrittlement is a significant safety and public health issue. Sept 15, 2010 Lahey Decl. at ¶¶ 8-12. Inadequate management of the effects of embrittlement on RPV and internals could lead to failures of those components to perform their intended safety functions and/or cracks in these components, which could result in the breaking away of parts which would interfere with other components and systems performing their safety functions. Sept 15, 2010 Lahey Decl. at ¶¶ 13-14, 16-18.

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3. Adequate Bases Have Been Provided For the Contention The State of New York today seeks leave to present Additional Bases in further support of a previously-admitted contention. These Additional Bases are detailed and exceed the regulatory requirement in 10 C.F.R. § 2.309(f)(1)(ii) for a "brief explanation" of the bases. The Additional Bases describe a number of deficiencies in Entergy' s submission regarding its AMP for embrittlement of RPV and internal components. These bases are in addition to the bases previously accepted when Contention NYS-25 was admitted. The bases for this new contention allege not that Entergy has omitted something, but that what Entergy has presented does not meet its burden to prove that the AMP for RPV and internals embrittlement is adequate to meet the requirements of 10 C.F.R. § 54.51(c)(1)(iii).

4. A Concise Statement of Facts and Expert Opinion Support the Contention Dr. Richard Lahey has offered his expert opinion that Entergy's July 14, 2010 Amendment to its LRA is flawed and does not provide an adequate AMP. For example, Dr.

Lahey has provided his opinion that the proposed AMP does not adequately address the combined synergistic effects of embrittlement and fatigue on RPV and internal components.

See, e.g., Sept. 15, 2010 Lahey Decl. at ¶¶ 8-13. Dr. Lahey also states that proposed aging management plan as set forth in NL- 10-063 lacks sufficient details to know precisely when the baseline inspections of the RPV and its internals will begin or when they will be completed. See Sept. 15, 2010 Lahey Decl. at ¶ 19. He also states that such baseline inspections and measurements should be completed before each reactor enters period of extended operation. Id.

Dr. Lahey has based his opinion upon Entergy's own submissions, his review of NRC regulations, NRC and industry guidance, technical studies, and his extensive professional experience.

5.

5. A Genuine Dispute Exists with the Applicant on a Material Issue of Law or Fact The State of New York has provided sufficient information that a genuine dispute exists with Entergy regarding several material issues of the fact including whether the recently-proposed AMP is deficient for: (1) failing to consider the synergistic effects of embrittlement and metal fatigue on RPV and internals; (2) failing to provide sufficient objective details about when it will conduct and complete baseline inspections andmeasurements; (3) failing to provide sufficient objective details about how and when it will implement corrective actions to address problems identified with embrittlement; (4) failing to include adequate inspection techniques to identify embrittlement issues for certain RPV internals, including bolts; and (5) relying on vague future commitments to undertake corrective action when Entergy has encountered difficulties in tracking and completing commitments and corrective actions in a timely manner. Conversely, NL- 10-063 reflects Entergy's view not to address such issues.

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F. Conclusion For the reasons stated, the State of New York respectfully requests that the Atomic Safety and Licensing Board grant leave to file the accompanying Additional Bases in support of the already-admiited Contention NYS-25.

Respectfully submitted, J~nJ. 'Sipos Janice A. Dean Assistant Attorneys General Office of the Attorney General for the State of New York The Capitol Albany, New York 12227 (518) 402-2251 dated: September 15, 2010 10 C.F.R. § 2.323 Certification Pursuant to 10 C.F.R. § 2.323(b) and the Board's July 1, 2010 scheduling order, I certify that I have made a sincere effort to contact the other parties in this proceeding, to explain to them the factual and legal issues raised in this motion for leave, and to resolve those issues, and I certify that my efforts have been unsuccessful.

JoA J. Sipos Assistant Attorney General State of New York 7

ADDITIONAL BASES FOR PREVIOUSLY-ADMITTED CONTENTION NYS-25 (Embrittlement of Reactor Pressure Vessels and Associated Internals)

For addition after NYS-25, ¶ 3:

3.1 On July 15, 2010, Entergy provided the Board and the parties in this proceeding with Entergy's July 14, 2010 NL 10-063 communication to NRC Staff conveying Amendment 9 to the License Renewal Application which, in turn, proposed, for the first time, a plant-specific aging management program for reactor vessel internals.

3.2 Entergy's recently-proposed aging management program contained in the July 14, 2010 NL-10-063 submission is inadequate and violates 50:C.F.R. § 54.21(c)(1)(iii) because it does not address or manage the combined, synergistic aging effects of embrittlement and fatigue on reactor pressure vessel intemal'components including the core baffle, intermediate shells, former plates and bolts (particularly the re-entrant comers), and including the baffle-to-baffle bolt locations, the core barrel-to-former bolt locations, and baffle-to-former bolt locations, core barrel (and its welds), lower core plate and support structures, clevis bolts, fuel alignment pins, thermal shield, the lower support column and mixer, and the control rods and their associated guide tubes, plates, and welds. The failure of the recently-proposed aging management program to address or manage the combined, synergistic aging effects of embrittlement and fatigue on reactor pressure vessel internal components could have profound safety consequences for the State and its citizens.

3.3 While Entergy's recently-proposed aging management program proposes "baseline" inspections and measurements (NL-10-063 at 87) to analyze the embrittlement of I

various reactor vessel internal components, the proposed program is inadequate because it does not specify with any meaningful precision when such baseline inspections will be initiated or completed. Such baseline inspections and measurements should be completed before each Indian Point reactors enters 20-year extended operation period. The failure of the recently-proposed aging management program to require the completion of such baseline inspections and.

measurements violates 50 C.F.R. § 54.21(c)(1)(iii). The failure of the recently-proposed aging management program to specify when the "baseline" inspections and measurements must be completed could have profound safety consequences for the State and its citizens.

3.4 Entergy's recently-proposed aging management program is also inadequate because it:

(a) does not specify with any meaningful precision when the replacement or repair of embrittled reactor vessel internal components will take place (NL- 10-063 at 88);

(b) disavows taking any preventative action to manage the effects of embrittlement aging of reactor vessel internal components (NL-10-063 at 86);

(c) relies on less reliable remote-control VT-3 examinations to examine baffle-former assembly plates and edge bolts instead of the more reliable volumetric ultrasonic testing (UT) (which Entergy states it will use to examine the nearby baffle-to-former bolting) (NL-10-063 at 87; EPRI MRP-227 at 4-4 to 4-5, 4-14 to 4-16).

These deficiencies in the proposed aging management program violate 50 C.F.R. § 54.21 (c)(1)

(iii) and could have profound safety consequences for the State and its citizens.

3.5 Much of what Entergy has proposed in its new aging management program for reactor pressure vessel internals involves commitments to take certain corrective actions in the future (NL- 10-063 at 88); however, there is growing evidence that Entergy is unable to meet its commitments, thus raising material questions about the adequacy of that portion of Entergy's recently-proposed aging management program that depends on future corrective actions.

2.ý

ADDITIONAL SUPPORTING EVIDENCE FOR PREVIOUSLY-ADMITTED CONTENTION NYS-25 For addition after NYS-25, ¶ 7:

7.1 In response to Entergy's recently-proposed aging management program (NL 063), the State of New York also relies on the September 15, 2010 declaration of Richard T.

Lahey, Ph.D.

7.2 Scope. Entergy describes the program as dividing internal components into four categories: (1) "primary" - components that are highly susceptible to effects of at least one aging mechanism; (2) "expansion" - components that are highly or moderately susceptible to the effects of at least one aging mechanism, but which show some degree of tolerance to those aging effects; (3) "existing" - components that are susceptible to an aging mechanism but are covered by an existing aging management program; and (4) "no measures" - components which will not be including within an aging management program. NL-10-063 at 85.

7.3 Preventative Actions. Entergy makes clear that the new aging management program "does not include preventative actions." NL- 10-063 at 86.

7.4 Monitoring Frequency & Methods. Entergy states that the new program will use "periodic and conditional examinations" through visual examinations and volumetric ultrasonic (UT) examinations. NL- 10-063 at pg. 86. Entergy also stated that in some instances it would make "baseline" measurements. NL- 10-063 at 87. Entergy did not specify when it would make the "baseline" measurements or conduct the "periodic" examinations.

7.5 Entergy did not disclose that certain visual examinations (class VT-3 examinations) would be done by remote control. EPRI MRP-227 at 4-4. Moreover, Entergy did 3

not disclose that other visual examination methodologies (class VT-I and class EVT-1) have a greater degree of detection than class VT-3 examinations. Compare NL-10-063 at 87 with EPRI MRP-227 at 4-4.

7.6 Apparently because of radiation exposure concerns, Entergy plans to use remote VT-3 examinations to examine "baffle former assembly plates" and "edge bolts." NL-10-063 at

87. Nevertheless, Entergy plans to use volumetric ultrasonic tests (UT) to examine "baffle former bolting" which-are also locate within the RPV and are in close proximity to the edge bolts and the baffle former assembly plates. Id. Entergy has not explained why it is using different examination methods for similar components.

7.7 Entergy states that it "may" use the results of inspections of the components in the "primary" group to conduct inspections of the components in the "expansion" group. NL-10-063 at 87.

7.8 Entergy also states that "In the case of significant conditions adverse to quality, measures are implemented to ensure that the cause of the nonconformance is determined and that corrective action is taken to preclude recurrence." NL-10-063 at 88. This is a vague commitment to some undefined action in the indefinite future that depends upon Entergy to be diligent in meeting this commitment. However, on September 14, 2010, NRC Staff released an audit of Entergy's Commitment Management System at the Vermont Yankee facility. NRC Staff stated:

The NRC staff audit of the VY's Commitment Management System (CMS) determined that entries were not created in a timely manner for several commitments in the Table to adequately track the status of commitments. The condition reports for these commitments were generated and CMS entries have been created.

A general observation was made of a process weakness in meeting implementation dates and entering CMS entries for each docketed site for 4

commitments made at the fleet leyel. It appears that VY relied on the issuance of a fleet procedure to satisfy the commitment, but issuance date of the procedure exceeded the scheduled commitment date.

NRC Staff, Audit Report (Sept. 14, 2010) ML102420206. On July 31, 2008, Entergy released the "Independent Safety Evaluation Report" that observed (at 14, 43-45) a backlog of preventative and corrective maintenance work at Indian Point.

Respectfully submitted, Jo J. Sipos Janice A. Dean Assistant Attorneys General Office of the Attorney General for the State of New York The Capitol Albany, New York 12227 (518) 402-2251 dated: September 15, 2010 5

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD

X In re: Docket Nos. 50-247LR and 50-286LR License Renewal Application Submitted By ASLB No. 07-858-03-LR-BDO1 Entergy Indian Point 2, LLC, DPR-26, DPR-64 Entergy Indian Point 3, LLC, and Entergy Nuclear Operations, Inc. September 15, 2010

x DECLARATION OF D& RIcHARD T. LAHEY, JR.

I, Richard T. Lahey, Jr., declare under penalty of perjury that the following is true and correct:

1. I am the EdwardE. Hood ProfessorEmeritus of Engineeringat Rensselaer Polytechnic Institute (RPI) in Troy, New York, a member of the National Academy of Engineering (NAE), a Fellow of the American Nuclear Society (ANS) and the American Society of Mechanical Engineers (ASME), and an expert in matters relating to the operations, safety, and the aging of nuclear power plants. I have previously submitted a declaration in support of the Notice of Intention to Participate and Petition to Intervene filed by the State of New York in this proceeding on November 30, 2007, which sets forth my qualifications in detail. By way of summary, I have held various positions in the nuclear industry and academia, and served on numerous panels and committees for the U.S. Nuclear Regulatory Commission (USNRC), Idaho National Engineering Laboratory (INEL),

1 September 15, 2010 Lahey Declaration

Oak Ridge National Laboratory (ORNL), Electric Power Research Institute (EPRI),

National Aeronautics & Space Administration (NASA), and the National Research Council (NRC). I have also held various positions in the nuclear industry and academia, including Dean of Engineering and Chair of the Department of Nuclear Engineering & Science at RPI. I have also been the lead engineer and manager of various departments responsible for safety analyses, Heat Transfer Mechanisms and Core & Safety Development for the General Electric Company (GE), including both military (i.e., Naval) and commercial nuclear reactors. Over the last 40 years, I have also published numerous books, monographs, chapters, articles, studies, reports, and journal papers on nuclear engineering and nuclear reactor safety technology, and most of these publications have been peer reviewed. My curricula vitae, which more fully describes my educational and professional background and qualifications, is attached to this declaration and is available at:

http://www.rpi.edu/l-aheyr/laheyvita.html.

2. The factual statements and the expression of opinion in this declaration are based on, among other things, my best professional knowledge, my extensive professional experience in nuclear reactor technology, and my review of Entergy's April 2007 License Renewal Application, Entergy's July 15, 2010 submission to the Atomic Safety and Licensing Board (conveying Entergy's July 14, 2010 License Renewal Application Amendment No. 9 (communication NL 10-063 to NRC Staff), and other documents referenced in this declaration.

2 September 15, 2010 Lahey.Declaration

3. This declaration documents my recommendations and concerns about Entergy's new July 14, 2010 aging management program discussed in NL-10-063 and the detection and management of the embrittlement and/or corrosion-induced cracking of important structures and fittings within the reactor pressure vessel (RPV), and the age-related safety issues for the Indian Point reactors. My recommendations and concerns are based on my extensive experience and expertise in the field of nuclear reactor thermal-hydraulics and safety. Moreover, this input is based on, and expands upon, many of the concerns that I raised in my prior ASLB declaration concerning the re-licensing of IP-2 & 3.

4. As I stated in my initial November 2007 declaration on these issues in support of the State of New York's Contention 25, in my professional judgment the applicant failed to demonstrate that it had adequately accounted for the aging phenomena of embrittlement for components inside the reactor pressure vessels at Indian Point Unit 2 and Unit 3. My professional judgment has not fundamentally changed based upon Entergy's July 14, 2010 submission of License Renewal Application, No. 9 [NL 10-063].

The Indian Point Reactors

5. Entergy's Indian Point Units 2 & 3 are currently under consideration for 20-year life extensions beyond their original 40-year design life. If approved, these plants will be licensed for operational levels of about 48 effective full power

(

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years (EFPY). These Westinghouse designed plants are 4-loop PWRs and they are currently' rated at power levels of 3,216.4 MWt..

6. They are sited on the east bank of the Hudson River in Buchanan, NY, which is about 24 miles north of the New York City (NYC) border. 2 Because of their close proximity to a very highly populated area (i.e., the NYC metropolitan area),

which is also the world's leading financial center, it is vital that IP Units 2 & 3 fully and unambiguously meet all reasonable and applicable criteria for safe operation.

This is particularly true when considering life extension, since, like metal fatigue failures, failures due to embrittlement are much more likely as the plants age.

7. The USNRC Staff have prepared a guidance document entitled the "Generic Aging Lessons Learned (GALL) Report," NUREG-1801, Rev. 1 (2005), in which Staff seeks to describe various Aging Management Programs (AMP) for the extended operations of nuclear power plants. That USNRC document does not specifically describe aging management programs for the embrittlement of internal components within the reactor pressure vessel (RPV), including, but not limited to, the: control rods and their associated guide tubes, assemblies, and seal welds, and many important in-core structures and fittings which will be discussed 1 The USNRC approved a stretch power increase of 3.26% for IP-2 in 2004 and a 4.85% increase for IP-3 in 2005; IP-2 and IP-3 also received 1.4% power uprates in 2003 and 2002, respectively.

2 By way of additional reference, the Indian Point reactors are approximately 37 miles north of Wall Street in lower Manhattan, 3 miles southwest of Peekskill, 5 miles northeast of Haverstraw, 16 miles southeast of Newburgh, 17 miles northwest of White Plains, 23 miles northwest of Greenwich, Connecticut, 37 miles west of Bridgeport, Connecticut, and 37-39 miles north-northeast of Jersey City and Newark, New Jersey.

4 September 15, 2010 Lahey Declaration

subsequently. See GALL, Chapter XI (Aging Management Programs); see also Entergy NL-10-063, at pg. 84 ("Revision 1 of NUREG-1801 includes no aging management program description for PWR reactor vessel internals."). Although the USNRC Staff did not include an aging management program to address reactor vessel internal components in GALL, I believe that all important safety concerns must be addressed to assure the health and safety of the American public during extended plant operations, and that the safety review for the requested licenses for' extended operations of the two Indian Point reactors should include an analysis of the embrittlement of components inside the reactor pressure vessels and the implementation of a meaningful program to manage the embrittlement of such components during periods of extended reactor operation.

Embrittlement Phenomena

8. As previously discussed in my initial November 2007 declaration (¶¶ 6-18), one of the key age-related phenomena that must be considered in Entergy's License Renewal Application (LRA) is the embrittlement of the reactor pressure vessel's (RPV's) internal metal structures and fittings, which occurs due to the extended irradiation (i.e., the neutron fluence, which is the neutron flux times the duration of the irradiation process) that will be experienced by these metal components, particularly those located within the so-called "belt line" region of the RPV (i.e., the region of the RPV that is closest to the core) where the neutron flux is the highest. In addition, the reactor vessel internals may experience flow/thermal-transient-induced fatigue degradation, as well as embrittlement-induced 5 September 15, 2010 Lahey Declaration

degradation due to various radiation damage mechanisms [Was, 2007], including damage due to void swelling which may occur because of transmutation and other effects [Was, 2007; NUREG/CR-6897; Barnes, 1964]. Also, some in-core components may experience irradiation assisted stress corrosion cracking (JASCC) [WCAP-14577, Rev.1-A, pgs,3-6 & 3-8, 20011, and/or primary water enhanced stress corrosion cracking (PWSCC) [WCAP-14577, Rev. 1-A, pgs. 3-4 & 3-5, 2001] due to prolonged exposure to the high temperature (i.e., T > 400'F) borated primary coolant. In addition, cast austenitic stainless steel reactor components (e.g., some reactor piping/fittings, pump casings, pressurizer spray heads, etc.) and'various reactor pressure vessel (RPV) internals (e.g., the upper mixing vanes, and the upper/lower core assemblies and support columns) are composed of a duplex stainless steel which contains both austenitic and ferretic phases, and are thus subject-to embrittlement- due to thermal- aging [WCAP-14577, Rev. 1-A, pgs. 3-12 &

3-13, 2001; EPRI Report TR-106092, 1.997; NUREG/CR-4513, Rev.1]. Moreover, the heat affected zone (HAZ) of stainless steel and nickel alloy weldments may be more sensitive to embrittlement mechanisms than the base metals being joined

[Hawthorne et al., 1986; NUREG/CR-6960; Carey, 2006].

9. In any event, embrittlement causes metals to lose ductility and become more susceptible to failures due to cracking or fracture. Also, reactor operations may be restricted by embrittlement since the temperature at which the embrittled metal structures and fittings change from non-ductile to ductile behavior (i.e., the so-called nil ductility temperature, NDT) will increase as the reactor operates over 6 September 15, 2010 Lahey Declaration

time and ages. Conversely, during reactor operations, the temperature at which the embrittled metal structures and fittings change from ductile to non-ductile behavior will increase. Significantly, this phenomenon implies that embrittled RPV internals will become progressively more vulnerable to failure due to thermal shocks as reactor operations continue. Obviously, irradiation damage is a serious age-related phenomena, and one that will not be annealed-out (i.e., be healed) during reactor operations since PWR operating temperatures are too low for this to occur.

10. How the rather complex metal degradation mechanisms associated with fatigue and irradiation interact is still an area of active research, but it is known that the radiation-induced damage on reactor vessel internals can be extensive, since they may experience a neutron fluence of up to 1023 n/cm 2 at neutron energy (E) levels of E> 1 MeV (i.e., >100 dpa) 3 [Was, 2007; Robinson, 2008] by the end of life (EOL) for extended operations. Indeed, the EOL Charpy impact Upper Shelf Energy (USE) for some thermally-aged cast stainless steel in-core components could be as low as 28 ft-lbf [WCAP-14577, pg. 3-13, 2001], which is well below the acceptable ASME code-specified minimum of 50 ft-lbf, and even the 43 ft-lbf variance proposed by Westinghouse [WCAP-13587, Rev. 1, 1993], and endorsed by the ACRS [ACRS Letter, 9/23/09], as being acceptable for an Indian Point reactor pressure vessel (RPV) at the EOL.

3 Displacements per atom (dpa) is a measure of radiation damage to a material.

7 September 15, 2010 Lahey Declaration

11. Given that a variance from the applicable ASME Code is needed for the RPV itself, it is noteworthy that the RPV's inner wall experiences much less fluence than many of the in-core metal components that are inside the RPV and in closer proximity to the core and fuel rods. That is, the Indian Point RPVs are expected to experience -1.9 1019 n/cm 2 by the end of extended operations [Entergy Letter, 3/8/10], which, as noted previously, is much less than the -1023 n/cm 2 fluences that may be experienced by some RPV internals. The obvious conclusion is that RPV internal components will be significantly embrittled during the period of extended operations of IP-2 and IP-3; and much more so than the RPV inner wall.

In-core components which are particularly vulnerable include the: core baffle, intermediate shells, former plates and bolts (particularly the re-entrant corners),

and including the baffle-to-baffle bolt locations, the core barrel-to-former bolt locations and baffle-to-former bolt locations, core barrel (and its welds), lower core plate and support structures, clevis bolts, fuel alignment pins, thermal shield, and the lower support column and mixer. As discussed below, such in-vessel components also include the control rods and their associated guide tubes, plates, and welds.

12. Entergy acknowledges that, "PWR internals aging degradation has been observed in European PWRs, specifically with regard to cracking of baffle-former bolting." NL-10-063, at pg. 89. Indeed, EPRI has stated that, "considerable amount of PWR internals aging degradation has been observed in European PWRs."

EPRI MRP-227, at A-4. Entergy also states: "As with other U.S. commercial PWR 8 September 15, 2010 Lahey Declaration

plants, cracking of baffle former bolts is recognized as a potential issue for the

[Indian Point] units." NL-10-063, at pg. 89. Moreover, material degradation has also been observed in control rod guide tube alignment (split) pins. EPRI MRP-227, at A-4.

13. As noted previously, any degradation in ductility will adversely effect the possible pressure-temperature (p-T) operating conditions (i.e., there will be an increase in the nil ductility temperature, NDT). Also, it will adversely affect the ability of embrittled in-core components to withstand thermal shock transients and the decompression shock loads associated with a postulated design basis accident (DBA) loss of coolant accident (LOCA). Moreover, the metal structures and fittings within the RPV are subjected to many of the same transients (e.g., a SCRAM - a rapid insertion of the control rods causing a rapid decrease in the core's power level), which are known to cause fatigue-induced degradation of the primary side piping, nozzles and structures [see, e.g., my Sept. 8, 2010 ASLB Declaration on metal fatigue]. Hence, fatigue will also degrade the strength and ductility of many of the metal structures and fittings within the RPV, but virtually no fatigue analyses of this type have been presented by Entergy in their application for the extended operations of IP-2 and IP-3 [see, e.g., my Sept. 8, 2010 ASLB Declaration on metal fatigue]. Entergy's recently-submitted aging management program amendment [NL-10-063], does not call for an analysis of the synergistic impacts of these different aging effects; I believe that this is a very serious omission and that 9 September 15, 2010 Lahey Declaration

this deficiency should be corrected during the ASLB's re-licensing hearings for Indian Point Units 2 & 3.

14. In addition, severe pressurized thermal shocks can occur during postulated accidents which may rapidly depressurize the secondary side of the reactor system and cause a SCRAM. While pressured thermal shock of the reactor pressure vessel (RPV) itself was discussed in Entergy's re-licensing applications, there was no indication of what new accident analysis was done (if any) in which both embrittlement and fatigue were explicitly taken into account when assessing the effect of the accident-induced transient loads on RPV internals. This is quite important since thermal shock may cause highly embrittled and fatigued in-core components to fail, perhaps leading to an uncoolable core geometry and core melt.

In my opinion, one of the most serious omissions from the USNRC's GALL Report and Standard Review Plan is that there was no mention at all of how highly embrittled and fatigued internal RPV structures and fittings will respond to the severe transient decompression shock loads associated with a DBA LOCA and the subsequent thermal shock loads associated with the discharge into the primary side of the reactor of relatively cold emergency core coolant (ECC) from the accumulators. It is well known [e.g., Tong &'Weisman, pgs. 147-149, 1970] that a strong decompression shock wave, created during the subcooled blowdown phase of a DBA LOCA, can cause significant transient pressure differentials across various internal RPV structures. Detailed experiments (e.g., LOFT) andanalyses have 10 September 15, 2010 Lahey Declaration

shown that, when ductile, these in-vessel metal structures are not likely to fail or deform to the point where a coolable geometry can not be maintained for the core.

In contrast, no such experiments and analyses have been presented by Entergy to justify that highly embrittled and fatigued in-vessel components will not fail and that a coolable core geometry will be maintained subsequent to a DBA LOCA. This is a very serious and, in my opinion, a totally unacceptable omission since brittle and fatigue-weakened structures are known not to tolerate shock loads well (e.g.,

they may break loose or fracture) and, if a coolable geometry of the core is not*

maintained, it can melt, releasing a significant amount of radiation and possibly.

causing a breach of the lower head of the RPV. It is incumbent on Entergy to prove this will not happen, since Federal regulation, 10 C.F.R. § 54.4(a), clearly states that reactor operators must: "provide the capability to shut down the reactor and maintain it in a safe shut-down condition." It is also important to stress that while the USNRC Staff noted in their review of the Safety Evaluation Reports (SERs) for IP-2 & 3 that, "...if certain reactor vessel internals failed, they could potentially inhibit core coolability during an accident." [SER, Dockets 50-247 and 50-286, pg. 2-40, (Nov. 2009)], their primary focus was on the reactor's sample tubing systems, and did not encompass the more critical RPV internal components such as those listed previously in paragraph 11. Also, the industry programs, which Entergy has proposed to follow under the AMP for RPV internals, are mute on the serious age-related safety concern of the coolability of PWR cores subsequent to an accident-induced failure of highly embrittled and fatigued PRV internals. Unfortunately, the 11 September 15, 2010 Lahey Declaration

new aging management plan submitted by Entergy [NL-10-063] does not address or manage the synergistic aging effects of embrittlement and fatigue on RPV internals and the impact of accident-induced shock loads on these components..

15. In summary, I believe the USNRC has made a major error in not highlighting the above age-related safety issues in the GALL Report [NUREG-1801.

Rev. 1] and the Standard Review Plan [NUREG-1800, Rev. 1]. Perhaps this is because of "stove piping" of the safety evaluations and the various AMP issues, in which each is discussed and analyzed separately, and thus the integrated and synergistic effect of accident-induced shock loads on highly embrittled and fatigued RPV internals was not considered. In fact, the aging phenomena of embrittlement and fatigue acting together and in concert with one another has apparently not been considered. In addition, there has apparently been some confusion associated with theUSNRC's-leak- before-break- (LBB) -ruling ENUREG/CR-4572i NUREG- 1061, Vol. 3, 10 CFR 50, Appendix-A], in which the USNRC's the rules were changed for some of the dynamic ex-vessel LOCA loads (i.e., for the pipe whip and jet loads) associated with the design basis accident (DBA). In particular, the USNRC now allows reactor operators to not use the ex-vessel loads associated with a double-ended pipe break if they can show that the primary side piping would be expected to leak well before it breaks. It is significant to note that the LBB ruling does not apply to the in-vessel DBA LOCA decompression and thermal shock loads.

Unfortunately, the implications of this ruling have apparently been misunderstood by many in the nuclear industry, and it appears to have led USNRC staff to not be 12 September 15, 2010 Lahey Declaration

overly concerned about the effect of DBA LOCA decompression loads, and emergency core cooling system (ECCS) or secondary side LOCA induced thermal shock loads, on highly embrittled and fatigued metal components within the RPV.

As a consequence, it appears that this significant safety issue has been totally over-looked in the Standard Review Plan for Licensing Renewal Applications (LRAs).

Integrity of Control Rods, Guide Tubes, and Plates

16. Any aging management program concerning the embrittlement of reactor pressure vessel internals should include control rods and their associated guide tubes, plates, and welds within the scope of such program. The control rods and their associated guide tubes, plates, and welds are also very important RPV internals and their integrity is an extremely important safety concern. They are located in the core region of the RPV, and are inserted into the RPV through the upper head via so-called stub tubes. Their function is to absorb excess fission neutrons (i.e., those not need to achieve a chain reaction) so that the power level of a reactor can be controlled.

17. With respect to control rods and their associated guide tubes and plates, of particular concern is the significant and reoccurring stress corrosion cracking that has been observed in the J-groove seal welds on the control rod drive (CRD) stub tube penetrations of the upper head of PWR RPV's. By way of example, according to USNRC documents, earlier this year the operator of the Davis-Besse reactor, "found evidence boric acid deposits and indications of primary water stress corrosion cracking in their nozzles and welds." NRC Staff, Division of Component 13 September 15, 2010 Lahey Declaration

Integrity, NRC Perspectives on PWR Materials Issues, at 7 (June 2010)

ML101520577. According to the.USNRC, "the timing and extent of cracking was unexpected." Id.; see also NRC News, 111-10-123 (May 26, 2010). It is significant to note that this type of leakage had been found earlier (i.e., in 2002 ) at Davis Besse, and it nearly resulted in a major LOCA due to a massive corrosion-induced failure of the upper RPV head. In fact, the stress corrosion cracking of these type welds is widely considered to be one of the biggest challenges currently facing operating PWRs [NEI 03-08 [Addenda], at D-5 (June 2009)].

.18. In addition, because of geometric considerations, many PWRs

.(including IP-2 and IP-3) can not meet the USNRC's required minimum coverage for the non-destructive testing (NDT) of these important J-groove welds [Walpole, 20091, and thus the integrity of these stub tube welds can not be confirmed.. It

-appears-tha-t-to helpadd ress-this-chroniczproblem-Entergy has ordered two new RPV heads [Telecon-USNRC/Entergy Report, March 18, 2008], but they have not yet been scheduled for installation at Indian Point [Telecon-USNRC/Entergy, March 18, 2008)). In any event, unlike the rather superficial treatment given this important safety concern by Entergy [ NL-10-063], I believe that a tangible, enforceable, and viable aging management program must developed and implemented before re-licensing the Indian Point reactor plants for extended operations since the integrity of these welds must be assured. If not, due to the leakage of borated primary coolant through cracked welds, there can be aggressive corrosion and wasting of the unclad outer surface of the upper head of the RPV 14 September 15, 2010 Lahey Declaration

(such as the serious event that occurred at Davis-Besse and was identified in 2002).

Worse yet, there might be an inadvertent control rod ejection (e.g., due to a massive failure of the welds in the upper RPV head), which could cause a relatively major reactivity excursion, leading to core melting and significant radiation releases.

Baseline Inspections

19. With respect to Entergy's proposal to conduct baseline examinations of the RPV internals, I note that I previously called on Entergy to conduct such examinations and for NRC Staff to require the conduct of such examinations before entering the period of extended operations. In particular, in my initial November 2007 declaration in support of the State of New York's motion to intervene in this proceeding, I stated:

As part of the relicensing review, and prior to the commencement of any extended operations, the NRC should require Entergy to conduct a thorough baseline inspection of both IP2 and IP3. These inspections should involve both visual and physical characterization and the non-destructive testing (NDT) of structures and components, including but not limited to the RPV, the RPV heads/fittings, the control rod drive mechanisms and associated RPV penetrations, most RPV internal hardware, and all key welds and fittings in the primary and secondary systems of the reactors.

.... Thorough baseline inspections should examine the changes that the plants' systems, structures, and components have experienced during the first three and a half decades of operation. Without proper inspections, the NRC, the applicant, and the public will not have the necessary information to assess whether these plants are in any condition to continue to operate for an additional 20 years.... Routine, sound engineering practice requires a thorough baseline inspection for the license extension of a nuclear power plant to establish the state of the reactor facility, systems, structures and components at the end of their design life and disclose degradation which may have occurred.

The failure to conduct thorough baseline inspections prior to life 15 September 15, 2010 Lahey Declaration

extension is reckless and runs counter to rudimentary engineering practice.

See November 2007 Declaration of Richard Lahey, at ¶¶ 24, 25; see also State of New York Notice of Intention to Participate and Petition to Intervene, at pgs. 217-220, State of New York Contention 23 (Baseline Inspections). 4 While Entergy now seems to have embraced the concept of baseline inspections for RPV internals, the text of the proposed aging management plan as set forth in NL-10-063 lacks sufficient details to know when the baseline inspections of the RPV and its internals will begin or when they will be completed. In my opinion, this should occur before the onset of extended operations.

4 Both Entergy and the USNRC Staff opposed this proposal and the State's Contention 23.

16 September 15, 2010 Lahey Declaration

20. For the all reasons given above, I do not believe the Entergy's July 15, 2010 communication to the Board [NL-10-063] concerning a new AMP for RPV internals is adequate to address the new safety concerns and technical issues that I have raised herein.

Pursuant to 28 U.S.C. §1746, I declare under penalty of perjury that the foregoing is true and correct.

September 15, 2010 Troy, New York Dr. Richard.T. Lahey, Jr.

/

17 September 15, 2010 Lahey Declaration

Referenced Documents Barnes, "A Theory of Swelling and Gas Release for Reactor Materials," J. of Nuclear Materials, Vol- 11(2), 135-148, 1964.

Carey, S., "Non-Class 1 Mechanical Implementation Guidelines and Mechanical Tools, Rev. 4," EPRI-1010639, January 2006.

Electric Power Research Institute (EPRI) Report, "Evaluations of Thermal Aging for Cast Austenitic Stainless Steel Components in LWR Reactor Coolant Systems," TR-106092, (Sept. 1997).

Electric Power Research Institute (EPRI), Final Report, Materials Reliability Program: Inspection Standard for PWR Internals (MRP-228), Report No. 1016609 (July 2009), J. Spanner, IPECPROP00056385.

Electric Power Research Institute (EPRI), Materials Reliability Program:

Pressurized Water Reactor Internals Inspection and Evaluation Guidelines, Rev. 0, (MRP-227-Rev. 0), Report 1016596 (December 2008), A. Demma.

EntergyJuly 15, 2010 submission to the Atomic Safety and Licensing Board (conveying Entergy July 14, 2010 Indian Point License Renewal Application, No. 9, NL-10-063 to NRC Staff).

Entergy Letter, Attachment-i to NL-10-030, March 8, 2010.

Hawthorne, et al., "Influence of Radiation on Material Properties," 13th International Symposium (Part-III), ASTM 04-95600-35, June 1986.

NRC ACRS Letter: N. Bonaca (ACRS) to G. Jaczko (USNRC), "Report on the Safety Aspects of the License Renewal Application for the Indian Point Nuclear Generating Unit Nos. 2 and 3," pg.4, September 23, 2009.

NRC News, ,"NRC asks FENOC to discuss basis for Davis-Besse plant restart at public meeting," May 26, 2010.

NRC Staff, "Generic Aging Lessons Learned (GALL) Report," NUREG-1801, Rev. 1 (2005).

NRC Staff, Division of Component Integrity, NRC Perspectives on PWR Materials Issues, at 7 (June 2010) ML101520577.

NRC Staff, Telecon-USNRC/Entergy, "Summary of Telephone Conversation held on March 18, 2008, between US Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc., Pertaining to I.P. units 2 and 3, LRA- Enviromental RAI", March 18, 2008.

1 September 15, 2010 Lahey Declaration

Nuclear Energy Institute, "Changes to NEI 03-08 and NEI 03-08 Addenda," April 23, 2010, ML101050335.

Nuclear Energy Institute, NEI 03-08 [Addenda], "Materials Initiative Guidance,"

pg. D-5, June 2009.

Nuclear Energy Institute, NEI 03-08 [Rev 2], Guideline for the Management of Materials Issues, January 2010.

NUREG/CR-6897, "Assessment of Void Swelling in Austenitic Stainless Steel Core Internals," January 2006.

NUREG/CR-6960, "Crack Growth Rates and Fracture Toughness of Irradiated Austenitic Stainless Steel in BWR Environments," Chopra et al., March 2008.

NUREG/CR-4513, Rev.1 "Estimation of Fracture Toughness of Cast Stainless Steels During Thermal Aging in LWR Systems (ANL-93/22), May 1994 NUREG/CR-4572, "NRC Leak-Before-Break Analysis Method for Circumferentially Through-Wall Cracked Pipes Under Axial Plus Bending Loads," (March 1986).

NUREG-1061, Vol. 3, "Report of the U S. Nuclear Regulatory Commission Piping Review Committee, Evaluation of Potential for Pipe Breaks," (Nov. 1984).

Robinson, M., EPRI Power Point Slides - " Implementation of Industry Change Management Plan forMaterials Related R&D Committees under NEI 03-08,"

Slide 20, 2008.

Tong, L.S. and Weisman, J., "Thermal Analysis of Pressurized Water Reactors,"

ANS Monograph, pp. 147-149, 1970.

Walpole, Robert, "Response to Request for Additional Information Regarding Relief Request-09," Attachment-1 to NL-09-130, 9/24/2009.

Was, Gary S., "Fundamentals of Radiation Material Science," Springer, 2007.

Westinghouse, WCAP-13587, Rev. 1, " Reactor Vessel Upper Shelf Energy Bounding Evaluation for Westinghouse Pressurized Water Reactors," S. Tandon, M.J. Malone, and T.R. Mager, Sept. 1993.

Westinghouse, WCAP-14577, Rev. 1-A, "License Renewal Evaluation: Aging Management for Reactor Internals," D.R. Forsyth et al., March, 2001.

ii September 15, 2010 Lahey Declaration

Attachment curriculavitae Richard T. Lahey, Jr., Ph.D.

September 15, 2010 Lahey Declaration

Dr. Richard T. Lahey Page I of 61 VITA Dr. Richard T. Lahey, Jr.

The Edward E. Hood ProfessorEmeritus of Engineering Rensselaer Polytechnic Institute Troy, New York Education B.S. Marine Engineering-1961, U.S. Merchant Marine Academy M.S. Mechanical Engineering- 1964, Rensselaer (RPI)

M.E. Engineering Mechanics-1966, Columbia University Ph.D. Mechanical Engineering-I1971, Stanford University Professional Experience 7/61 - 9/61 Cities Service Company, New York, New York Third Assistant Engineer - Operating Engineer on "jumbo" tanker, S/S Fort Hoskins also had responsibility for maintenance of all electrical equipment.

9/61 - 8/64 Knolls Atomic Power Laboratory, Schenectady, NY Engineer - Various assignments on advanced naval nuclear submarine (S5G) design.

Thermal Development Group - Experimental work on DNB and hydrodynamic instability.

Fluid Systems Group - Systems design and documentation.

Safety Analysis Group - Analytical investigation of hypothetical accident conditions development of analog and digital computer models.

9/64 - 6/66 Columbia University, New York, New York Research Assistant - University research in the area of biomechanics (blood flow, pulmonary mechanics, etc.)

8/61 - 8/67 U.S.. Navy Naval Officer - USNR 7/66 - 6/71 General Electric, San Jose, California Principal Development Engineer - Responsible for experimental and analytical investigations in two-phase flow and boiling heat transfer phenomena, including: hydrodynamic stability, subchannel analysis, CHF and Pressure drop.

http://www.rpi.edu/-laheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 2 of 61 6/71 - 6/72 General Electric Company, San Jose, California Manager, Heat Transfer Mechanisms - Responsible for applied research in the are of subchannel analysis, transient analysis and detailed Boiling Water Nuclear Reactor (BWR) heat transfer mechanisms.

6/72 - 11/73 General Electric Company, San Jose, California Manager, Core Development - Responsible for all non-safety related thermal-hydraulic development work in support of the boiling water nuclear reactor.

11/73 - 10/75 General Electric Company, San Jose,. California Manager, Core and Safety Development - Responsible for all heat transfer and fluid flow and reactor physics development work in support of the boiling water nuclear reactor. Responsible for all foreign and domestic safety R&D programs.

10/75 - 6/87 Rensselaer Polytechnic Institute, Troy, New York Chairman, Department of Nuclear Engineering & Science - Teaching, research and management of academic department concerned with nuclear technology.

5/87 - 4/89 Rensselaer Polytechnic Institute, Troy, New York Professor, Department of Nuclear Engineering and Engineering Physics, and, Professor, Department of Chemical Engineering - University teaching and research.

4/89 - Present, Rensselaer Polytechnic Institute, Troy, New York The EdwardE. Hood, Jr.Professorof Engineering (4/89-9/08 Emeritus 9/08-Present), Department of Mechanical, Aerospace & Nuclear Engineering and, Chemical Engineering - University teaching and research.

5/91 - 6/94 Rensselaer Polytechnic Institute, Troy, New York Director, Center for Multiphase Research - University teaching, research and administration.

7/94 - 3/98 Rensselaer Polytechnic Institute, Troy, New York Dean of Engineering - Academic administration and research.

Consulting Argonne National Laboratory Long Island Lighting Company http://www.rpi,.edu/-Iaheyr/laheyvita.html 9821 9/8/2010

Dr. Richard T. Lahey Page 3 of 61 Battelle Northwest Laboratories Nuclear Associates International Brookhaven National Laboratory Oak Ridge National Laboratory Babcock & Wilcox Company PJM Intercon nection(Board Member)

Combustion Engineering (ABB) Sandia Laboratories Corning, Inc Savannah River Laboratory Creare, Inc. Singer Link-Miles EG&G Idaho, Inc. (INEL) Stauffer Chemical Company Electric Power Research Institute Stone & Webster Exxon Nuclear Company, Inc. U.S. Department of Energy General Electric U.S. Nuclear Regulatory Commission General Public Utilities Westinghouse (NED)

International Atomic Energy Agency Yankee Atomic Electric Company Air Products Jason Associates NYS-DEC; NYS- OAG NYC (Couch White, LLP)

Norhtrop Grumman Professional Memberships and Technical Review GrouDs American Nuclear Society (ANS)

President, Northeastern New. York Section (78-79)

Member, Board of Directors (79-82)

Member, ANS Executive Committee (80-82)

Member, Executive Committee - Power Division (79-82)

Chairman, Technical Group for Thermal-Hydraulics (79-80)

Member, 7

Executive Committee - Thermal-Hydraulics (80-81)

Member, E.E.&A. Accreditation Committee (84-87)

Member, NHTC Coordinating Committee (86-89)

Member, ANS Nominating Committee (86) http://www.rpi.edu/-Iaheyr/laheyvita.html9//01 ' 9/8/2010

Dr. Richard T. Lahey Page 4 of 61 American Society of Mechanical Engineers (ASME)

Nucleonics Heat Transfer Committee (ASME K-13)

Chairman (78-81)

American Society of Engineering Education (ASEE)

Chairman, Program Committee (86-87)

Chairman, Nuclear Engineering Division (87-88)

American Institute of Chemical Engineers (AIChE)

Chairman, Energy Transport Field Research Committee (87-91)

Association of Engineering Collegesin New York State (AECNYS)

Secretary/Treasurer (96)

ECPD Council ASME Representative, (76-79)

Engineering Manpower Commission (EMC)

Commissioner (81-84)

Council on Competitiveness Member (94-98)

Nuclear Engineering Department Heads Organization (NEDHO)

Chairman (82-83) http://www.rpi.edu/-laheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 5 of 61 Liaison with USNRC and USDOE (82-87)

International Center for-Multiphase Flow - Japan Corresponding Member (USA)

The New York Academy of Sciences (NYAS)

Member (90-09)

Society of the Sigma Xi Member (70-Present)

Editorial Boards Journalof NuclearEngineering& Design (Formerly Editor-NE&D, 83-94)

InternationalJournalof Heat & Mass Transfer InternationalCommunications in Heat & Mass Transfer Journalof Multiphase Science & Technology Nuclear Safety Review Board (RPI)

Chairman (76-87)

EG&G Scientific Advisory Committee Member (76-83)

Review Group Membership http://www.rpi.edu/-laheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 6 of 61 USNRC Advanced Code Review Group (76-84)

USNRC Two-Phase Instrumentation Review Group (76-84)

USNRC Containment Code Review Group (77-84)

USNRC Two-Phase Flow Calibration Review Group (78-84)

USNRC LOFT Review Group (77-83)

USNRC EBTF Research Review Group, (79-82)

USNRC 2D/3D Review Group (79-84)

.USNRC BWR BDHT Review Group (79-84)

EPRI Design Review Committee Member for MAAP Code (88-93)

EPRI Design Review Committee Member for BWRSAR.Code (88-90)

LILCO Peer Review Committee Member (88-92)

USDOE Savannah River Laboratory (SRL) Review Group Member (88-92)

USDOE Advanced Neutron Source (ANS) Review Panel (88-92)

ORNL Engineering Technology Division Advisory Committee - Chairman (89-92)

ORNL Advanced Neutron Source (ANS) Reactor Advisory Committee - Chairman (92-93)

ORNL CASL Science Council - Member (2010 - Present)

National Association of Corporate Directors. (NACD) - Member (97-Present)

National Academy Activities http://www.rpi.edu/-laheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 7 of 61 Member, National Research Council (NRC) -Space Science Boards Committee. on Microgravity Research (1997-2008)

Member, National Research Council (NRC) Study on: "Microgravity Research in Support of Technologies for the Human Exploration and Development of Space and Planetary Bodies" (1998-2000).

Member, National Research Council (NRC)I Study on: "The.Safety and Security of Commercial Spent Fuel Storage" ( 2004 - 2006).

Member, National Research Council (NRC) Decadal Study on: "Biological and Physical Sciences in Space" (2009 - 2010).

Honors

Elected Fellow of ANS (1980)

Elected Life Fellow of ASME (1980)

Elected NationalAcademy of Engineering(1994)

Elected Russian NationalAcademy of Sciences-Baskortostan(1995)

Graduated (with Honors) - USMMA (1961)

Nominated: G.E.s Steinmetz Award (1975)

Whos Who in Engineering

Whos Who in the East

International Whos Who in Energy & .Nuclear Sciences

Whos Who in Technology Today

American Men & Women of Science (1 7 th-Edition)

The International Whos Who of Intellectuals (Vol. VI)

Fulbright-HaysFellowship (1983-1984)

Elected Senior Fellow-Magdalen College of Oxford University (1983-1984)

Keynote Lecture, 5 th Indian Heat & Mass Transfer Conference, Hyderabad, India (1.980)

" Editor, Journalof NuclearEngineeringand Design, (1983-1994)

" Appointed IAEA Expert to Assist Argentina in Nuclear Power Research (1985-Present)

" Keynote Lecturer, International Workshop on Two-Phase Flow Fundamentals, NBS, Gaithersburg, MD (1985)

People-to-People Delegation Leader to the PRC on Nuclear Reactor Safety'(11/4-25/85)

Keynote Lecture, 4 th International Symposium on Multi-Phase Transport & Particulate Phenomena - Miami, Florida (1986)

Keynote Lecturer, International Centre for Heat and Mass Transfer, Dubrovnik, Yugoslavia (1987)

Chairman, DOE/EPRI Second International Workshop on Two-Phase Flow Fundamentals (3/87)

Visiting Professor, University of Pisa, Pisa, Italy (1987)

Visiting Professor, Universite Claude Bernarde, Lyon, France (1987)

Appointed External Dissertation Reviewer - Univeriti Malaya (1987) ,

a Visiting Professor of Engineering, Centro Atomico, Bariloche, Argentina (1988)

Keynote Lecture, Japan Society of Multiphase Flow - Tokyo, Japan (1988).

http://www.rpi.edu/-Iaheyr/laheyvita.htmi 9/8/2010

Dr. Richard T. Lahey, Page 8 of 61

Appointed Honorary Senior Fellow - Magdalen College of.Oxford University (1989-Present)

Elected Chairman of RPI Faculty Council (1989-1991)

Japan Society for the Promotion of Science (JSPS) Fellowship (1990)

Keynote Lecture, American Society of Mechanical Engineers, Dallas, TX (1990)

Alpha Nu Sigma Honor Society (1992)

Plenary Lecturer, International Symposium on Instabilities in Multiphase Flows - Rouen, France (5/92)

Member, Editorial Advisory Board - InternationalJournalof Heat and Mass Transfer e Member, Editorial Advisory Board - InternationalCommunicationsin Heat and Mass Transfer

. U.S. Representative, International Information Center for Multiphase Flow (ICeM)

Mark S. Mills Award of the ANS [Advisee: Susana Kalkach-Navarro] (1993)

. Elected Member of RPI Engineering Research Council (1993-1994)

General Chairman, International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-7), Sept. 10-15, 1995 "Member, Advisory Editorial Board - Heat TransferResearch

Keynote Lecture, MFTP-2000, Antalya, Turkey (2000)

. Member, Presidium, ICMS-2000, UfA, Russia (2000) a Listed as an Expert Knowledge Provider, Intota web site, www.intota.com (2001)

. Keynote Lecture, HEAT-2002, Kielce,Poland (2002)

. Member - Engineering Advisory Board, U.S. Merchant Marine Academy (2003-2005)

Elected to Palmer C. Ricketts Society of Patroons'_ RPI (2004-present)

. Co-Chair, Japan/US Seminar on Two-Phase Flow Dynamics., Nagahama, Japan (2004) e Plenary Lecture, PISA' 04, Pisa, Italy (2004)

Keynote Lecture , Yadigaroglu Retirement Seminar, ETH-Zurich , Zurich, Switzerland (2004) 0 Keynote Lecture, ISMF' 05, Xi'an, China (2005) a Keynote Lecture, NURETH-11 , Avignon, France (2005)

Alexander von Humbolt Senior Scientist Fellowship-FZK (2005-2006) e Keynote Lecture, NURETH-12, Pittsburgh, PA. (2007)

Awards

" Meritorious Service Award of the ANS (1983)

Glenn Murphy Award of the ASEE (1985)

" Technical Achievement Award of the ANS (1985)

" United States Merchant Marine Academy Alumni Association, Outstanding Professional Achievement Award (1986)

" E.O. Lawrence MemorialA wardof the USDOE (1988)

" Arthur Holly Compton Award of the ANS (1989)

" Donald 2.Kern Award of the AIChE (1989)

" Glenn T. SeaborgMedal of the ANS (1992)

" ASME/ANS NHTC Best Paper Award (1993)

" William H. Wiley Distinguished Faculty Award-RPI (200.4)

Books and Monographs "Out-of-Pile Subchannel Measurements in a Nine-Rod Bundle for Water at 1000 http://www.rpi.edu/-Iaheyr/laheyvita.htm l 9/8/2010

Dr. Richard T. Lahey Page 9 of 61 PSIA," Progress in Heat and Mass Transfer, Vol. 6, 1972 (with B. Shiralkar)

"Non-Equilibrium Two-Phase Flows" (Associate Editor), ASME Symposium Volume, 1975.

The Thermal-Hydraulics of a Boiling Water Nuclear Reactor, ANS Monograph, 1977 (with F. Moody).

"Light Water Reactors: Thermal-Hydraulic Aspects of Nuclear Reactor Safety" (Associate Editor), ASME Symposium Volume, 1977.

"Topics in Two-Phase Heat Transfer & Flow" (Associate Editor), ASME Symposium Volume, 1977.

"Power Reactor Concepts and Systems Overview," Chapter 2, Nuclear Reactor Safety Heat Transfer, Hemisphere Press, 1980.

"Light Water Nuclear Reactors," Chapter 4, Nuclear Reactor Safety Heat Transfer, Hemisphere Press, 1980.

"Fundamental Concepts of System Safety Modeling," Chapter 8, Nuclear Reactor Safety Heat Transfer, Hemisphere Press, 1980.

"Basic Mechanisms in Two-Phase Flow and Heat Transfer," (Associate Editor),

ASME Symposium Volume, 1980.

"Section 507: Vaporization/Boiling Heat Transfer," Heat Transfer and Fluid Flow Data Book, General Electric Company, 1981.

"Transient Analysis of Two-Phase Systems," Two-Phase Flow Dynamics, Hemisphere Press, 1981.

"Current Boiling Water Nuclear Reactor LOCA Issues," Two-Phase Flow Dynamics , Hemisphere Press, 1981.

"Advances in Two-Phase Flow Instrumentation," Advances in Nuclear Science and Technology, Vol. 13, 1981 (with S. Banerjee).

"On the Junction Problem in Two-Phase Flow," Selected Topics in Two-Phase Flow, Tapir, 1984.

"An Analysis of Density-Wave Oscillations in Ventilated BWR Fuel Rod Bundles,"

Multi-Phase Flow and Heat Transfer Ill, Part A: Fundamentals, eds. Veziroglu &

Bergles, Elsevier, 1984 (with R. Taleyarkhan and M. Podowski).

"Three Dimensional Conical Probe Measurements in Turbulent Air/Water Two-Phase Pipe Flow," TSI Quarterly (Flow Lines), 1987 (with S.K. Wang, S.J. Lee and O.C. Jones, Jr.)

"Phase Distribution in a Triangular Duct," Multiphase Science and Technology, http://www.rpi.edu/-Iaheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 10 of.61 Vol. 3, Hemisphere Press, 1987.

"Dividing Flow in a Tee Junction," Multiphase Science and Technology , Vol. 3, Hemisphere Press, 1987.

"On the Analysis of Instabilities in Two-Phase Flows," Multiphase Science and Technology, Vol. 4, pp. 183-370, Hemisphere Press, 1989 (with M. Podowski).

"The Three Dimensional Time and Volume-Averaged Conservation Equations of Two-Phase Flows," Advances in Nuclear Science & Technology, Vol. 20, pp. 1-69, 1989 (with D.A. Drew).

"The Prediction of Phase Separation in a Branching Conduit Using a Three-Dimensional Two-Fluid Model," Editor, T.N. Veziroglu, Multiphase Transport and Particulate Phenomena, Vol. 1, Hemisphere Corp., 1990 (with S. Kalkach-Navarro, S.J. Lee and D.A. Drew).

"Relation of Microstructure to Constituitive Relations," Editors, Daniel D. Joseph and David G. Schaeffer, Two Phase Flows and Waves, Vol:26, Springer-Verlag, 1990 (with D.A. Drew and G.S. Arnold).

"The Dispersion and Attenuation of Small Amplitude Standing Waves and the Propagation of Acoustic Pressure Pulses in Bubbly Air/Water Two-Phase Flows,"

Multiphase Science & Technology, Vol. 6, Hemisphere Press, 1992 (with A.E.

Ruggles).

"Boiling Heat Transfer - Modern Developments and Advances," Elsevier, 1992 (Editor).

"Analytical Modeling of Multiphase Flows," Editor, M.D. Roco, Particulate Two-Phase Flow, 1993 (with D.A. Drew).

The Thermal-Hydraulics of a Boiling Water Nuclear Reactor, Second Edition, ANS Monograph, 1993 (with F.J. Moody).

"Two-Phase Flow," The Engineering Handbook, CRC Press, 1994.

Multiphase Science and Technology -, Volume 8, "Two-Phase Flow Fundamentals," Begell House, Inc., New York, 1996 (Co-Editor with G.F. Hewitt, et al).

"A CFD Analysis of Multidimensional Two-Phase Flow and Heat Transfer Phenomena," Process, Enhanced and Multiphase Heat Transfer (A.E. Bergles -

Festschriff), Begell House, Inc., New York, 1996.

"Two-Phase Instabilities," International Encyclopedia of Heat & Mass Transfer, CRC Press, 1997.

"The Air Carryunder Induced by Plunging Liquid Jets," International Encyclopedia of Heat & Mass Transfer, CRC Press, 1997 (with F. Bonetto).

http ://www.rpi.edu/-Iaheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page I I of 61 "Three-Phase Flow Measurements using A Hot-Film Anemometer," Applied Optical Measurements, Editor, M. Lehner et al, Springer, 1999.

"Microgravity Research in Support of Technologies for the Human Exploration and Development of Space and Planetary Bodies", National Reserach Council -

Space Studies Board Topical Report, 2000 "Sonoluminescence and the Search for Sonofusion", Advances in Heat Transfer, Academic Press, Vol. 35, pp: 1-168, 2005.

"Recent Advances and Results in Acoustic Inertial Confinement Bubble Nuclear Fusion", Low Energy Nuclear Reactions and New Energy Technologies Source Book V.2, Oxford University Press, Chapter-8, pp: 139-157, 2009 (with R.P.

Taleyarkhan, C.D. West,R.I. Nigmatulin, R.C. Block, J.S. Cho, Y. Yu).

"Acoustic Inertial Confinement (Bubble) Nuclear Fusion", Energy Encylopedia, John Wiley & Sons, 2010 (with R.P. Taleyarkhan, R. I. Nigmatulin).

Refereed Publications (Journals)

"Mass Flux and Enthalpy Distribution in a Rod Bundle for Single- and Two-Phase Conditions," Journalof Heat Transfer,May 1971 (with B. Shiralkar).

"An Exact Solution for Flow Transients in Two-Phase Systems by the Method of Characteristics," Journalof Heat Transfer,November 1973 (with J. M. Gonzalez-Santalo).

"The Variation of the Vapor Volumetric Fraction During Flow and Power Transients," NuclearEngineeringandDesign, 25, 1973 (with B. Shiralkar).

"The Effect of Obstacles on a Liquid Film," Journalof Heat Transfer, November 1973 (with B. Shiraikar).

"On the Various Forms of the. Conservation Equations in Two-Phase Flow,"

InternationalJournalof Multiphase Flow, No. 2, 1976 .(with G. Yadigaroglu).

-An Exact Analytical Solution of Pool Swell Dynamics During Depressurization by the Method Characteristics," NuclearEngineeringand Design, 45, 101-116, 1978 (with H.W. Vea).

"A Turbine-Meter Evaluation Model for Two-Phase Transients," Journalof Heat Transfer,102, 2/9-13, 1980 (with P.S. Kamath).

"The Analysis of Virtual Mass Effects in Two-Phase Flow," Int. J. of Multiphase Flow 5, 233-242,1979 (with D..A. Drew and L. Cheng).

"Application of General Constitutive -Principles to the Derivation of Multidimensional Two-Phase Flow Equations," Int. J. Multiphase Flow Vol. 4,

.243-264, 1979 (with D.A. Drew).

http://www.rpi.edu/-Iaheyr/laheyvita.htmi 9/8/2010

Dr. Richard T. Lahey Page 12 of 61 "An Experimental Technique fo~r Determination of Steam Fraction in Flowing Steam/Air Mixtures," Nuclear Technology, 48, 1980 (with N. Saba and J.C.

Corelli).

"The Analysis of Boiling Water Reactor Long-Term Cooling," Nuclear Technology, 49, 1980 (with P.S. Kamath).

"The Analysis of CCFL using Drift-Flux Models," Journalof NuclearEngineering andDesign,61, 245-255, 1980 (with K. Ohkawa).

"The Effect of Gravity and Friction on the Stability of Boiling Flow in a Channel,"

AIChE Symposium Series, #199, Vol. 76, 1980- Chem. Eng. Commun., Vol. 11, 59-79, 1981 (with J-L. Achard and D.A. Drew).

"Transient Analysis of DDT Rakes, " NuclearEngineeringand Design, 65, 342-367, 1981 (with P.S. Kamath).

"Development of a Radio-Frequency Excited Local Impedance Probe, "Nucl. Eng.

and Design,67, 125-136, 1981 (with M.Vince and G. Krycuk).

"The Effect of Virtual Mass on the Numerical Stability of Accelerating Two-Phase Flows," Int. J. Multiphase Flow,6, 1981, (with L. Cheng, D.A. Drew and J.E.

Flaherty).

"The Measurement of Phase Separation in Wyes and Tees," Nucl. Eng. and Design, 64, No. 1, 1981 (with T.J. Honan).

"Phase Distribution Mechanisms in Turbulent Two-Phase Flow in Channels of Arbitrary-Cross Section," ASME J. of Fluids Eng., 103, 583-589, 1981 (with D.A.

Drew).

"On the Development of an Objective Flow Regime Indicator," Int. J. Multiphase Flow, 8, No. 2,93-124, 1982 (with M.A. Vince).

"Phase Distribution Mechanisms in Turbulent Low Quality Two-Phase Flow in a Circular Pipe," J,. of FluidMechanics, 117,91-106, 1982 (with D.A. Drew).

"Optical Probe for High Temperature Local Void Fraction Determination, "J. of Applied Optics, 21, 886, 1982 (with M.A. Vince, H.E. Breed and G. Krycuk).

"Measurement of Flow in Large Pipes by the Pulsed Neutron Activation Method,"

Nucl. Sci. Eng., 82, 19-33, 1982 (with M.L. Perez-Griffo and R.C. Block).

"An Experimental Investigation of BWR Parallel Channel Effects, "Nucl Eng. and Design, 73, 425-440, 1983 (with W.M. Conlon).

"The Prediction of Pressure Drop and CCFL Breakdown in Countercurrent Two-Phase Flow," J. of Heat Transfer,105, 1983 (with A. Ostrogorsky and R.R. Gay).

"An Investigation of BWR/4 Parallel Channel Effects During a Hypothetical LOCA http://www.rpi.edu/-Iaheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 13 of 61 for Both Intact and Broken Jet Pumps," Nuclear Technology,Vol. 65, No. 2, 1984 (with M. Fakory).

"The Analysis of Phase Separation Phenomena in Branching Conduits," Int. J. of Multiphase Flow,Vol. 10, 1984 (with N. Saba)

"Measurement of Virtual Mass and Drag Coefficients of a.Disk Oscillating Sinusoidally in a Two-Phase Mixture," Int. J. of Multiphase Flow, 10; No. 3,1984 (with P.S. Kamath and D.R. Harris).

"NUFREQ-NP: A Computer Code for the Stability Analysis of Boiling Water Reactors," Nuc. Sci& Eng., 88, 1984 (with S.J. Peng, M.Z. Podowski and M.

Becker).

"The Development of a Gamma-Ray Scattering Densitometer for the Non-Intrusive Measurement of Local Void Fraction," Nuclear Technology, 67, 1984 (with K. Ohkawa).

"An Instability Analysis of Ventilated Channels," J. Heat Transfer, 107,175-181,.

1985 (with R. Taleyarkhan and M. Podowski).

"The Analysis of Nonlinear Density-Wave Oscillations in Boiling Channels ," J. of FluidMechanics, 155, 213-232, 1985 (with J.L. Achard and D.A. Drew).

"An Analytical Model for the Analysis of BWR/4 Long-Term Cooling with Either Intact or Broken Jet Pump Seals," J. of NuclearEngineeringand Design, 85, 1985 (with M.R. Fakory).

"An Analysis of Wave Propagation in Bubbly Two-Component Two-Phase Flows,"

J. of Heat Transfer,107, 1985, (with L.Y. Cheng and D.A. Drew).

"Measurement of Flow in a Horizontal Pipe using the Pulsed Photon Activation Technique," Nuc. Sci Eng., 91, No. 3,1985 (with T.F. Lin, R.C. Bloc, O.C. Jones,

.Jr. and M. Murase).

"Film Thickness Measurements and Modeling in Horizontal Annular Flows,"

PhysicochemicalHydrodynamics,Vol. 6, No.1/2, pp. 197-206, 1985 (with T.F.

Lin, O.C. Jones, Jr., R.C. Block and M. Murase).

"The Development of a Closed Form Analytical Model for the Stability Analysis of Density-Wave Oscillations in Boiling Water Nuclear Reactors," Nucl. Eng. and Design, 92, No. 2,1986 (with G.C. Park, M. Becker, M. Podowski and S.J. Peng).

"A Stability Analysis of Ventilated Boiling Channels," J. Nucl. Eng. and Design, 93, No. 1, 1986 (with M. Podowski and R.P. Taleyarkhan).

"BWR Linear Stability Analysis," J. Nucl Eng. and Design,93, No. 1, 1986 (with S.J. Peng and M. Podowski).

"Advances in the Analytical Modeling of Linear and Nonlinear Density-Wave http://www.rpi.edu/-laheyr/laheyvita.htm I 9/8/2010

Dr. Richard T. Lahey Page 14 of 6 1 Instability Modes," Journalof NuclearEngineeringand Design, 95, pp. 5-34, 1986.

"Current Understanding of Phase Separation Mechanisms in Branching Conduits,"

Journalof NuclearEngineeringand Design,95, 1986.

."Horizontal Annular Flow Measurements Using Pulsed Photon Activation and Thickness Distribution Modeling," Journalof NuclearEngineeringand Design,

-95, 1986 (with T.F. Lin, R.C. Block, O.C. Jones, Jr. and M. Murase).

"The Measurement of Phase Distribution in a Triangular Conduit," Int. J. of Multiphase Flow,12, No. 3,405-425, 1986 (with S. Sim).

"The Virtual Mass and Lift Force on a Sphere in Rotating and Straining Flow," J.

of Multiphase Flow Vol. 13, No. 1, pp. 113-121, 1987 (with D.A. Drew).

"3-D Turbulence Structure and Phase Distribution Measurements in Bubbly Two-Phase Flows," InternationalJournalof Multiphase Flow,Vol. 13, No. 3, pp.

327-343, 1987 (with S.K. Wang, S.J. Lee and O.C. Jones, Jr.).

"An Experimental Investigation of BWR/4 Long-Term Cooling with either Intact or Broken Jet Pumps," Journalof NuclearEngineeringand Design, Vol. 99, pp.

391-402, 1987 (with M. Fakory).

"An Experimental Study of Two-Dimensional Phase Separation Phenomena,"

InternationalJournalof Multiphase Flow,Vol. 13, No. 3, pp. 327-344, 1987 (with K.M. Bukhari)..

"The Effect of Fuel Rod Dynamics on BWR Stability Margin," Journalof Nuclear Engineeringand Design,Vol. 99, pp. 5-14, 1987 (with R. Taleyarkhan and M.Z.

Podowski).

"A Linear Model to Study Fluid Dynamic Instabilities in Boiling Channels due to Density Oscillations," InternationalJournalof Heat & Technology, Vol. 5, No.

3.4, 1987 (with F,. DAuria, N. DeSanctis, P. DiMarco and M. Podowski).

"An Investigation of the Propagation of Pressure Perturbations in Bubbly Air/Water Flows," Journalof Heat Transfer Vol. 110, 494-499, 1988 (with A.. Ruggles, D.A.

Drew and H. A. Scarton).

"A Study on Single and Two-Phase Pressure Drop in Branching Conduits, "Int. J.

of Experimental Thermal andFluid Science, Vol. 1, No. 2,1988 (with S.T.

Hwang).

"Phase Separation in Dividing Two-Phase Flows," Int. J. of Multiphase Flow, Vol. 14, No. 4,1988 (with S.T. Hwang and H. Soliman).

"The Prediction of Two-Phase Turbulence and Phase Distribution Phenomena Using a k-Epsilon Model, JapaneseJournalof Multiphase Flow, Vol. 3, No. 4, 335-368, 1989 (with S.J. Lee and O.C. Jones, Jr.).

http://www.rpi.edu/-Iaheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 15 of 61 "An Experimental Investigation of Phase Distribution in an Eccentric Annulus,"

Int. J. of MultiphaseFlow Vol. 15, No. 3, 4470457, 1989 (with K. Ohkawa).

"Phase Separation in Impacting Wyes and Tees," Int. J. of MultiphaseFlow, Vol. 15, No. 6, 965-976, 1989 (with S.T. Hwang and H. Soliman).

"An Analysis of Stability and Oscillation Modes in Boiling Multichannel Loops Using Parameter Perturbation Methods," InternationalJournalof Heat and Mass Transfer,Vol. 32, No. 11, pp. 2055-2064, 1989 (with A. Clausse and M.

Podowski).

"The Relationship Between Standing Waves, Pressure Pulse Propagation and Critical Flow Rate in Two-Phase Mixtures," Journalof Heat Transfer, Vol. 111, 467-473, 1989 (with A.E. Ruggles and D.A Drew).

"Derivation of Constitutive Equations for Interfacial Force and Reynolds Stress for a Suspension of Spheres Using Ensemble Averaging," Journalof Chemical Engineering Communications,Vol. 86, pp. 43-54, December 1989 (with G.

Arnold and D.A. Drew).

"A Lumped Parameter Model for Linear and Nonlinear Analysis of Excursive and Density-Wave Instabilities in Boiling Channels," EnergiaNucleare, Vol. 6, No. 3, pp. 53-59, September-December, 1989 (with P. DiMarco, A. Clausse and D.A.

Drew).

"A Nodal Analysis of Instabilities in Boiling Channels," Heat& Technology, Vol.

8, No. 1-2, 1990 (with P. DiMarco, A. Clausse and D.A. Drew).

"Statistical Analysis of Turbulent Two-Phase Pipe Flow," Journalof Fluids Engineering,Vol. 113, pp. 89-95, 1990 (with S.K. Wang, S.J. Lee and O.C.

Jones, Jr.)

"The Prediction of Two-Phase Turbulence and Phase Distribution Phenomena Using a Reynolds Stress Model," Journalof Fluids Engineering,Vol. 112, pp.

107-113, 1990 (with M. Lopez de Bertodano, S.J. Lee and D.A. Drew).

"Void Wave Dispersion in Bubbly Flows," NuclearEngineeringandDesign,Vol.

121, No. 1, pp. 1-10, 1990 (with J-W. Park and D.A. Drew and A. Clausse)

"An Assessment of Multiphase Flow Models using the Second Law of Thermo-Dynamics," Int.J. ofMultiphaseFlow,Vol. 16, No. 3, pp. 481-494, 1990 (with G.

Arnold and D.A. Drew).

"The Influence of*Flow Development on Subcooled Boiling," Int.

Communicationsin Heat & Mass Transfer,Vol. 17, No. 5, pp. 545-554, 1990 (with A. Clausse).

"The Analysis of Phase Separation and Phase Distribution Phenomena using Two-Fluid Models," Nuclear Engineering& Design,Vol. 122, pp. 17-40, 1990.

http://www.rpi.edu/-Iaheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 16 of 61 "Some Supplemental Analysis Concerning the Virtual Mass and Lift Force on a Sphere in a Rotating and Straining Flow," InternationalJournalof Multiphase Flow,Vol. 16, No. 6, pp. 1127-1130, 1990 (with D.A. Drew).

"An Application of Fractal and Chaos Theory in the Field of Two-Phase Flow and Heat Transfer," W&Scaronrme-und Stoff&Yumibertragung,vol. 26, pp. 351-363, 1991.

"Void Wave Propagation Phenomena in Two-Phase Flow," AIChE.Journal, Vol.

37, No. 1, pp. 123-135, Jan. 1991.

"The Use of Fractal Techniques in Flow Regime Identification," Int. J. Multiphase Flow,Vol. 17, No. 4, pp. 545-552, 1991 (with F. Franca, M. Acikgoz and A.

Clausse).

"A Contribution to Mathematical Modeling of Bubbly/Slug Flow Regime Transition," Chemical EngineeringCommunications, Vol. 102, pp. 69-85, April 1991 (with S. Valenti, A. Clausse and D.A. Drew).

"The Analysis of Periodic and Strange Attractors During Density-Wave Oscillations in Boiling Flows," J. of Chaos, Solitons and Fractals,Vol. 1, No. 2, pp. 167-178, 1991 (with A. Clausse).

"An Analysis of Non-Linear-Instabilities in Boiling Systems," Journalof Dynamics and Stability of Systems, Vol. 6, No. 3, pp. 191-216, 1991 (with P. DiMarco and A. Clausse).

"An Analysis of the Eigenvrluessof Bubbly Two-Phase Flows,." Chemical EngineeringCommunications,Vol. 106, pp.93-117, August 1991, (with T.C.

Haley and D.A. Drew).

"Analysis of Phase Distribution in Fully Developed Laminar Bubbly Two-Phase Flow," InternationalJournalof MultiphaseFlow,Vol. 17, No. 5, pp. 635-652, 1991 (with S.P. Antal and J.E. Flaherty).

"A Contribution to the Prediction of Phase Separation in Branching Conduits,"

ChemicalEngineeringCommunications,Vol. 111, pp.79-105, 1992 (with R.H.

Kimpland, B.J. Azzopardi and H.M. Soliman).

"Global Volumetric Phase Fractions in Horizontal Three Phase Flows," AIChE Journal,Vol. 38, No. 7, pp. 1049-1059, 1992 (with M. Acikgoz and F. Franca).

"An Experimental Study of Three-Phase Flow Regimes," Int. J. Multiphase Flow, Vol. 18, No. 3, pp. 327-336, 1992 (with F. Franca and M. Acikgoz).

"On the Development of Multidimensional Two-Fluid Models for Vapor/Liquid Two-Phase Flows," ChemicalEngineeringCommunications,Vol. 118, pp. 125-140, Nov/Dec. 1992.

http://www.rpi.edu/-laheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 17 of 61 "On the Use of Drift-Flux Techniques for the Analysis of Horizontal Two-Phase Flows," Int. J. Multiphase Flow,Vol. 18, No. 6, pp. 787-801, 1992.

"A Characteristic Analysis of Void Waves Using Two-Fluid Models," Nuclear Engineering& Design,Vol. 139, No. 1, pp. 45-58, 1993 (with T.C. Haley and D.A. Drew).

"An Experimental Study on Air Carryunder Due to a Plunging Liquid Jet," Int. J.

Multiphase Flow,Vol. 19, No. 2, pp. 281-294, 1993 (with F. Bonetto).

"Phase Distribution in Complex Geometry Conduits," Nuc. Eng. & Design, Vol.

141, Nos. 1&2, pp. 177-201, 1993 (with M. Lopez de Bertodano and 0.C. Jones, Jr.)

"Buoyantly-Driven Two-Phase Countercurrent Flow in Liquid Discharge From a Vessel With an Unvented Gas Space," Nuc. Eng. & Design, Vol. 141, Nos. 1&2, pp. 237-248, 1993 (with Christopher E. Henry, Robert E. Henry and S. George Bankoff).

"The Analysis of Void Waves in Two-Phase Flow," Nuc. Eng. & Design, Vol.

141, Nos. 1&2, pp. 203-224, 1993 (with J-W. Park and D.A. Drew).

"Interfacial Area Density, Mean Radius and Number Density Measurements in Bubbly Two-Phase Flow," NuclearEngineeringand Design, Vol. 142, pp. 341-351, 1993 (with S. Kalkach-Navarro, D.A. Drew and R. Meyder).

"Development of a k-Epsilon Model for Bubbly Two-Phase Flow, Trans. ASME, J.

of Fluids Engineering,Vol. 116, No. 1, pp. 128-134, 1994 (withM. Lopez de Bertodano and O.C. Jones).

"Phase Distribution in Bubbly Two-Phase Flow in Vertical Ducts," Int. J.

Multiphase Flow, Vol. 20, pp. 805-818, 1994 (with M. Lopez de Bertodano and 0.C. Jones).

"Phase Distribution and Turbulence Structure for Solid/Fluid Upflow in a Pipe," Int.

J. Multiphase Flow,Vol. 20, No. 3, pp. 453-479, 1994 (with A. Alajbegovic, A.

Assad and F. Bonetto).

"Turbulent Bubbly Two-Phase Flow Data in a Triangular Duct," Nuclear Engineeringand Design,Vol. 146, pp. 43-52, 1994 (with M. Lopez de Bertodano and 0.C. Jones).

"The Analysis of a Plunging Liquid Jet The Air Entrainment Process," Chemical EngineeringCommunications,Vol. 130, pp. 11-29, 1994, (with F. Bonetto and D.A. Drew).

"The Measurement of Void Waves in Bubbly Two-Phase Flows," Nuclear Engineeringand Design,Vol. 149, pp. 37-52, 1994 (with J-W. Park and D.A.

Drew).

http://www.rpi.edu/-Iaheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 18 of 61 "Analysis of the Bubbly/Slug Flow Regime Transition," Mark Mills Award Paper, Nuclear Engineeringand Design, Vol. 151, pp. 15-39, 1994 (with S. Kalkach-Navarro and D.A. Drew).

"Benchmarking and Qualification of the N UFREQ-NPW Code for Best Estimate Prediction of Multichannel Core Stability Margins," NuclearEngineeringand Design,Vol. 151, pp. 157-171, 1994 (with R. Taleyarkhan, F.A. McFarlane and M.Z. Podowski).

"The Thermal-Hydraulics of Aseptic Food Processing," Int. J. Heat & Mass Transfer,Vol. 37, Suppl.-1, pp. 233-239, 1994 (with M. Millies and D.A. Drew).

"On the Different Forms of Momentum Equations and on the Intra- and Interphase Interaction in the Hydromechanics of a Monodispersed Mixture," Chemical EngineeringCommunications,Vol. 141-142, pp. 287-302, 1996, (with R.I.

Nigmatulin and D.A. Drew).

/

"A First Order Relaxation Model for the Prediction of the Local Interfacial Area Density in Two-Phase Flows," Int. J. Multiphase Flow,Vol. 22, No. 6, pp. 1073-1104,1996 (with M. Millies and D.A. Drew).

"A Method for Superhigh Compression-Induced Temperatures in a'Gas Bubble Using Non-Periodic Resonance Liquid Pressure Forcing," ChemicalEng.

Communications, Vols. 152-153, pp. 17-39, 1996, (with R.I. Nigmatulin, V. S.H.

Shagapov and N.K. Vakhitova).

"The Analysis of Chaotic Instabilities in Boiling Systems," NuclearEngineering andDesign,Vol. 167, No. 3, pp. 307-334, 1997 (with C.J. Chang).

"The Modeling of Core Melting and In-Vessel Corium Relocation in the APRIL Code," Nuclear Engineeringand Design,Vol. 177, Nos. 1-3, pp. 265-283, 1997 (with S.W. Kim, M.Z. Podowski and N. Kurul).

"The Resonant Supercompression and Sonoluminescence of a Gas Bubble in a Liquid Filled Flask," Chemical Eng. Communications,Vol. 168, 145-171, 1998 (with -R.I. Nigmatulin, I.S. Akhatov and N.K. Vakhitova).

"The Interaction of Background Ocean Air Bubbles with a Surface Ship," Int. J.

Num. Meth. Fluids,Vol. 28, pp. 571-600, 1998 (with P.M. Carrica, D. Drew and F. Bonetto).

"The Analysis of Void Wave Propagation in Adiabatic, Monodispersed Bubbly Two-Phase Flows using an Adiabatic, Ensemble-Averaged, Two-Fluid Model,"

Int. J. Multiphase Flow,Vol. 24, No. 7, pp. 1205-1244, 1998 (with J-W. Park and D.A. Drew).

"A Polydisperse Model for Bubbly Two-Phase Flow Around a Surface Ship,"

InternationalJournalof Multiphase Flow,Vol. 25, No. 2, pp. 257- 305, 1999 (with P.M. Carrica, D. Drew, and F. Bonetto).

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Dr. Richard T. Lahey Page 19 of 61 "A Moving-Boundary Nodal Model for the Analysis of the Stability of Boiling Channels," InternationalJournalof Heat& Mass Transfer, Vol. 42, No.

19 ,pp. 3575-3584, 1999 (with V. Garea and D.A. Drew).

"An Analysis of Phase Distribution and Turbulence in Dispersed Particle/Liquid Flows," ChemicalEngineeringCommunications,Vol. 174, pp. 85-1 33, 1999 (with A. Alajbegovic and D.A. Drew).

"On the Use of Nonlinear Filtering, Artificial Viscosity and Artificial Heat Transfer for Strong Shock Computations," Journalof ComputationalPhysics Vol. 153, pp. 575-595, 1999 (with S. Bae).

"Lateral Forces on Spheres in Turbulent Uniform Shear Flow," International Journalof Multiphase Flow Vol..25, Nos. 6-7, 1999 (with F.J. Moraga and F.J.

Bonetto).

"An Experimental Study of Phase Distribution and Turbulence Structure for Solid/Fluid Flow in Horizontal Pipes," Chemical Eng. Communications, Vol.

179, pp. 149-179, 2000 (with A. Assad and F. Bonetto).

On the Forced Oscillations of a Small Gas Bubble in a Spherical Liquid-Filled Flask, J. FluidMech., Vol. 414, pp. 47-73, 2000 (with R.I. Nigmatulin, I. Sh.

Akhatov, and N.K. Vakhitova).

"An Experimental Study of Dispersed Liquid/Liquid Two-Phase Upflow in a Pipe,"

ChemicalEngineeringCommunications,Vol. 182, pp. 47-73, 2000. (with T.

Nigmatulin, F. Bonetto, A. Larreteguy, and J. McQuillen).

"Role of Very High-Frequency Excitation In Single Bubble Sonoluminescence,"

PhysicalReview-E, Vol. 62, No. 2, pp. 2233-2237, 2000 (with F. Moraga, R.

Taleyarkhan and F. Bonetto).

The Analysis of Two-Phase Flow and Heat Transferusing a Multidimensional, Four Field, Two-Fluid Model, Nuc. Eng. & Design ,Vol. 204, Nos. 1-3 , pp. 29-44, 2001 (with D. A. Drew).

"Evidence for Nuclear Emissions During Cavitation", Science, Vol. 295, pp.

1868-1873, 2002 (with Taleyarkhan et al).

"The Relationship Between the Method of Acoustic Excitation and the Stability of Single Bubble Sonoluminescence for Various Noble Gases," ChemicalEng.

Communications, Vol. 189, pp. 786-802,2002 (with G. Delgadino and F.

Bonetto).

"Deuterium-Deuterium Nuclear Fusion during Cavitation", Heritageof the Academy of Sciences - Republic of Bashkortostan, Vol.7 No.4, pp.3-25,2003 (with R. Nigmatulin and R. Taleyarkhan)

"Assessment of Turbulent Dispersed Models for Bubbly Flows", Int. J.

Multiphase Flow Vol.29 ,No.4,pp.655-673, 2003 (with F. Moraga, A.

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Dr. Richard T. Lahey Page 20 of 61 Larreteguy and D. Drew).

"The Modeling of Lift and Dispersion Forces in Two-Fluid ModeI Simulations of a Bubbly Jet", J. Fluids Engineering,Vol. 126(4), 2004 (with M. Lopez de Bertodano, F. Moraga and D.A. Drew).

"The Evidence for Nuclear Emissions during Acoustic Cavitation Revisited", J. of Powerand Energy , Vol. 218(A), 345, 2004 (with R.I. Nigmatulin and R.P.

Taleyarkhan).

"An Analytical Study on Interfacial Wave Structure Between the Liquid Film and Gas Core in a Vertical Pipe", Int. J. Multiphase Flow,.Vol. 30, 829, 2004 (with F. Inada and D.A. Drew).

"Additional Evidence of Nuclear Emissions during Acoustic Cavitation," Physical Review-E, Vol. 69, 036109, 2004 (with R.P. Taleyarkhan, J. Cho, C. West, R.Nigmatulin, R. Block).

"On the Multidimensional Analysis of Two-Phase Flows," Multiphase Science &

Technology, Vol. 15 (1-5), 1, 2004 (with D. A. Drew).

"Update and Clarifications on Experimental Studies for Nuclear Emissions during Acoustic Cavitation," J. Acous. Soc. Am., Vol. 113, 2205, 2004 (with R.

Nigmatulin, R. P. Taleyarkhan, C. West).

"Update and Clarifications on Experimental Studies for Nuclear Emissions during Acoustic Cavitation," J. Acous. Soc. Am., Vol. 113, 2223, 2004 (with R. P.

Taleyarkhan, C. West, J. Cho, R. Block, R. Nigmatulin).

"Sonoluminescence and the Search for Sonofusion," IEEESpectrum, May issue ,2005 (with R. Taleyarkhan, R. Nigmatulin).

"The Simulation of Multidimensional Multiphase Flows," Nuc. Eng. & Design, Vol.235( 10-12),1043, 2005.

"The Analysis of Interfacial Waves," Nuc. Eng. & Design,Vol. 235 (10-12),1283, 2005 (with A. Galimov, D. A. Drew).

"Analysis of Void Wave Propagation and Sonic Velocity using a Two-Fluid Model", Multiphase Science & Technology, Vol. 17 Issue 4, 293-320, 2005 (with J. Yin, P. Tiwari).

"The Analysis of Linear and Nonlinear Bubble Cluster Dynamics" , Multiphase Science & Technology, Vol.17 Issue 3, 225-256,2005 (with I. Akhatov, R.

Nigmatulin).

"The Design of Acoustic Chambers for Bubble Dynamics Research", Multiphase Science & Technology, Vol. 17 Issue 3, 257-291 , 2005 (with S, Cancelos, F.

Moraga, P. Bouchilloux).

http://www.rpi.edu/-laheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 21 of 61 "Bubble Nuclear Fusion Technology - Status and Challenges" , Multiphase Science & Technology, Vol. 17 Issue 3, 191-224 ,2005 (with R. P. Taleyarkhan, R. Nigmatulin).

"The Theory of Supercompression of Vapor Bubbles and Nano-Scale Thermonuclear Bubble Fusion", Physics of Fluids, Vol. 17 ,107106-1, 2005 (with R. Nigmatulin, I. Akhatov, A. Topolnikov, R. Bolotnova, N. Vakhitova).

"Computation of Incompressible Bubble Dynamics with a Stabilized Level Set Method", ComputerMethods in Applied Mechanics and Engineering,Vol. 194 (42-44), 4565-4587,October ,2005 ( with S. Nagrath and K. Jansen).

"Nuclear Emissions During Self-Nucleated Acoustic Cavitation", Physical Review Letters, Vol.96, 034301-1, 2006( with R. Taleyarkhan ,C. West, R, Nigmatulin ,R. Block, Y. Xu).

"Modeling Wall-Induced Forces on Bubbles for Inclined Walls", Multiphase Science & Technology, Vol. 18 Issue 2, 111-133,2006 (with F. Moraga, S.

Cancelos).

"An Analysis of Interacting Instability Modes", MultiphaseScience &

Technology, Vol. 18 Issue 4, 305-333, 2006 (with J. Yin, M. Podowski, M.

Jensen).

"A Center-Averaged Two-Fluid Model for Wall-Bounded Bubbly Flows", J.

Computers and Fluids,Vol.35 (4), 429-461, 2006 (with A. Larreteguy, F.

Moraga, D. A. Drew).

"Hydrodynamic Simulationi of Air Bubble Implosion using a FEM-based Level Set Approach", J. Comp. Physics,Vol.215 (1),98-132,2006 (with S. Nagrath, K.

Jansen, I. Akhatov).

Response to the PRL paper of Naranjo et al.", Phys. Rev. Left. j Vol. 97, 149404 , 2006 (with R. Taleyarkhan, R. Block, R. Nigmatulin and Y. Yu).

"Response to the PRL paper of A. Lipson", Phys. Rev. Left. , Vol.97 , 149402, 2006 (with R. Taleyarkhan, R. Block, R. Nigmatulin and Y. Yu).

"The Effect of Buoyancy on Phase Distribution in Dispersed Two-Phase Flows",

Chemical Engineering Communications, Vol.194, 507-536, 2007 (with M.

Singhal, D.A. Drew).

"Sonofusion Technology Revisited" , Nuclear Engineering & Design, Vol.237 (15-17), 1571-1585, 2007 (with R.P.Taleyarkhan., R. I. Nigmatulin).

"A Sub-Grid Air Entrainment Model for Breaking Bow Waves and Naval Surface Ships", J. Computers and Fluids , Vol.37, 281-298, 2007 (with F. J. Moraga, P.

M. Carrica, D.A. Drew).

"Modeling , Analysis and Prediction of Neutron Emission Spectra from Acoustic http://www.rpi.edu/-Iaheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 22 of 61 Cavitation Bubble Fusion Experiments" ,Nuc. Eng. & Design, Vol.238, 2779-2791 ,2008 (with R.P. Taleyarkhan, J. Lapinskas, Y. Xu, J.S. Cho, C. D. West, R.C. Block, R. I. Nigmatulin).

"Stability Analysis of a Uniformly Heated Channel with Supercritical Water", Nuc.

Eng. & Design, Vol.238(8), 1930-1939, 2008 (with T. Ortega-Gomez, A. Class, T. Schulenberg).

"A Spectral Turbulent Cascade Model for Single and Two-Phase Uniform Shear Flows", J. of Turbulence, Vol. 9 (26), 1-18, 2008 (with L.A. Bolotnov, D.A. Drew, K. E. Jansen, A.A. Oberai).

"Turbulent Cascade Modeling of Single and Bubbly Two-Phase Turbulent Flows",

International Journal of Multiphase Flow, Vol.34(12), 1142-1151, 2008 (with I.

A. Bolotnov, D. A. Drew, K. E. Jansen).

"On the Computation of Multiphase Flows", J. Nuclear Technology, Vol.167,1-17, 2009.

"On the Direct Numerical Simulation of Two-Phase Flows", Nuc. Eng. & Design, Vol.239/5, 867-879, 2009.

"Direct Numerical Simulationof Turbulent Channel Flows using a Stabilized Finite Element Method", J. Computers & Fluids, Vol.38(4) ,924-938, 2009 (with A.

Trofimova, A. E. Tejada-Martinez, K. E. Jansen).

"Spectral Cascade Modeling of Turbulent Flow in a Channel", Japanese J. of Multiphase Flow, Vol.23(2), 190-204, 2009 (with I. Bolotnov, A. Oberai, D. Drew, K. Jansen).

"A Quantitative Sub-Grid Air Entrainment Model for Bubbly Flows", J.

Computers & Fluids, Vol. 39, 77-86, 2009 (with Jingsen Ma, A. Oberai, D.

Drew, F. Moraga).

"Spectral Analysis of Turbulence based on the DNS of a Channel Flow", J.

Computers & Fluids , Vol.39, 640-655, 2010.

"Parallel Adaptive Simulation of a Plunging Liquid Jet", ýActa Mathematica Scientia, Vol. 30(2) Series-B, 522-538, March, 2010 (with A.Y. Galimov, 0. Sahni, M. Shephard, D.A. Drew, K.E. Jansen).

"An Analysis of Interacting Instability Modes in a Phase Change- System", in press, Nuc. Eng. & Design, 2010 (with W. Schlichting , M. Podowski).

"The Effect of Acoustically-Induced Cavitation on the Permeance of a Bullfrog Uinary Bladder", in press, J. Acoustical Society of America, 2010 (with Silvina Cancelos, Francisco Moraga, William shain, Robert Parsons).

"Recent Advances in Acoustic Inertial Confinement Fusion" , submitted , Journal of Fusion Energy, 2009 (with R. Taleyarkhan , R. Nigmatulin).

http://www.rpi.edu/-laheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 23 of 61 "A Comprehensive Sub-Grid Air Entrainment Model for RaNS Modeling of Bubbly Flows Near the Free Surface", submitted, J. Computers & Fluids, 2010 (with Jingsen Ma ,A. Oberai, D. Drew, M. Hyman).

"Evolution of Distortions from Spherical of a Cavitation Bubble during Acoustic Supercompression", submitted, J. Fluid Mechanics , 2010 (with R. I..Nigmatulin, A.A. Aganin, M.A. Ilgamov, D. Yu. Toporkov, R.I. Taleyarkhan).

"A Two-Way Coupled Polydispersed Simulation of Bubbly Flow Beneath a Plunging Liquid Jet", submitted, J.-Fluids Engineering, 2010 (with Jingsen Ma.

Assad Oberai, Donald Drew).

"Detached Direct Numerical Simulations of Turbulent Two-Phase Bubbly Channel Flow"., submitted, Int. J. Multiphase Flow, 2010, (with Igor A. Bolotnov, Kenneth E. Jansen, Donald A. Drew, Assad A. Oberai, Michael Z. Podowski).

Refereed Publications (Proceedings)

"Mixing, Flow Regimes, and Void Fraction for Two-Phase Flow in Rod Bundles,"

ASME Symposium Volume, Two-Phase Flow and Heat Transfer in Rod Bundles, November 1969 (with A. Schraub).

"Transient Flow Measurements with Sharp-Edged Orifices," ASME Paper 71-FE-30, 1971 (with B. Shiralkar).

"Diabatic Local Void Fraction Measurements in Freon-1 14 with a Hot Wire Anemometer," ANS Transactions,15, No. 2, November 1972 (with B. Shiralkar).

"A Langrangian Analysis of Two-Phase and Nuclear-Coupled Density-Wave Oscillations," Paper .B5.9, Proceedings of the Fifth International Heat Transfer Conference, Tokyo, 1974 (with G. Yadigaroglu).

"The Effect of Reduced Clearance and Rod Bow on Critical Power in Full-Scale Simulations of 8x8 BWR Fuel," ASME preprint 75-HT-69, 1975 (with.B. Matzner).

"16 N Tagging of Water for Transient Flow Measurements," ANS Transactions,27, December 1977 (with R.C. Block, M. Perez-Griffo and U.N. Singh).

"Critical Power in Boiling Water Nuclear Reactor Fuel Bundles," Proceedings of the ANS Topical Meeting on Thermal Reactor Safety, July 1977.

"The Effect of Non-Uniform Axial Heat Flux on Critical Power," Proceedings of the Conference on Heat and Fluid Flow in Water Reactor Safety, University of Manchester, September, 1977 (with J. Gonzalez-Santalo).

"The Status of Boiling Water Nuclear Reactor Safety Technology," ASME http://www.rpi.edu/-laheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 24 of 61 Symposium Volume on Thermal-Hydraulic Aspects of Nuclear Reactor Safety, November 1977.

"An Experimental Technique for the Determination of Steam/Air Fraction," ANS Transactions,27, December 1977 (with N. Saba and G. Krycuk).

"06 N Tagging for Two-Phase Flow Measurements," ANS Transactions, 30, 1978 (with M. Perez-Griffo and R.C. Block).

"Opportunities for University Contributions to BWR Thermal-Hydraulic Technology," ANS Transactions,28, June 1978, San Diego, CA.

"Radial Phase Distribution Mechanisms in Two-Phase flow," Proceedings of the OECD/CSNI Specialists Meeting on Transient Two-Phase Flow," Paris, France, 6/12-14, 1978 (with D.A. Drew and S. Sim).

"A Turbine-Meeting Evaluation Model for Two-Phase Transients," ASME Symposium Volume, Topics /n Two-Phase Flow and Heat Transfer, 1978 (with P.S. Kamath).

"A Mechanistic Subcooled Boiling Model," Proceedings of the 6 th International Heat Transfer Conference, 1978, Toronto, Canada.

"The Development of a High Temperature Optical Void Probe," ANS Transactions, 30, 1978 (with M. Vince and H.E. Breed).

"Development of a Radio-Frequency Local Probe for Void Fraction Measurements, ANS Transactions,30, 1978 (with S. Moreira and G. Krycuk).

"A High Intensity X-Ray System for Stochastic Measurements of Two-Phase Flow," ANS Transactions,30, 1978 (with G. Krycuk and B.K. Malaviya).

"The Side-Scatter Gamma Technique for Local Density Measurements,"

ANS Transactions, 30, 1978 (with R.R. Gay and S. Schell).

"The Development of an Optical Digital Interferometer," Proceedings of the 2 nd Multi-Phase Flow and Heat Transfer Symposium-Workshop, 4/16-18, 1979, Miami, FL (with M.A. Vince and G. Krycuk).

"The Analysis of Phase Distribution in Fully Developed Two-Phase Flows,"

Proceedings of the 2 nd Multi-Phase Flow and Heat Transfer Symposium-Workshop, 4/16-18, 1979, Miami, FL (with D.A. Drew)

"An Evaluation of Interfacial Drag Models for Bubbly Two-Phase Flows," ASME Symposium Volume on Interfacial Transport Phenomena, 1979 (with S. Sim and D.A. Drew).

"The Analysis of Dynamic Bias in Gamma Densitometer Measurements," ANS Transactions,32, 1979 (with T.J. Honan).

http://www.rpi.edu/- laheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 25 of 61 "The Evaluation of Static Error in Gamma Densitometry," ANS Transactions, 32, 1979 (with T.J. Honan).

"Scaling of the RPI Parallel Channel Effects Experiment," ANS Transactions, 32, 1979 (with W.M. Conlon).

"Current Light Water Nuclear Reactor Safety Concerns," ANS Transactions, 32, 1979.

"Dynamic Bias in Side-Scatter Gamma Density Measurements," ANS Transactions, 323, 1979 (with R.R. Gay).

"An Analytic Derivation of a Subchannel Void-Drift Model," ANS Transactions, 33, 1979 (with D.A. Drew).

"Dynamic Analysis of a Drag-Disk in Transient Two-Phase Flow," ANS Transactions, 33, 1979 (with P. Kamath).

"The Effect of Heater Rod Dynamics on CCFL Mechanisms," ANS Transactions, 33,1979 (with K. Ohkawa).

"Modeling of Two-Phase Flow Manometric Oscillations," Proceedings of the 1 1 th Annual Pittsburgh Conference on Modeling and Simulation, University of Pittsburgh, 1980 (with C.N. Shen and R.P. Taleyarkhan).

."An Assessment of Current LWR Thermal-Hydraulic Safety Concerns,"

Proceedings of 5th Indian Heat & Mass Transfer Conference, Hyderabad, India, 1980.

'An Analytical Approach to the Evaluation of Water Hammer Phenomena," ANS Transactions,35, 1980 (with D.A. Drew).

"A Mixing Length Model for Fully-Developed Turbulent Two-Phase Flow," ANS Transactions,35, 1980 (with D.A. Drew).

"The Measurement of Local Void Fraction with a Side-Scatter Gamma Technique," Proc. 2 6 th International Symposium of the Instrument Society of America, Seattle, WA, May 1980 (with R.R. Gay and K. Ohkawa).

"The Analysis of a Drag-Disk in Transient Two-Phase Flow," Proceedings of the ANS/ASME Topical Meeting on Reactor Thermal-Hydraulics, NUREG/CP-0014, Saratoga Springs, NY, October 1980 (with M. Perez-Griffo and R.C. Block).

"Basic Two-Phase Flow Measurements Using 16 N Tagging Techniques,"

Proceedings of the ANS/ASME Topical Meeting on Reactor Thermal-Hydraulics, NUREG/CR-0014, Saratoga Springs, NY, October 1980 (withM. Perez-Griffo and R.C. Block).

"Analysis of the Error in Instantaneous Void Fraction Measurements by a Dual-http://www.rpi.edu/-Iaheyr/laheyvita.html 9/8/2 010

Dr. Richard T. Lahey Page 26 of 61 Beam X-Ray Technique," ANS Transactions,34, 1980 (with B.K. Malaviya).

"The Analysis of LOFT Drag Disk Turbine. Meter Rakes," ANS Transactions, 34, 1980 (with P.S. Kamath).

"Derivative Signal Thresholding for a Local Void Impedance Probe," ANS Transactions,34, 1980 (with M. Vince).

"Flow Regime Identification Using a High Intensity X-Ray System," ANS Transactions,34, 1980 (with M. Vince).

"Involvement in Nuclear Public Information Activities at RPI," ANS Transactions, 34, 1980 (with B.K. Malaviya, H. Burdock and R.M. Ryan).

"The Analysis of.Two-Phase Level in a PWR Core During Conditions of Severely Reduced Liquid Mass Inventory," Proceedings of the ICHMT Seminar, Dubrovnik, Yugoslavia, 1980.

"The Effect of Gravity and Friction on the Stability of Boiling Flow in a Channel,"

AIChE Symposium Series #199, Vol. 76,1980 Vol. 11, 59-79, 1981 (with J-L.

Achard and D.A. Drew).

"The Analysis of Vent Clearing," ANS Transactions,35, 1980 (with Z.M. Khalid).

"The Effect of Radial Nonuniformity on BWR Stability Margins," ANS Transactions, 35, 1.980 (with G. Park and M. Becker).

"Non-Uniform Tagging and Flow Structure Effects in PNA Measurements,"

ANSTransactions, 35, 1980 (with M. Perez-Griffo and R.C. Block).

"Interfacial Dissipation in Two-Phase Flow," ASME Symposium Volume, Basic Mechanisms in Two-Phase F/ow and Heat Transfer, 1980 (with D.A. Drew).

"Analytical Modules for Nuclear Reactor Simulators," Proceedings of USNRC/EPRI Symposium on Simulation Methods for Nuclear Power Systems, EPRI Report WS-81-212, 1981.

"The Effect of Virtual Mass on the Prediction of Critical Flow," Proceedings of 3 rd CSNI Specialists Meeting on Transient Two-Phase Flow, Cal. Tech., 1980.

"The Adaptation of a Non-Equilibrium Vapor Generation Model into MAYU4a,"

ANS Transactions,38, 1981 (with C.E. Hardie and R.R. Gay).

"The Analysis of System Pressure Drop Characteristics During Flow Boiling," ANS Transactions,38, 1981.

"Stability Analysis for a Nonuniformly Heated Boiling Channel," ANS Transactions, 38, 1981 (with R. Taleyarkhan and M. Podowski).

"Thermal-Hydraulic Instrumentation for LWR Experiments A Review," ANS http://www.rpi.edu/-laheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 27 of 61 Transactions,38, 1981.

"A State Variable Model and Stability Criterion for Density-Wave Oscillations in Boiling Water Reactors," Proceedings of the 1 2 th Annual Pittsburgh Conference on Modeling and Simulation," University of Pittsburgh, 4/30-5/1, 1981 (with C.N.

Shen and J. Balaram).

"A State Variable Formulation of Density-Wave Oscillation in Boiling Water Reactors," ANS Transactions,36, 1981 (with C.N. Shen and J. Balararn).

"A Mechanistic Analysis of LOFT Pulsed Neutron Activation Data," ANS Transactions, 38, 1981 (with M.L. Perez-Griffo and R.C. Block).

"An Analytical Solution for BWR Channel Flow Split," ANS Transactions, 39, 1981 (with R. Beauman).

"Flow Regime Effects on Integral and Local Slip in Vertical Two-Phase Flows,"

ANS Transactions,39,1981 (with M.A. Vince).

"An Interactive Graphics Based Multi-Purpose Nuclear Power Plant Simulator,"

ANS Transactions,39,1981 (with F.E. Wicks).

"A Review of Some Selected Nonintrusive Nuclear and Optical Techniques for the Determination of Void Fraction, Flow Regime and Two-Phase Flow Rate," ANS Transactions,39, 1981.

"Thermal-Hydraulic Stability of Interconnected Boiling Channels," ANS Transactions,39, 1981 (with R. Taleyarkhan and M. Podowski).

"The Use of Microprocessors for the Evaluation of the Thermal-Hydraulic Stability of Boiling Systems," ANS Transactions,39, 1981.

"An improved Model for the Stability Analysis of BWRs," ANS Transactions, 39, 1981 (with G.C. Park, J.K. Park, M. Becker and M. Podowski).

"The Effect of Heater Wall Dynamics on Density-Wave Oscillations in a Boiling Channel," Proc. 7 th International Heat Transfer Conference, Munich, Germany, 1982 (with R. Taleyarkhan and M. Podowski).

"Ventilated Channel Instability Analysis," ASME Preprint 82-WA/HT-3, 1982 (with R. Taleyarkhan and M. Podowski).

"The Modeling of Density-Wave Oscillations in Boiling Water Nuclear Reactors,"

Proc. NATO Advanced Workshop on Two-Phase Flows and Heat Transfer,"

August 31-September 3, 1982, Spitzingsee, Germany (with G.C. Park, M.

Podowski and M. Becker).

"Density-Wave Oscillations," Proc. 9 th U.S. National Congress of Applied Mechanics, Cornell University, June 1982 (with M. Podowski)..

http://www.rpi.edu/-laheyr/laheyvita.htm I 9/8/2010

Dr. Richard T. Lahey Page 28 of 61 "Some Physical Problems Involving Large Moving Gradients," Proc. of 1 0 th IMACS World Congress on Systems Simulation and Scientific Computation, Concordia University, Montreal, Canada, August 1982.

"An Analysis of BWR Flow Transients," ANS Transactions,41, 1982 (with S. Peng and D.A. Drew).

"An Analysis of a Hypothetical BWR Inlet Flow Blockage," ANS Transactions, 41, 1982 (with M.E. Nissley and R.R. Gay).

"On the Relationship Between Ledinegg and Density-Wave Instability Analysis,"

ANS Transactions,41, 1982 ý(with G. Yadigaroglu).

"The Stability Analysis of BWR Recirculating Loops," ANS Transactions, 41, 1982 (with G.C. Park, M. Podowski and M. Becker).

"Virtual Mass Effects in Two-Phase Flows A Review," ANS Transactions, 41, 1982.

"The Interaction of Neutronics and Thermal-Hydraulics in the Evaluation of BWR Stability," Proc. ANS Topical Meeting on Advances in Reactor Physics and Core Thermal-Hydraulics, 1982 (with M. Becker, J.K. Park, G.C. Park and M.

Podowski).

"Pulsed Neutron Activation for Single- and Two-Phase Flow Measurements,"

Proc. of Institute of Physics Conference on the Neutron and Its Applications, Cambridge, England, Sept. 1982 (with M.L. Perez-Griffo and R.C. Block).

"Mulitivariable Approach to Boiling Water Nuclear Reactor Stability," Proc. 1 3 th Annual Pittsburgh Conference on Modeling and Simulation, 1982 (with J. Balaram and C.N. Shen).

"A Heat Transfer Model for LWR Fuel Rods During Hypothetical Core Meltdown Accidents," ANS Transactions,42, 1982 (with T. Ikeda, M. Podowski and B. Koh).

"Multivariable Stability Margins for Boiling Water Nuclear Reactors," Proc. of 2 1 st IEEE Conference on Decision and Control, Orlando, FL, December 8-10, 1982 (with J. Balaram and C.N. Shen).

"Wave Dispersion Effects in Two-Phase Flow," Proc. of 2 nd International Topical Meeting on Reactor Thermal-Hydraulics, Santa Barbara, CA, January 1983 (with L. Cheng and D.A. Drew).

"The Development of a Nodal Method for the Stability Analysis of Ventilated Boiling Channels," Proc. of 2 nd International Topical Meeting on Reactor Thermal-Hydraulics, Santa Barbara, CA, January 1983 (with R. Taleyarkhan and M.

Podowski).

"Scaling of BWR Parallel Channel Effects," Proc. NRC Meeting on Basic Thermal-http://www.rpi.edu/-laheyr/laheyvita.htmi 9/8/2010

Dr. Richard T. Lahey Page 29 of 6.1 Hydraulic Mechanisms in LWR Analysis, Bethesda, MD, September 1983 (with W.M. Conlon).

"Multichannel Stability Analysis of BWR Recirculating Loops," ANS Transactions, 44, 1983 (with G. Park, M. Becker and M. Podowski).

"Channel-to-Channel Instabilities in Parallel Channel Boiling Systems," ANS Transactions,44, 1983 (with M. Podowski and R.P. Taleyarkhan).

"The Modeling of Heat Transfer in a Degraded BWR Core," AIChE Symposium Series, 79, 1983 (with M.- Podowski and R. Taleyarkhan).

"Annular Two-Phase Flow Measurements in a Horizontal Pipe using the Pulsed Photon Activation Technique," ANS Transactions,45, 1983 (with .O.C. Jones, Jr.,

T.F. Lin and R.C. Block).

"The Analysis of Subcooled Boiling Dynamics in Boiling Water Nuclear Reactors,"

Proc. of ASME/JSME Thermal Engineering Joint Conference, Honolulu, Hawaii, 1983 (with G.C. Park, M. Becker, and M. Podowski).

"An Analysis of Molten Material Relocation and Rubble Bed Formation in Degraded BWR Cores," ASME Symposium Volume, Thermal-Hydraulic Aspects of Nuclear Reactor Safety, 1983 (with M. Podowski and R. Taleyarkhan).

"An Analysis of Feed-and-Bleed Mode of PWR Emergency Core Cooling," ANS Transactions,45, 1983 (with A. Salame-Alfie).

"The Two-Phase Flow Measurements Using a Pulsed-Photon-Activation (PPA)

Technique," Proc. of the IUTAM Symposium on Measuring Techniques in Gas/Liquid Two-Phase Flows, Nancy, France, 1983 (with T.F. Lin, R.C. Block, O.C. Jones, Jr. and M. Murase).

"An Analysis of Density-Wave Oscillations in Ventilated BWR Fuel Rod Bundles,"

Trans. Of the 3 rd Multi-Phase Flow & Heat Transfer Symposium Workshop, 1983, Miami Beach, Florida (with M. Podowski and R. Taleyarkhan).

"NUFREQ-NP: A Computer Code for the Stability Analysis of Boiling Water Reactors," ANS Transactions,46 and 2 nd Proceedings on Nuclear Thermal Hydraulics, Annual Meeting of American Nuclear Society, New Orleans, Louisiana., 1984 (with S.J. Peng and M. Becker).

"The Modeling of Emergency Core Cooling (ECCS) in a Degraded BWR Core,"

ANS Transactions,46 and 2 nd Proceedings on Nuclear Thermal-Hydraulics, Annual Meeting of American Nuclear Society, New Orleans, LA, 1984 (with B.R.

Koh, R.P. Taleyarkhan and M. Podowski).

"Film Thickness and Non-Intrusive Void Fraction Measurements in Horizontal Annular Flows," Proceedings of International Symposium on Two-Phase Annular and Dispersed Flows; Pisa, Italy, 1984 (with T.F. Lin, O.C. Jones, Jr., R.C. Block and M. Murase).

http://www.rpi.edu/-Iaheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 30 of 61 "Local Void Fraction Measurements Techniques in Two-Phase Bubbly Flows Using Hot-Film Anemometry," Proc. 22 ASME/AIChE National Heat Transfer Conference, Niagara Falls, NY, August 5-8, 1984.

"Mathematical Modeling of U-Tube Steam Generator Dynamics for Slow Transients and Small Break Loss-of-Coolant Accidents," Proceedings of International Conference on Power Plant Simulation, Cuernavaca, Mexico, 1984.

"An Analysis of Core Meltdown Accidents for BWRs," Proceedings of the Fifth Int.

Meeting on Thermal Nuclear Reactor Safety, Karlsruhe, Germany, 1984 (with S.H.

Kim, M. Podowski and R.P. Taleyarkhan).

"Mathematical Modeling of U-tube Steam Generator Dynamics for Slow Transients and Small Break Loss-of-Coolant Accidents," Proceedings of 85 Eastern Simulation Conference, Norfolk, VA, March .3-8, 1985 (with J.S. Petzold and M. Podowski).

"Modeling Two-Phase Flow Division at T Junctions," Proc. 2 nd Int. Conf. On Multiphase Flow, BHRA, London, 1985 (with B. Azzopardi and M. Cox).

"The Analysis of Degraded BWR Core Thermal-Hydraulics," ANS Proceedings, 1985 National Heat Transfer Conference, Denver, CO, August 6-9, 1985 (with M.Z. Podowski, S.H. Kim, B.R. Koh and R.P. Taleyarkhan).

"A Stability Analysis of Ventilated Boiling Channels," ANS Proceedings, 1985 National Heat Transfer Conference, Denver, CO, 1985 (with R. Taleyarkhan and M. Podowski).

"BWR Linear -Stability Analysis," ANS Proceedings,1985 National Heat Transfer Conference,. Denver, CO, 1985 (with S.J. Peng and M.Z. Podowski).

"The Hydrodynamic Development Length for Lateral Void Distribution in a Triangular Conduit," ASME Symposium Volume, Multiphase Flow and Heat Transfer, Denver, CO, August 6-9, 1985 (with S.H. Kim).

"An Assessment of the Severe Core Damaged Predictive Capabilities using MELRPI," Proceedings of the Third International Topical meeting on Reactor Thermal-Hydraulics, Newport, RI, October 15-18, 1985 (with S.H. Kim and M.Z.

Podowski).

"An Analytical Model for the Prediction of Two-Phase Level During Bottom Reflooding of a Heated Channel," Proceedings of the Third International Conference on Nuclear Reactor Thermal-Hydraulics, Newport, RI, 1985 (with M.R.

Fakory).

"Stability Margin Evaluation in Boiling Water Nuclear Reactors," Proceedings of the Third International Topical Meeting on Reactor Thermal-Hydraulics, Newport, RI, October 15-18, 1985 (with M.Z. Podowski and S.J. Peng).

"The Effect of Fuel Rod Dynamics on BWR Stability Margin," Proceedings of the http://www.rpi.edu/-laheyr/laheyvita.html 9/8/2 010

Dr. Richard T. Lahey Page 31 of 61 Third International Topical Meeting on Reactor Thermal-Hydraulics, Newport, RI, October 15-18, 1985 (with R.P. Taleyarkhan and M.Z. Podowski).

"An Experimental Investigation of BWR/4 Long-Term Cooling with Either Intact or Broken Jet.Pump Seals," Proceedings of the Third International Topical Meeting on Reactor Thermal-Hydraulics, Newport, RI, October 15, 1985 (with M. Fakory).

"MELRPI.Code Assessment and Its Application to Severe Core Damage Accident Analysis," Proceedings of the ANS Topical Meeting on Thermal Reactor Safety, San Diego, CA, February, 1986 (with S. Kim and M. Podowski).

"A Study of Using Simulants for Assessments of LWR Meltdown Models," ANS Transactions,52, 1986 (with S. Kasprzak and M. Podowski).

"An Analysis of Siphon Dynamics," ANS Transactions,52, 1986.

"Subchannel Measurements of the Equilibrium Quality and Mass Flux Distribution in a Rod Bundle," Proceedings of the Eighth International Heat Transfer Conference, Vol. 5, San Francisco, CA, August 17-22, 1986.

"An Analysis of BWR-Core Degradation and Meltdown Progression Using the MELPRI Computer Code," Proceedings of the ANS Topical- Meeting on Advances in Reactor Physics and Safety, NUREG/CR-0080, Vol. 1, Saratoga Springs, NY, September 1986 (with A. Sozer, S.H. Kim and M.Z. Podowski).

"Current Challenges in Nuclear Reactor Safety," Proceedings of the ANS Topical Meeting on Advances in Reactor Physics and Safety, NUREG/CP-0080, Vol. 1, Saratoga Springs, NY, September 1986.

"Experimental Simulations and Analytical Modeling of Impinging-Jet-Induced Plate Melting," Proceedings of the ANS Topical Meeting on Advances in Reactor Physics and Safety, NUREG/CP-0080, Vol. 1, Saratoga Springs, NY, September 1986 (with S. Kasprzak and M.Z. Podowski).

"The Modeling of Molten Fuel Relocation Phenomena in a Degraded BWR Core,"

Proceedings of the ANS Topical Meeting on Advances in Reactor Physics and Safety, NUREG/CP-0080, Vol. 1, Saratoga Springs, NY, September 1986 (with El-K. SiAhmed and M.Z. Podowski).

"An Investigation of Sound Propagation in Bubbly Air-Water Flows," Proceedings of the ASME WAM International Symposium on Multi-Phase Fluid Transients, Anaheim, CA, December 7-12, 1986 (A.E. Ruggles and H.A. Scarton).

"Bubble Size and Velocity Distribution in Bubbly Two-Phase Flows," Proceedings of the 4 th Miami International Symposium on Multi-Phase Transport & Particulate Phenomena, Miami Beach, FL, December 15-17, 1986 (with K.M. Bukhari).

"Finite Element Analysis of Two-Dimensional Single and Two-Phase Flows,"

Proceedings of the 4 th Miami International Symposium on Multi-Phase Transport

& Particulate Phenomena, Miami Beach, FL, December 15-17, 1986 (with K.M.

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Dr. Richard T. Lahey Page 32 of 61 Bukhari).

"Phase Separation Phenomena in Multiphase :Systems," Proceedings of the 4 th Miami International Symposium on Multi-Phase Transport & Particulate Phenomena, Miami Beach, FL, December. 15-17, 1986.

"A Dual Loop Jet Pump Model for BWR Stability Analysis," ANS Transactions, 53, 1986 (with S.J. Peng and M.Z. Podowski).

"The Modeling of BWR Thermal-Hydraulics for Severe Accident Analysis,"

Proceedings of the Second ASME/JSME thermal Engineering Joint Conference, Honolulu, Hawaii, March 22-27, 1987 (with B.R. Koh and M.Z. Podowski).

"A Study of Using Simulant Materials to Model Core Meltdown Accidents,"

Proceedings of the Second ASME/JSME Thermal Engineering Joint Conference, Honolulu, Hawaii, March 22-27, 1987 (with S.J. Peng and M.Z. Podowski).

"Interfacial Transport Phenomena During Simulated Reactor Meltdowns,"

submitted to the 6 th International Conference on PhysicoChemical Hydrodynamics, England, April 6-8, 1987 (with M.Z. Podowski and S. Kasprzak).

"Turbulence and Phase Distribution Phenomena in Two-Phase Flow,"

Proceedings of the ICHMT Seminar on Transient Phenomena in Multiphase Flow, Hemisphere Press, Dubrovnik, Yugoslavia, May 24-30, 1987.

"A Linear Model to Study Fluid Dynamics Instabilities in Boiling Channels Due to Density Wave Oscillations," Proceedings of the 5 th Congresso Nazionale sul.

Trasporto del Calore (UIT), Torino, Italy, June 25-27, 1987 (with F. DAuria, N.

DeSanctis, P. DiMarco and M.Z. Podowski).

"The Relationship Between Standing Waves, Pressure Pulse Propagation and Critical Flow Rate in Two-Phase Mixtures," ANS Proceedings of the National Heat Transfer Conference, Pittsburgh, PA, August 9-12, 1987 (with A.E. Ruggles, D.A.

Drew and H.A. Scarton).

"Transient Two-Phase Channel Flow for Nonuniform Axial Heat Fluxes," ANS Proceedings of the National Heat Transfer Conference, Pittsburgh, PA, August 9-12, 1987 (with G. Arnold).

"The Modeling of Reactor Vessel Failure Modes During Core Meltdown Accidents of BWRs,"' ASME Preprint: 87-HT-70, 1987 (with D.H. Kim and M.Z. Podowski).

"The Impact of Transient Single-Phase Heat Transfer Modeling on Predicted BWR Fuel Stability Margins," ANS Transactions,Vol. 55, 1987 (with R. Taleyarkhan, A.

McFarlane and M.Z. Podowski).

"An Application of the APRIL Code to the Analysis of BWR Core Meltdown Accidents," ANS Transactions,Vol. 55, 1.987 (with S.H. Kim and M.Z. Podowski).

"Transient Two-Phase Channel Flow for Nonuniform Axial Heat Fluxes," ANS http://www.rpi.edu/-Iaheyr/laheyvita.htmi 9/8/2.010

Dr. Richard T. Lahey Page 33 of 61 Transactions,Vol. 55, 1987 (with G. Arnold).

"A Study on Single and Two-Phase Pressure Drop in Branching Conduits,"

Proceedings of the AIChE Winter Meeting, New York, NY, November 15-20, 1987 (with S.T. Hwang).

"The Modeling of BWR Thermal-Hydraulics for Severe Accident Analysis," AIChE Symposium Volume No. 257, Vol. 83, 1987 (With B. Koh and M.Z. Podowski).

"The Analysis of Two-Phase Drop in Branching Conduits Using a Two-Fluid Model," ANS Transactions,Vol. 56, 1988 (with S. Kalkach-Navarro and S-J. Lee).

"Derivation of Constitutive Equations for Interfacial Force and Reynolds Stresses for a Suspension of Spheres using Ensemble Cell Averaging," ANS Proceedings of the 2 5 th NHTC, HTC-Vol. 3,1988 (with G. Arnold and D. Drew).

"Finite Element Analysis of Fully Developed Turbulent Two-Phase Flow in Triangular Conduits," ANS Proceedings of the 2 5 th NHTC, HTC-Vol. 3, 1988 (with S.K. Sim and J.E. Flaherty).

"A Linear Analysis of Channel-to-Channel Instability Modes," ASME Proceedings (Vol-2) of the 2 5 th NHTC,.HTD-Vol. 96,1988 (with M.Z. Podowski, A. Clausse and N. DeSanctis).

"An Experimental Investigation of Phase Distribution in an Eccentric Annulus,"

Proceedings of the 2 nd International Symposium on Two-Phase Annular and Dispersed Flows Oxford, England, 1988.

"The Prediction of Two-Phase Turbulence and Phase Distribution Phenomena Using a Reynolds Stress Model," Fundamentals of Gas/Liquid Flows, FED-Vol.

72, ASME, NY, NY, 1988 (with M. Lopez de Bertodano, S.J. Lee and D.A. Drew).

"The Analysis of Choking in Two-Phase Flow," ANS Transactions,Vol. 57, 1988.

"An Experimental and Theoretical Investigation of Melt Propagation in a Rubble Bed, with Application in Severe Accident analysis," Proceedings of the ANS Winter Meeting, Washington, DC, Oct. 30 to Nov. 4, 1988 (with El-K. SiAhmed and M.Z. Podowski).

"Benchmarking and Qualification of the NUFREQ-NPW Code for Best Estimate Prediction of Multi-Channel Core Stability Margins," 4 th Proc. of Nuclear Thermal-Hydraulics, ANS Winter Meeting, Washington, DC, 1988 (with R. Taleyarkhan, F.A. McFarlane and M.Z. Podowski).

"Finite EJement Analysis of Fully Developed Single-Phase Turbulent Flows in Triangular Conduits," Proceedings of the Third International Meeting on Nuclear Power Plant Thermal-Hydraulics and Operations, Seoul, Korea, 14-17 Nov. 1988 (with S.K. Sim and J.E. Flaherty).

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Dr. Richard T. Lahey Page 34 of 61 "The Analysis of Phase Separation and Phase Distribution Phenomena using Two-Fluid Models," Proceedings of the Third International Meeting on. Nuclear Power Plant Thermal-Hydraulics and Operations, Seoul, Korea, 14-17 Nov. 1988.

"Modification of the BNL Plant Analyzer (HIPA) for the Nine Mile Point-1 Nuclear Power Station," Proceedings of the Third International Meeting on Nuclear Power Plant Thermal-Hydraulics and Operations, Seoul, Korea, 14-17 Nov. 1988 (with M.E. Bryam, M.Z. Podowski and S. Cheng).

"An Analysis of Void Wave Propagation in Bubbly Flows," Proceedings of the 5 th Miami International Symposium on Multiphase Transport & Particulate Phenomena, 1988 (with A.E. Ruggles and D.A. Drew).

"'The Influence of Gravity on Density-Wave Instabilities in Boiling Channels,"

.Proceedings of the 5 th Miami International Symposium on Multiphase Transport &

Particulate Phenomena, 1988 (with A. Clausse).

"A Lumped Parameter Model for Linear and Non-Linear Analysis of Excursive and Density-Wave Instabilities in Boiling Channels," Proceedings of 7 th EUROTHERM Thermal Non-Equilibrium in Two-Phase Flow, Seminar Proceedings Technical Rome, Italy, 1989 (with P. DiMarco, A. Clausse and D.A. Drew).

"The Analysis of Core Meltdown Progression in BWRs," Proceedings of the 4 th International Meeting on Nuclear Reactor Thermal-Hydraulics, Karlsruhe, FRG, 1989 -(with M.Z. Podowski and J.M. Burger).

"Chaos and Non-Linear Dynamics of Density-Wave Instabilities in a Boiling Channel," AIChE Symposium Series 269, Vol. 85, 1989 (with A. Clausse and P.

DiMarco).

"Void Wave Dispersion in Bubbly Flows," ANS Symposium Volume, HTC Vol. 4, 1989 (with J-W. Park and D.A. Drew).

"The Modeling of Aerosol Dynamics During, Degraded Core Events," ANS Transactions, Vol. 60, 1989 (with A. Clausse).

"Experimental Simulation and Theoretical Analysis of Molten-Corium/Structure Interaction," ANS Transactions, Vol. 60, 1989 (with M.Z. Podowski, S. Kasprzak and D.H. Kim).

"Modeling and Calculation of Corium/Concrete Interaction in a.MARK-I Containment," ANS Transactions,Vol. 61, 1990 (with H. Jia, S.J. Lee and M.Z.

Podowski).

"An Analysis of Nonlinear Void Waves in Bubbly Flows," Proceedings of the Ninth International Heat Transfer Conference, Vol. 6, pp. 9-14, Jerusalem, Israel, August 19-24, 1990 (with J-W. Park and D.A. Drew).

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Dr. Richard T. Lahey Page 35 of 61 "An Investigation of Periodic and Strange Attractors in Boiling Flows Using Chaos Theory," Proceedings of the Ninth International Heat Transfer Conference , Vol. 2, pp. 3-8, Jerusalem, Israel, August 19-24, 1990 (with A. Clausse).

"The Effect of CRD Flow on Severe Accident Mitigation in BWRs," ANS Transactions, Vol. 62, 1990. (with D.H. Kim and M.Z. Podowski).

"An Analysis of Chugging Loads in Containment Systems," ANS Transactions, Vol. 62, 1990 (with P.M. Lahey and D.A. Drew).

"The Analysis of Chaotic Instabilities in Boiling Systems," Proceedings of the 1 6 th Eurotherm Seminar: Natural Circulation in Industrial Applications, October 11-12, 1990, Pisa, Italy (with A. "Clausse and D. Delmastro).

"The Current State-of-the-Art in the Modeling of Vapor/Liquid in Two-Phase Flows," ASME Preprint 90-WA/HT-13, 1990 (with D.A. Drew).

"Applications of Fractal & Chaos Theory in the Field of Two-Phase Flow and Heat Transfer," Proceedings of the 1990 ASME Winter Annual Meeting, Advances in Gas-Liquid Flows, HTD- Vol. 155, Dallas, TX, November 25-29, 1990.

"The Prediction of Phase Distribution using Two-Fluid Models," Proceedings of the 3 rd ASME/JSME Thermal Engineering Joint Conference, March 17-22, 1991, Reno, NV (with M. Lopez de Bertodano).

"The Analysis of S/RV, Loads in Pressure Suppression Containment Systems,"

ANS Transactions,Vol. 63, pp. 304-306, 1991 (with P.M..Lahey and D.A. Drew).

."The-Analysis of Chaotic Density-Wave Oscillations," ANS Transactions, Vol. 63, pp. 197-198, 1991 (with N. Takenaka and M.Z. Podowski).

"A Model of Radionuclides Transport in BWR Systems," Proceedings of the 2 7 th NHTC, Minneapolis, MN, July 28-31, 1991 (with C.S. Cho and M.Z. Podowski).

"A Model f BWR Containment Thermal-Hydraulics under Severe Accident Conditions," Proceedings of the 2 7 th NHTC, Minneapolis, MN, July 28-31, 1991 (with S-W. Kim and M.Z. Podowski).

"A Characteristic Analysis of Void Waves using Two-Fluid Models," Proceedings of the International Conference on Multiphase Flow, Tsukuba, Japan, Sept. 24-27, 1991.

"A Model of Radionuclides Transport in BWR Systems," Proceedings of 7 th Nuclear Thermal-Hydraulics Symposium, ANS Trans., pp. 332-342, 1991 (with C.S. Cho and M.Z. Podowski).

"The Analysis of Phase Distribution in Turbulent Two-Phase Flows," Proceedings of the 4 th International Lecture Course on Waves and Turbulence in Multiphase Flow, and Its Application, 1991.

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Dr. Richard T. Lahey Page 36 of 61 "A Aplicacao do Modelo de Deslizamento na Determinacao da Fracao de Vazio em Escoamento Horizontal Estratificado e Anular," Proceedings of the 1 1 th ABCM Mech. Eng. Eonf., Sao Paulo, Brazil, Dec. 1991 (with Fr. Franca).

"The Relationship Between Void Waves and Flow Regime Transition,"

Proceedings of the International Symposium on Instabilities in Multiphase Flows, Rouen, France, May 11-14, 1992 (with D.A. Drew, S. Kalkach-Navarro and J-W.

Park).

Phase Distribution in Complex Geometry Conduits," Proceedings of the Japan/US Seminar on Two-Phase Flow Dynamics, Berkeley, CA, July 5-11, 1992 (with M.

Lopez de Bertodano and O.C. Jones, Jr.).

"The Analysis of Void Waves in Two-Phase Flow," Proceedings of the Japan/US Seminar on Two-Phase Flow Dynamics, Berkeley, CA, July 5-11, 1992 (with J-W.

Park and D.A. Drew).

"Interfacial Area Density, Mean Radius and Number Density Measurements in Bubbly Two-Phase Flow," Proceedings of the 2 8 th NHTC, San Diego, CA, Aug. 9-12, 1992 (with S. Kalkach-Navarro, D.A. Drew and R. Meyder).

"Simulation of Ablation Heat Transfer During (orium/Concrete Interaction,"

Proceedings of the 2 8 th NHTC, San Diego, CA, Aug. 9-12, 1992 (with V. Garea, S. Kasprzak and M. Podowski).

"Multidimensional Effects During Corium Spreading in a MARK-I Containment,"

Proceedings of the 2 8 th NHTC, San Diego, CA, Aug. 9-12, 1992 (with S.

Kasprzak, H. Jia, M.Z. Podowski and R. Lilquist).

"Turbulent Bubbly Two-Phase Flow in a Triangular Duct," Proceedings of the NURETH-5, Salt Lake City, September 21-24, 1992 (with M. Lopez de Bertodano and O.C. Jones, Jr.).

"Numerical Simulation of DF-4 and CORA-16/17 Severe Fuel Damage Experiments Using APRIL.MOD3," Proceedings of the NURETH-5, Salt Lake City, September 21-24, 1992 (with S.W. Kim and M.Z. Podowski).

"The Assessment of Two Fluid Models Using Critical Flow Data,'" Proceedings of the ANS/ENS 1992 International Conference, Chicago, IL, November 15-20, 1992 (with B. Shome).

"Prediction of Critical Heat Fluxes Using a Hybrid Kohonen-Back Propagation Neural Network," Intelligent Engineering Systems Through Artificial Neural Networks, Vol. 2, pp. 853-858, Proceedings of Artificial Neural Networks in Engineering (ANNIE), November 15-18, 1992 (with T.C. Yapo, M.J..Embrechts and S.T. Cathey).

"The Application of Neural Networks to Two-Phase Flow Regime Identification,"

Intelligent Engineering Systems Through Artificial Neural Networks, Vol. 2, pp.

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Dr. Richard T. Lahey Page 37 of 61 865-870, Proceedings of Artificial Neural Networks in Engineering (ANNIE),

November 15-18, 1992 (with M.J. Embrechts and T.C. Yapo).

"Chaotic Phenomena in Density-Wave Oscillations," Presented at the New Bases for Engineering Science Algorithm, Dynamics & Fractal Symposium, November 23-28,1992 (with C.J. Chang, F.J. Bonetto and D.A. Drew).

"The Application of Neural Networks to Flow Regime Identification," Presented at the Annual Meeting of the American Power Conference, April 13-15, 1993, sponsored by Illinois Institute of Technology (with M.J. Embrechts and T. C.

Yapo).

"A Numerical Simulation of Two-Phase Jet Spreading Using and Euler-Lagrangian Technique," Proceedings of the International Symposium on Gas-Liquid Flows ,

ASME Spring Meeting, Washington; DC, June 20-23, 1993 (with F. Bonetto and D.A. Drew).

"The Measurement of Void Waves in Bubbly Two-Phase Flows," Proceedings of NURETH-6, Grenoble, France, October 5-8, 1993 (with J-W. Park and. D.A.

.Drew).

"Numerical Simulation of Gas-Flow-Induced Circulation and Heat Transfer in a Liquid Pool Near an Inclined Wall," Proceedings of NURETH-6, Grenoble, France, October 5, 8, 1993 (with H. Jia, M. Lopez de Bertodano and M.Z. Podowski).

"Prediction of Two-Phase Sonic Velocity Using Two-Fluid -Models," Proceedings of the ANS, TANSAO-69, 1993 (with C. Chang).

"Two-Fluid Modeling of the Bubbly/Slug Flow Regime Transition," Proceedingsof the ANS, TANSAO-69, p. 495-496,1993. Mark Mi//s Award, Invited Lecture (with S. Navarro-Valenti and D.A. Drew).

"Prospects.for Bubble Fusion", Proceedings of NURETH-7, NUREG/CP-0142, 1995 (with R. I. Nigmatulin).

"Near- and Far-Field CFD for a Naval Combatant Including Thermal-Stratification and Two-Fluid Modeling," Proceedings of Twenty-first Symposium on Naval Hydrodynamics, Trondheim, Norway, June 1996 (with E.G. Paterson, M.C.

Hyman, F. Stern, P.M. Carrica, F.J. Bonetto, and D.A. Drew).

"Bubble Fusion Reactor Technology," Proceedings of the Japan/U.S. Seminar on Two-Phase Flow Dynamics, Fukuoka, Japan, July 1996.

"A Geometrical Analysis of Interfacial Area Density for a Sinusoidal Wave and a Taylor Bubble in a Vertical Tube," Proceedings of AIChE Conference, Houston, TX, August 1996 (with T. Nigmatulin, and D.A. Drew).

A CFD Analysis of Multidimensional Phenomena in Two-Phase Flow using a Two-Fluid Model," Proceedings of AIChE Conference, Houston, TX, August 1996 (with A. Alajbegovic, N. Kurul, M. Podowski, and D.A. Drew).

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Dr. Richard T. Lahey Page 38 of 61 "Mechanistic Modeling of CHF in Forced-Convection Subcooled Boiling,"

Proceedings of Conference on Convective Flow and Pool Boiling, Irsee, Germany, May 18-23, 1997 (with M.Z Podowski, A. Alajbegovic, N. Kurul and D.A. Drew).

"A Polydisperse Approach to Two-Phase Flow Around a Ship," Proceedings of ASME Fluids Engineering Division Summer Meeting, Vancouver, June 22-26, 1997 (with P.M. Carrica, F. Bonetto, and D.A. Drew).

"A New Mechanistic Model of Critical Heat Flux in Forced-Convection Subcooled Boiling," Proceedings of NURETH-8, Kyoto, Japan, Sept. 30-Oct. 4, 1997 (with A.

Alajbegovic, N. Kurul, M.Z. Podowski and D.A. Drew).

"A Mechanistic Model of the Ebullition Cycle in Forced Convection Subcooled Boiling," Proceedings of NURETH-8, Kyoto, Japan, Sept. 30-Oct. 4, 1997 (with R.M. Podowski, D.A. Drew and M.Z. Podowski),

"An Analysis of a Wavy Interface Between a Liquid Film and Gas Core in a Vertical Circular Channel," Proceadhgs-of-German-Japanese Symposium on Multi-Phase Flow, Tokyo, Japan, September 1997 (with F. Inada and D.A. Drew).

"Interfacial Area Density in a Four Field Model," Proceedings of the International Symposium of Multiphase Flow, Beijing, China, October 7-11, 1997 (with T.R.

Nigmatulin and D.A. Drew).

"On the Theory of Supercompression and Sonoluminescence of a Gas Bubble in a Liquid-Filled Flask," Proceedings of the International Symposium of Multiphase Flow, Beijing, China, October 7-11, 1997 (with R.I. Nigmatulin, I.S. Akhatov and N.K. Vakhitova).

"The Development of Multidimensional Modeling Capabilities, for Annular Flows,"

Proceedings of the ICMF-Lyon, France, June 8-12, 1998 (with S. Antal, N. Kurul and M.Z. Podowski).

"Dynamics of a Small Gas Bubble in a Spherical Liquid Filled Flask," Proceedings of the ICMF-Lyon, France, June 8-12, 1998 (with R. Nigmatulin, I. Akhatov and N.

Vakhitova).

"A Polydispersed Approach to the Two-Phase Flow Around a Ship," Proceedings of the ICMF-Lyon, France, June 8-12, 1998 (with P. Carrica, F. Bonetto and D.A.

Drew).

"Three-Phase Flow Measurements Using a Hot-Film Anemometer," Proceedings of the Symposium on Optical Measurement Techniques Applied to Heat and Mass Transfer, Multiphase Flow and Combustion, Garching, FRG, September 23-24, 1999 (with S. Mayo).

"The Analysis of Two-Phase Flow and Heat Transfer Using a Multidimensional, Four Field, Two-Fluid Model," Proceedings of NURETH-9, San Francisco, CA,

.October 3-7, 1999 (with D.A. Drew).

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Dr. Richard T. Lahey Page 39 of 61 "Hydrodynamics,, Acoustics and Transport in Sonoluminescence Phenomena" ,L.A. Crum et al (Eds.), Sonochemistry and Sonoluminescence, pp.

127-138, Kluwer Publishers, 1999 (with R. Nigmatulin , I. Akhatov ,and N.

Vakhitova).

"A Center-Averaged Two-Fluid Model for Wall-Bounded Bubbly Flows,"

Proceedings of MECOM 99, Argentina, 1999 (with A.E. Larreteguy and D.A.

Drew).

"An Analysis of Two-Phase Flow and Heat Transfer using a Multidimensional, Multi-Field , Two-Fluid Computational Fluyid Dynamics (CFD) Model",

Proceedings of the US(NSF)/Japan(JSPS) Joint Seminar on Two-Phase Flow Dynamics, Santa Barbara, CA, June 5-8,2000 (with D. A. Drew)

"Applications of Laser Anenometry in Experimental Studies of Two-Phase Flows",

Proceedings of the International Conference on Multiphase Systems (ICMS-2000), Ufa, Russia, June 15-17, 2000 (with T.R. Nigmatulin and R.J. Bonetto).

"Experimental and Analytical Investigations on the Role of Multifrequency Excitation on Enhancing Sonoluminescence in Air/Water Mixtures", Proceedings of the International Conference on Multiphase Systems (ICMS-2000), Ufa, Russia, June 15-1.7, 2000 (with F.J. Moraga, R.P. Taleyarkhan, and F.J.

Bonetto).

"An Analysis of Wavy Annular Flow ", Proceedings of the International Conference on Multiphase Systems (ICMS-2000), Ufa, Russia, June 15-17,2000 (with T.J. Nigmatulin and D.A. Drew).

"CFD Analysis of Dispersed Two-Phase Flows",. Proceedings of the International

..Symposium of Multiphase Flow & Transient Phenomena (MFTP-2000), Antalya, Turkey, November 5-10, 2000.

"Modeling Turbulence Non-isotropy in Dispersed Particle/Liquids Flows",

Proceedings of the International Symposium on Multiphase flow & Transient Phenomena (MFTP-2000), Antalya, Turkey, November 5-10, 2000 (with A.

Alajbegovic and D.A. Drew).

"A Multidimensional Analysis of Bubbly Two-Phase Flow", Proceedings of the 2 nd International Symposiumon Advances in Computational Heat Transfer (CHT01),

Palm Cove, Queensland, Australia, May 20-25, 2001.

"Acoustic Excitation and the Stability of Single Bubble Sonoluminescence for Various Noble Gases", Proceedings of the 5 th World Conference of Experimental Heat Transfer, Fluid mechanics and Thermodynamics (ExHFT-5), Thessaloniki, Greece, September 24-28, 2001.

"Assesment of Turbulent Dispersion Models for Bubbly Flows"., Proceedings of the 4 th Int. Conf. On Multiphase.Flow,(ICMF-2001), New Orleans,' LA, May 27-June 1, 2001 (with F. Moraga, A. Larreteguy and D. Drew).

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Dr. Richard T. Lahey Page 40 of 61 "Thermonuclear Fusion in Collapsed Microbubbles", Proceedings of EUROTHERM-74, March 23-26, Eindhoven, Netherlands, 2002 (wilh R.

Nigmatulin, I. Akhatov and R. Taleyarkhan).

"A Center-Averaged Two-Fluid Model for Wall-Bounded Bubbly Flows",

Proceedings of the 5 th Int. Symposium on Numerical Methods for Multiphase Flow, ASME/European FED Conference , Montreal,Canada,July 14-18, 2002 (with A.E. Larreteguy and D. A. Drew).

"Sonoluminescence and the Search for Bubble Fusion", Proceedings of HEAT-2002, Kielce, Poland, June 24-27, 2002 (with R. I. Nigmatulin and R. P.

Taleyarkhan ).

"The Analysis of Bubble Fusion", ANS Trans., June 9-13, 2002 (with K.E.

Jansen and S. Nagrath).

"Dynamics of Collapsing Bubbles: Sonoluminescence and Bubble Fusion",

Proceedings of the 16th Int. Symposium on NonLinear Acoustics (ISNA-16),

Moscow, Russia , August 19-23, 2002 ( with R. Nigmatulin, I. Akhatov, A.

Topolink, R. Bolotnova and R. Taleyarkhan).

"An Analytical Approach to Bubble/Slug Flow Regime.Modeling using a Multi-Field., Two-Fluid Model", Proceedings of the 6th ASME/JSME Conference, Kona ,Hawaii ,March 16-20., 2003 (with*D. Drew).

"Update and Clarifications on Experimental Studies for Nuclear Emissions during Acoustic Cavitation"., Proceedings of the 145th Meeting of the Acoustic Society of America , Nashville, TN, April 28-May 2,2003 (with R.P. Taleyarkhan, C.D.

West-,J.S. Cho , R.C. Block, and R. . Nigmatulin).

"Update and Clarification on Analytical Studies for Nuclear Emissions during Acoustic Cavitation", Proceedings of the 145th Meeting of the Acoustic Society of America, Nashville , TN , April 28-May 2, 2003 (with R.I. Nigmatulin , R.P.

Taleyarkhan , and C.D. West).

"The Modeling of Bubbly Flows around Naval Surface Ships atHigh Reynolds Numbers", Proceedings of the 2nd MIT Conference of Computational Fluid and Solid Mechanics, June 17-20, 2003 (with F. Moraga , A. Larreteguy and D.A.

Drew).

"The Design of Acoustic Resonant Chambers by Numerical Simulation",Proceedings of the 2nd MIT Conference of Computational Fluid and Solid Mechanics, June 17-20, 2003 (with S. Cancelos , F. Moraga , I. Akhatov and R.H. Parsons).

"Advancements in the Multidimensional Analysis of Multiphase Flows" Proceedings of HEFAT-2003, Victoria Falls, Zambia ,June 23-26, 2003 (with D.

Drew, K. Jansen , A. Galimov and S. Nagrath).

"The Modeling of Lift and Dispersion Forces in Two-Fluid Model Simulations, Part-.

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Dr. Richard T. Lahey Page 41 of 61 I: Jet Flows", Proceedings of the ASME/JSME Meeting , Honolulu, Hawaii ,July 6-10,.2003 (with M. Lopez de Bertodano, F. Moraga and D. A. Drew).

"The Modeling of Lift and Dispersion Forces in Two-Fluid Model Simulations, Part-II : Boundary Layer Flows", Proceedings of the ASME/JSME Meeting , Honolulu, Hawaii ,July 6-10,2003 (with F. Moraga , M. Lopez de Bertodano, and D. A.

Drew).

"An Analytical Study on Interfacial Wave Structure Between a Liquid Film and Gas Core in a Vertical Circular Channel", Proceedings of NURETH-10, Seoul ,Korea, October 5-9, 2003 (with F. Inada and D. A. Drew).

"A Non-Linear Model for Bubble-Induced Turbulent Viscosity in Bubbly Two-Phase Flow", Proceedings of NURETH-10 , Seoul,Korea, October 5-9,2003 (with I.

Bolotnov, F. Moraga and D. A. Drew).

"An Analytical Study on Interfacial Wave Structure Between Liquid Film and Gas Core in a Vertical Channel", Proceedings of NURETH-10 , Seoul, Korea , October 5-9, 2003 (with F. Inada and D.A. Drew).

"Modeling and Simulation of Full Scale Bubbly Flows around Surface Ships,"

Proc. of 3 rd Int. Symposium of Two-Phase Flow Modeling and Experiments, Pisa, Italy, Sept. 22-24, 2004 (with F. Moraga, D. A. Drew).

"Simulating Churn -Turbulent Flows in a Bubble Column using a Three Field, Two-Fluid Model," Proc. of 5 th Int. Conf. Multiphase Flow (ICMF'04), Yokohama, Japan, May 30-June 4, 2004 (with S. Antal, M. AI-Dahhan).

"The-Analysis of Void Wave Propagationand -nstability using Two-Fluid Models,"

Proc. of 5 th Int. Conf. Multiphase Flow (ICMF'04), Yokohama, Japan, May 30-June 4, 2004 (with J. Yin).

"An Analysis of Interacting Instability Modes," Proc. of Japan/US Seminar on Two-Phase Flow Dynamics, Nagahama, Japan, Dec. 6-11, 2004 (with J. Yin, M.

Jensen).

"Analysis of Void Wave Propagation and Sonic Velocity using a Two-Fluid Model,"

Proc. of Japan/US Seminar on Two-Phase Flow Dynamics, Nagahama, Japan, Dec. 6-11, 2004.

"The Analysis of Linear and Nonlinear Bubble Cluster Dynamics," Proc. of Japan/US Seminar on Two-Phase Flow Dynamics, Nagahama, Japan, Dec. 6-11, 2004 (with I. Akhatov, R. Nigmatulin).

"Modeling Wall-Induced Forces on Bubbles for Inclined Walls," Proc. of Japan/US Seminar on Two-Phase Flow Dynamics, Nagahama, Japan, Dec. 6-11, 2004 (with F. Moraga, S. Cancelos).

"The Design of Acoustic Chambers for Bubble Dynamics Research," Proc. of Japan/US Seminar on Two-Phase Flow Dynamics, Nagahama, Japan, Dec. 6-11, http://www.rpi.edu/-Iaheyr/laheyvita.html/ 9/8/2010

Dr. Richard T. Lahey Page 42 of 61 2004 (with S. Cancelos, F. Moraga, P. Bouchilooux).

"Bubble Nuclear Fusion Technology - Status and Challenges," Proc. of Japan/US Seminar on Two-Phase Flow Dynamics, Nagahama, Japan, Dec. 6-11, 2004 (with R. Taleyarkhan, R. Nigmatulin).

"The Analysis of Interfacial Waves," Proc. 3 rd Int. Symposium of Two-Phase Flow Modeling and Experiments, Pisa, Italy, Sept. 22-24, 2004 (with A. Galimov, D. A.

Drew).

"The Analysis of Sonofusion" , Proc. ISMF' 05, Xi'an , China, July 3-6, 2005 (with R.I. Nigmatulin ,R.P. Taleyarkhan).

"The Effect of an Accumulator on Pressure-Drop and Density-Wave Oscillations using a Linear Frequency Domain Model", Proc. ISMF' 05, Xi'an, China, July 3-6, 2005( with J. Yin, M.K. Jensen , M.Z. Podowski).

"Sonofusion - Fact or Fiction", Proc. NURETH-1 1 , Avignon, France, October 2-6, 2005 (with R.P. Taleyarkhan, R.I. Nigmatulin).

"Multidimensional Modeling. of Developing Two-Phase Flows in a Large Adiabatic Riser", Proc. NURETH-1 1, Avignon, France, October 2-6, 2005 (with S.

Antal, M. Z. Podowski , D. Barber ,C. Delfino).

"Nanoscale Bubble Thermonuclear Fusion in. Acoustically Cavitated Deuterated Liquid", Proc, NURETH-1 1, Avignon, France, October 2-6,2005 ( with R.

Nigmatulin, R. Taleyarkhan).

"Stabilitaetsanalyse eins Stroemungskanals mit ueberkritischen Dampfzustaenden'", Proc. Compact fur Kerntechnische Gesell Shaft (KTG),

Aachen, Germany, May 16-18, 2006 (with T. Ortega-Gomez, A. Class ,T.

Schulenberg).

"Stability Analysis of a Uniformly Heated Channel with Supercritical Water", Proc.

ICONE-14, Miami, Florida', July 17-20, 2006 ( with T. Ortega-Gomez, A. Class, T. Schulenberg):

"Computation of the Unsteady Two-phase Flow Around a Manuvering Surface Ship", Proc. 26th Symposium on Naval Hydrodynamics, Rome, Italy, Sept. 17-22, 2006 (with M. Hyman., F. Moraga, D.A. Drew).

"The Effect of Gravity Level on the- Stability of a Rankine Cycle Power System",

Proc. ICAPP 2007, Nice, France, May 13-18, 2007 (with W. Schlichting, M.

Podowski).

"The Modeling of Two-Phase Turbulence", Proc. ICMF-2007, Leipzig, Germany, July 9-13 ,2007 ( with I. Bolotnov, D. Drew, K. Jansen).

"Convergence Studies of Turbulent Channel Flows using a Stabilized Finite Element Method", Proc. 9th US National Congress on Computational Mechanics, http://www.rpi.edu/-Iaheyr/laheyvita.htm9/ 9/8/2010

Dr. Richard T. Lahey Page. 43 of 61 San Francisco, CA, July 23-26, 2007 (with A. Trofimova., A. Tejada-Martinez, K. Jansen).

"Stability Analysis of a Boiling Loop in Space", Proc. COMSOL Conference-2007, Boston, MA, October 4-6, 2007 (with W. Schlichting, M. Podowski, T. Ortega-Gomez)..

"On the Direct Numerical Simulation of Two-Phase Flows", Proc. NURETH-12, Pittsburgh, PA, Sept. 30 - Oct. 4, .2007.

"Density-Wave Oscillations in Coupled Parallel Channels under Supercritical Pressure Conditions", Proc. ANS/ENS International Winter Meeting , Washington DC, November 11-15, 2007 (with T. Ortega-Gomez, A. Class, T. Schulenberg).

"Multidimensional Analysis of Developing Two-Phase Flows in an ESBWR with and without Riser Channels", Proc. ICAPP' 08, Anaheim, CA, June 8-12, 2008 (with H. Murakawa and S. Antal).

"Multidimensional Analysis of Developing. Two-Phase Flows using Multifield Simulation in Natural Circulation BWR Chimney", Proc. IFHT2008, Tokyo, Japan, Sept. 17-19, 2008 (with H. Murakawa and S. Antal).

"A Subgrid Model for Predicting Air Entrainment Rates in Bubbly Flows", Proc.

61st Meeting of the APS- Division of Fluid Dynamics, San Antonio , TX, Nov. 23-25, 2008 (with Jingsen Ma, A. Oberai, D. Drew and F. Moraga).

"On the Operating Characteristics of Acoustic Chambers for Sonofusion", Proc.

NURETH-13, Kanazawa City, Japan, Sept. 27 - Oct.2, 2009 (with Markus Stokmaier, Bernard Maoulin, Andreas Class and Thomas Schulenberg).

"A Comprehensive Subgrid Air Entrainment Model for Reynolds-averaged Simulations of Free-Surface Bubbly Flows", Proc. 62nd Meeting of the APS-Division of Fluid Dynamics, Minneapolis, MN , Nov. 22-24, 2009 (with Jingsen Ma , A. Oberai, D. Drew and M. Hyman).

"The Numerical Simulation of Two-Phase Annular Flow", Proc. ICMF 2010, Tampa, Florida, May 30-June 4, 2010 (with Joseph Rodriguez and Ken Jansen).

"Direct Numerical Simulation of Turbulent Two-Phase Bubbly Channel Flow",

Proc. ICMF 2010, Tampa, Florida, May 30-June 4, 2010 (with Igor Bolotnov, Ken Jansen , Donald Drew, Assad Oberai and Michael Podowski).

"DES and RaNS Modeling of a 3-D Hydraulic Jump with Air Entrainment using a Two-Fluid Model", Proc. ICMF 2010, Tampa, Florida, May 30-June 4, 2010 (with Jingsen Ma, Assad Oberai and Donald Drew).

"A Generalized Sub-Grid Air Entrainment Model for RaNS Modeling of Bubbly Flows", Proc. ICMF 2010, Tampa, Florida, May 30-June 4, 2010 (with Jingsen Ma, Assad Oberai and Donald Drew).

http://www.rpi.edu/-laheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 44 of 61 "Sub-grid Air Entrainment Model for RANS and LES Simulations of Free Surface Turbulence Bubbly Flows", Proc. 28th ONR Symposium on Naval Hydrodynamics, Cal Tech, Pasadena , CA, Sept. 12-17, 2010 ( with Assad Oberai, Jingsen Ma, and Donald Drew).

A Detached Direct Numerical Simulation of Two-Phase Turbulent Bubbly Channel Flow", Proc. 7th Int. Conference on Multiphase Flow (ICMF 2010),

Tampa, FL. May30 - June 4, 2010 (with I. A. Bolotnov, K.E. Jansen, D.A. Drew, A.A. Oberai, M.Z..Podowski).

"The Simulation of Air Entrainment in a Hydraulic Jump using Two-Fluid DES and RaNS Models", Proc. 7th Int. Conference on Multiphase Flow (ICMF 2010),

Tampa, FL. May30 - June 4, 2010 (with J. Ma, A.A. Oberai, D.A. Drew).

"A Generalized Subgrid Air Entrainment Model for RaNS Modeling of Bubbly Flows around Ship Hulls"., Proc. 7th Int. Conference on Multiphase Flow (ICMF.

2010), Tampa, FL. May30 - June 4, 2010 (with J. Ma, A.A. Oberai, M.C. Hyman, D.A. Drew).

"ATwo-Way Coupled Polydispersed Simulation of Bubbly Flow Beneath a Plunging Liquid Jet", Proc. ASME Fluids Engineering Division (FED) Summer Meeting , Montreal, Quebec-Canada, August 1-5, 2010 (with J. Ma, A.A. Oberai, D.A. Drew)."

"Acoustic Chambers for Sonofusion Experiments : FE - Analysis Highlighting Performance Limiting Factors'!, Proc.17th International Congress on Sound and Vibration (ICSV 17 ), Cario, Egypt, July 18-22, 2010 ( with Markus J. Stokmaier, Andreas G. Class, Thomas Schulenberg).

"Influence of Bubbles on Liquid Turbulence Based on the Direct Numerical.

Simulation of Channel Flows", Proc. 63rd Annual APS Meeting - Division of Fluid Dynamics, Long Beach, CA, Nov. 21-23, 2010 (with Igor Bolotnov, Donald D.

Drew and -Michael Z. Podowski) .

Unrefereed Publications "Control Rod Oscillator Tests: Garigliano Nuclear Reactor," GEAP-5534, August 1967.

"BWR Stability Considerations Resulting from Garigliano Research and Development Program," International Symposium on Dynamics of Two-Phase Flow, presented at University of Eindohoven, The Netherlands, 1967 (with J.

Hodde).

"Representation of Space-Time Velocity and Pressure Fluctuation Correlations by a Tentative Phenomenological Model," Stanford University Report MD-22, August http://www..rpi.edu/-Iaheyr/laheyvita.html 9821 9/8/2010

Dr. Richard T. Lahey Page 45 of 61 1968.

"Subchannel and Pressure Drop Measurements in a Nine-Rod Bundle for Diabatic and Adiabatic Conditions," GEAP-13049, March 1970 (with B. Shiralkar, et al)

"A Stochastic Wave Model Interpretation of Correlation Functions for Turbulent Shear Flows," Stanford University Report MD-26, May 1971.

"The Analysis of Transient Critical Heat Flux," GEAP-1 3249, 1972 (with J.

Gonzalez).

"General Electric BWR Thermal Analysis Basis (GETAB): Data, Correlation and Design Application,"NEDO-10958, November 1973.

"A Turbine-Meter Evaluation Model for Two-Phase Transients (TEMPI)," EG&G Idaho, Inc. Topical Report, 1977 (with P. Kamath).

"Transient Analysis of a Drag-Disk in Two-Phase Flow," EG&G Topical, NES-483, 1978 (with P. Kamath and D.R. Harris).

"The Measurement of Phase Separation in Wyes and Tees," USNRC Topical Report, NUREG/CR-0557, 1978 (with T.J. Honan).

"The Development of a Side-Scatter Gamma Ray System for the Measurement of Local Void Fraction," USNRC Topical Report, NUREG/CR-0677, 1978 (with S.

Schell).

"A Review of Selected Void Fraction and Phase Velocity Measurement Techniques," Proceedings of the FDI Two-Phase Instrumentation Course, Dartmouth College, 1978...

"The Analysis of Proposed BWR Inlet Flow Blockage Experiments at PBF," EG&G Idaho, Inc., Topical Report, 1978 (with K. Ohkawa).

"Virtual Mass Effects in Two-Phase Flows," USNRC Topical Report, NUREG/CR-0020, 1979 (with L. Cheng and D.A. Drew).

"Flow Patterns & Phase Distribution Phenomena," Invited paper given at Two-Phase Flow Summer Course, Munich, Germany, 1979.

"Two-Phase Flow Instability," Invited paper given at Two-Phase Flow Summer Course, Munich, Germany, 1979.

"The Measurement of Void Fraction and Phase Velocity using Electrical Impedance Probes," Invited paper given at Two-Phase Instrumentation course, Grenoble, France, 1979.

"Radioactive Tagging Techniques in Two-Phase Flow," Invited paper given at Two-Phase Instrumentation Course, Grenoble, France, 1979.

http://www.rpi.edu/-Iaheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 46 of 61 "Photon Attenuation and Scattering Techniques in Two-Phase Flow," Invited paper given at Two-Phase Flow Instrumentation Course, Grenoble, France, 1979.

"Two-Phase Flow Phenomena in Nuclear Regulatory Technology," USNRC Topical Report, NUREG/CR-0677, 1979 (with S. Schell and R.R. Gay).

"Force & Torque Flow Measurement Methods," Proceedings of Stanford Summer Course on Two-Phase Flow Instrumentation, 1980.

"Transit Time Techniques," Proceedings of Stanford Summer Course on Two-Phase Flow Instrumentation, 1980.

"The Design of Photon Attenuation and Scattering Systems," Proceedings of Stanford Course on Two-Phase Flow Instrumentation, 1980.

"Local Void Probes," Proceedings of Stanford Summer Course of Two-Phase Flow Instrumentation, 1980.

"The Analysis of Linear and Nonlinear Instability Phenomena in Heated Channels," USNRC Topical Report, NUREG/CR-1718, 1980 (with J.L. Achard and D.A. Drew).

"Flow- Regime Identification and Void Fraction Measurement Techniques in Two-Phase Flow," USNRC Topical Report, NUREG/CR-1692, 1980 (with M.A. Vince).

"An Assessment of the Literature Related to LWR Instability Models,"

NUREG/CR-1414, 1980 (with D.A. Drew).

"Transient Analysis of DTT Rakes," USNRC Topical Report, NUREG/CR-2151, 1981 (with P.S. Kamath).

"The Analysis of Countercurrent Two-Phase Flow Pressure Drop and CCFL Breakdown in Diabatic and Adiabatic Conduits," NUREG/CR-2386, 1981 (with A.

Ostrogorsky and R.R. Gay).

"Parallel Channel Effects During the Emergency Core Cooling of a BWR,"

Proceedings of the 9 th Water Reactor Safety Information Meeting, Washington, DC 1981.

"Transient and Sustained Instabilities in Multiphase Flows," Proceedings of the 2 nd Multiphase Flow and Heat Transfer Symposium Workshop, 1981 (with J.L.

Achard).

"The Measurement of Two-Dimensional Phase Separation Phenomena," USNRC Topical Report, NUREG/CR-1936, 1981 (with M. Barasch).

"Two-Fluid or Not Two-Fluid," Guest Column, Heat Transferand FluidFlow Service, UKAEA, UK,1981.

"The Analysis of Proposed BWR Inlet Flow Blockage Experiments Using http://www.rpi.edu/-Iaheyr/laheyvita.htmI 9/8/2010

Dr. Richard T. Lahey Page 47 of 61 MAYU4b," USNRC Topical Report, NUREG/CR-2260 and EG&G Topical Report, EGG-2181, 1982 (with M.E. Nissley and R.R. Gay).

"The Analysis of Pulsed Neutron Activation Technique," USNRC topical Report, NUREG/CR-2471, 1981 (with M.L. Griffo and R.C. Block).

"An Experimental Investigation of Boiling Water Nuclear Reactor Parallel Channel Effects During a Postulated Loss-of-Coolant Accident," USNRC Topical Report, NUREG/CR-2971, 1982 (with W.M. Conlon).

"An Analysis of Density-Wave Oscillations in Ventilated Channels," USNRC Topical Report, NUREG/CR-2972, 1982 (with R. Taleyarkhan and M. Podowski).

"Phase Separation Phenomena in Branching Conduits," USNRC Topical Report, NUREG/CR-2590, 1982 (with N. Saba).

"The Development of NUFREQ-N, An Analytical Model for the Stability Analysis of Nuclear Coupled Density-Wave Oscillations in Boiling Water Nuclear Reactors,"

USNRC Topical Report, NUREG/CR-3375, 1983 (with G.C. Park, M. Podowski and M. Becker).

"An Analysis of Wave Dispersion, Sonic Velocity and Critical Flow in Two-Phase Mixtures," USNRC Topical Report, NUREG/CR-3372, 1983 (with L. Cheng and D.A. Drew).

"Air/Water Subchannel Measurements of the Equilibrium Quality and Mass Flux Distribution in a Rod Bundle," USNRC Topical Report, NUREG/CR-3373, 1983 (with R. Sterner).

"Parallel Channel Effects and Long-Term Cooling During Emergency Core Cooling in a BWR/4," USNRC Topical-Report, NUREG/CR-3376, 1983 (with M.

Fakory).

"The Development of Gamma Ray Scattering Densitometer and Its Application to the Measurement of Two-Phase Density Distribution in an Annular Test Section,"

USNRC Topical Report, NUREG/CR-3374, 1983 (with K. Ohkawa).

"An Analysis of Boiling Water Nuclear Reactor Stability Margin," USNRC Topical Report, NUREG/CR-3291, 1983 (J. Balaram, C.N. Shen and M. Becker).

"The Measurement of Phase Distribution Phenomena in a Triangular Conduit,"

USNRC Topical Report, NUREG/CR-3576, 1983 (with S. Sim).

"MechanisticCore-Wide Meltdown and Relocation Modeling for BWR Applications," NUREG/CR-3525, 1983 (with M.Z. Podowski and R. Taleyarkhan).

"Mathematical Modeling of U-Tube Steam Generator Dynamics for Slow Transients and Small Break Loss-of-Coolant Accidents," EPRI report RP1 1, 63-5, 1983.

http://www.rpi.edu/-Iaheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 48 of 61 "The Measurement of Countercurrent Phase Separation and Distribution in a Two-Dimensional Test Section," USNRC Topical Report, NUREG/CR-3577, 1984 (with K.M. Bukhari).

"Current Understanding of Phase Separation Mechanics in Branching Conduits,"

Proceedings of the U.S.-Japan Seminar on Two-Phase Flow Dynamics, Lake Placid, NY 1984.

"Advances in Analytical Modeling of Linear and Nonlinear Density-Wave Instability Modes," Proceedings of the U.S.-Japan Seminar on Two-Phase Flow Dynamics, Lake Placid, NY 1984.

"Modeling Two-Phase Flow Division at T Junctions," Proceedings of the H.T.F.S.

Symposium, Coventry, England, 1984 (with B. Azzopardi -and M. Cox).

"NUFREQ-NP: A Digital Computer Code for the Linear Stability Analysis of Boiling Water Nuclear Reactors," NUREG/CR-4116 USNRC Topical Report, 1984 (with S.J. Peng and M.Z. Podowski).

"Analytical Methods for Multicomponent Systems," Proceedings of Workshop on Industrial Applications of Multiphase Flow, UCSB, 1985.

"Light Water Nuclear Reactor LOCA Technology," Proceedings of Workshop on Industrial Applications of Multiphase Flow, UCSB, 1985.

"Condensation Heat Transfer," Proceedings of the RPI Summer Course on Two-Phase Heat and Mass Transfer in Single and Multicomponent Systems, 1985.

"Multicomponent Condensation," Proceedings of the RPI Summer Course on Two-Phase Heat and Mass Transfer in Single and Multicomponent Systems, 1985.

"Multicomponent Boiling," Proceedings of the RPI Summer Course on Two-Phase Heat and Mass Transfer in Single and Multicomponent Systems, 1985.

"The Modeling of BWR Core Meltdown Accidents - For Application in the MELRPI.MOD2 Computer Code," NUREG/CR-3889, 1985 (B.R. Koh, S.H. Kim, R. Taleyarkhan and M.Z. Podowski).

"Basic Conservation Equations," Proceedings of the RPI Summer Course on Computer Simulation of Multiphase Flows, 1986.

."Interfacial Transfer Laws," Proceedings of the RPI Summer Course on Computer Simulation of Multiphase Flows, 1986.

"Closure Conditions for Two-Fluid Models of Two-Phase Flow," Proceedings of the Sixth Symposium on Energy Engineering Sciences, ANL, 1988 (with G. Arnold and D.A. Drew).

"The Relationship Between Microstructure and the Averaged Equations of Two-http ://www.rpi.edu/-Iaheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 49 of 61 Phase Flow," EUROMECH 234, Toulouse, France, May, 1988 (with G. Arnold and D.A. Drew).

"The Analysis of Phase Separation Phenomena in Branching Conduits,"

Proceedings-of the JAPAN/US Seminar-on Two-Phase Flow Dynamics, Kyoto, Japan, July 1988.

"An Analysis of Wave Propagation Phenomena in Two-Phase Flow," Proceedings of the JAPAN/US Seminar on Two-Fluid Flow Dynamics, Kyoto, Japan, July, 1988

'Phase Distribution and Phase Separation Phenomena in Two-Phase Flows,"

Proceedings of the Japan Society of Multiphase Flow, 1988.

"An Analysis of Wave Propagation Phenomena in Two-Phase Flow," Proceedings of RPI Summer Course of Modern Developments in Boiling Heat Transfer and Two-Phase Flow, 1988.

"An Analysis of Phase Distribution Phenomena in Two-Phase Flow," Proceedings of RPI Summer Course of Modern Developments in Boiling Heat Transfer and Two-Phase Flow, 1988.

"An Analysis of Phase Separation in Branching Conduits," Proceedings of RPI Summer Course of Modern Developments in Boiling Heat Transfer and Two-Phase Flow, 1988.

"The Development of APRIL.MOD2 - A Computer Code for Core Meltdown Accident Analysis of.Boiling Water Nuclear Reactors," NUREG/CR-5157, July, 1988 (with S. Kim, et al).

"An Analysis of Wave Propagation Phenomena in Two-Phase Flow," Proceedings of RPI Summer Course of Modern Developments in Boiling, Heat Transfer and Two-Phase Flow, 1989.

"An Analysis of Phase Distribution Phenomena in Two-Phase Flow," Proceedings of RPI Summer Course of Modern Developments in Boiling Heat Transfer and Two-Phase Flow, 1989.

"An Analysis of Phase Separation in Branching Conduits," Proceedings of RPI Summer Course of Modern Developments in Boiling Heat Transfer and Two-Phase Flow, 1989.

"Degraded BWR Core. Modeling - Physical Simulations of Selected Components,."

ESEERCO EP84-4 Final Report, September 1989 (with M.Z. Podowski).

"The Analysis of Void Wave Phenomena," Proceedings of the Eighth Symposium on Energy Engineering Sciences, pp. 27-34, ANL Report CONF-90051.83, 1990 (woth J-W. Park and D.A. Drew).

"Degraded BWR Core Modeling - APRIL.MOD3 Severe Accident Code,"

ESEERCO EP84-4 Final Report, July 1990 (with M.Z. Podowski).

http://www.rpi.edu/-Iaheyr/laheyvita.htm/ 9/8/2010

Dr. Richard T. Lahey Page 50 of 61 "Multiphase Thermal Science," Proceedings of the NSF Workshop on Thermal Sciences, Chicago, April 19-21, 1991.

"A Four Field. Model for Two-Phase Flow," 1 2 th Symposium on Energy Engineering Sciences, 4/27-29/94, Argonne National Laboratory (with D.A. Drew).

"Synchronic Nonlinear Forcing of a Sonoluminescent Microbubble using Fast Ultrasonic Pulses," Proceedings of the APS, March 1996 (with F.J. Bonetto and G.A. Delgadino).

"A CFD Analysis of Multidimensional Two-Phase'Flow and Heat Transfer Using a Four Field Two-Fluid Model," Proceedings of the Thirteenth U.S. National Congress on Applied Mechanics, U of Florida, June 21-26, 1998.

"A CFD Analysis'of Multidimensional Two-Phase Flow & Heat Transfer with a Four Field Two-Fluid Model," Proceedings of IMUST Meeting, Santa Barbara, CA, March. 18-20, 1999.

"A Center-Averaged Two-Fluid Model for Wall-Bounded Flows," ONR Free Surface and Bubbly Flows Workshop, La Jolla, CA, Feb. 24-26, 1999 (with A.E.

Larreteguy and D.A. Drew).

"Multidimensional Two-Fluid Modeling of Two-Phase Flow and Heat Transfer In a Boiling Channel with Applications to CHF Modeling in Forced-Convection Sucooled Boiling," National Science Agency of Tiawan Report, August 1999 (with C. Pan and D. A. Drew)

"An Analysis of Two-Phase Flow and Heat Transfer using a Multidimensional, Multi-Field, Two-Fluid Computational Fluid Dynamics (CFD) Model"I Proceedings of the Japan/US Seminar on Two-Phase Flow Dynanmics, Santa Barbara, California, June 5-8, 2000 (with D.A. Drew).

"An Analysis of Rectified Diffusion in a Sonoluminescing Gas Bubble",,

Proceedings of the Japan/US Seminar on Two-Phase Flow Dynamics, Santa Barbara, California, June 5-8, 2000 (with S. Bae and R. Nigmatulin).

"On the Multidimensional Analysis of Two-Phase Flows", Proceedings of the USDOE Workshop on Scientific Issues in Multiphase Flow, U. Illinois-CU May 7-9,2002 (with D. Drew).

"Sonoluminescence and the Search for Sonoluminescence", ANS Panel on Advances in Fusion Technology, ANS Annual Meeting , Hollywood, Florida, June 9-13, 2002 "Response - Tabletop Fusion Revisited (.by: A. Galonsky)", Science on-line, 2002 (with R. Taleyarkhan, R. Block and C. West).

"Response.- Questions Regarding Nuclear Emissions in Cavitation Experiments (by: M. Saltmarsh and D. Shapira )", Science on-line , 2002 (with R.

Taleyarkhan, R. Block and C. West).

http://www.rpi.edu/-Iaheyr/laheyvita.html *9/8/2016

//21

Dr. Richard T. Lahey Page 51 of 61 "Energetics of Nano-to-Macro Scale Triggered Tensioned Metastable Fluids",

ORNL/TM-2022/233, 2002 (with R. Taleyarkhan, C. West, J. Cho and I.

Akhatov).

"The Modeling of Bubbly Flows Around Ship Hulls", Maui High Performance Computing Center, Application Brief, 2002 (with F. Moraga and D. A. Drew).

"Full-Scale Simulations of the Research Ship Roger Revelle", Maui High Performance Computing Center, Application Brief, 2003 (with F. Moraga and D.

A. Drew).

"The Development of Interfacial Drag and Non-Drag Laws for Stratified Flow using PHASTA-21", Proceedings of the American Physical Society, East Rutherford, NJ ,Nov.23-25, 2003 "Computational Multiphase Fluid Dynamics (CMFD) Analysis of a Single ESBWR Riser Channel," ISL Final Topical Report, 2004 (with S. Antal, M. Popowski).

"Research in Support of the Use of Rankine Cycle Energy Conversion Systems for Space Power and Propulsion," NASA/CR-2004-213142, 2004 (with V. Dhir)

"Safety and Security of Commercial Spent Nuclear Fuel Storage," Classified National Research Council (NRC) Topical Report, 2004.

"Nuclear Engineering External Review Committee Report," Purdue University Report, 2004.

"The CMFD Analysis of Three-Field Chemical Reactors," CREL Topical Report, 2004 (with S. Antal).

"The Sonofusion Research Project at KIT and RPI", Proceedings of the 62nd Meeting of the American Physical Society - Division of Fluid Dynamics, Minneapolis, Minnesota, November 22-24, 2009 (with Markus Stokmaier, Bernard Malouin, Andreas Class, Thomas Schulenberg).

Special Courses Taught

RPI Summer Program on Nuclear Reactor Design & Basic Nuclear Technology (RPI sponsored), Troy, NY 1997-1983 9 Short course in Introduction to Nuclear Power, Continuing Education Center, (CEC sponsored) Sheraton Motor Inn, East Brunswick, NJ, 1978

Two-Phase Flow and Heat Transfer (B&W sponsored), Alliance, OH, 1978

Two-Phase Flow and Heat Transfer (EG&G sponsored), Idaho Falls, ID, 1979-1983

Two-Phase Flow Instrumentation course (FD! sponsored), Dartmouth University, 1978 http ://www.rpi.edu/-laheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 52 of 61

Multiphase Flow Instrumentation course (CEA sponsored), Grenoble, France, 1979

" Workshop on Transient Analysis of Reactors (FRG sponsored), Munich, Germany, 1979

Reactor Thermal-Hydraulics, AIChE short course, 1976 -1983

" Stanford summer course on Two-Phase Flow Instrumentation, 1980

Course on Two-Phase Flow and Boiling, Yankee Atomic Electric Company, 1980

Summer school on Reactor Thermal-Hydraulics (ICHMT sponsored), Dubrovnik, Yugoslavia, 1980

Stanford summer course on Two-Phase Flow & Heat Transfer (Stanford sponsored),

Stanford University, 1982

Simposio Internacional Sobre Flujos Bifasicos en Tuberias (Mexican sponsored),

Cuernavaca, Mexico, 1983

Lecture Series No. 8, Construction Aspects of Two-Phase Flow Equipment (Norwegian sponsored), Trondheim,. Norway, 1984

Workshop on IndustrialApplications of Multiphase Flow (UCS sponsored), Santa Barbara, CA 1985

. Workshop on Two-Phase Heat and Mass Transfer in Single and Multicomponent Systems (RPI sponsored), Troy, NY 1986 9 Modern Developments in Boiling Heat Transfer and Two-Phase Flow (CMR sponsored),

Troy, NY 1988-present An Introduction to Applied Nonlinear Dynamics - Bifurcations, Fractals and Chaos in Heat Transfer and Fluid Flow (ETH sponsored), Zurich, Switzerland, 1994-1996

Short Course on Multiphase Flow and Heat Transfer (ETH sponsored), Zurich, Switzerland, 1994-1996 2001 Frederic Joliot/Otto Hahn Summer School, Karlsruhe, Germany, August 20-29 2001 Short Course on "Transient Multiphase Flow and Heat Transfer at Microgravity", NASA, Glenn Resrarch Center, Cleveland, Oh. Sept. 17-19, 2002 (with M.Z. Podowski)

Research Funding USNRC Two-Phase Flow Phenomena in Nuclear Reactor Technology http://www.rpi.edu/-Iaheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 53 of 61

$1,006,240 6/1176-5/31180.

Technical Assistance Program for the Thermal-Hydraulic Stability Analysis Relating to Light Water Nuclear Reactors

$676,425 3/15/76-94/83.

Multidimensional Effects in-LWR Thermal-Hydraulics

$176,000 6/1/80-1/31/81.

The Development of Thermal-Hydraulic Stability Methods for BWR's

$100,000 9/5/81-9/4/83.

ONR An Experimental Study of Plunging Liquid Jet Induced Air Carryunder and Dispersion

$122,883 11/1/90-10/30/91.

A Study of Spreading Two-Phase Jets

$120,000 1/1/94-12/31/95.

A Study of Spreading Two-Phase Jets

$138,892 3/1/95-12/31/95.

Bubbly Flow Dynamics and Numerical Implementation in Complex Flows

$707,701 2/1/96-6/30/2000.

The Modeling of Two-Phase Flow Around Ship Hulls

$900,841 July 1, 2001 - June 30, 2006 The Modeling of Two-Phase Flow Around Ship Hulls

$1,1280,000. July 1,2006 - June 30, 2010.

EG&G An Investigation of Turbine-Meter Drag Disc Devices in Transient Two-Phase Flow

$11,000 10/1/76-9/30/77.

Analysis of BWR Inlet Flow

$20,000 10/1/77-9/30/78.

An Investigation of Turbine-Meter Drag Disc Devices in Transient Two-Phase Flow

$121,764 10/15/76-9/30/79.

http://www.rpi.edu/-laheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 54 of 61 Analysis of BWR Inlet Flow

$78,549 211/80-1/31/81.

The Analysis of PNA Techniques

$29,323 2/1/80-2/28/81.

The Development of a Global Transient Model for DTT Rakes

$55,764 10/1/78-9/30/79.

The Analysis of BWR Inlet Flow Blockage using MAYU-4B

$81,258 1/1/80-12/31/80.

NSF Three-Dimensional Turbulence Structure Measurement in Two-Phase Flow

$218,000 3/1/81-11/30/83.

Three-Dimensional Turbulence Structure Measurements in Two-Phase Flow

$78,800 5/1/82-4/30/83.

Three-Dimensional Turbulence Structure in Two-Phase Flow Measurements

$77,700 5/1/83-4/20/84.

Phase Separation -Mechanisms in .Branching Conduits

$175,000 12/1/84-1/31/87.

Phase Distribution Phenomena in Complex Geometry Conduits

$85,655 3/1/88-2/28-89.

A Study of Phase Separation in Branching Conduits

$95,000 2/1/89-1/31/90.

Phase Distribution Phenomena in Multiphase Systems

$88,446 9/1/89-8/31/90.

The Modeling of Two-Phase Turbulence

$252,351 11/1/01 -10/31/04 ORNL The Development of Mechanistic Models for the MARCH-based Analysis of BWR Cores

$30,950 9/1/81-8/31/82.

http://www.rpi.edu/-Iaheyr/laheyvita.htm/ 9/8/2010

Dr. Richard T. Lahey Page 55 of 61 The Development of Mechanistic Models for the MARCH-based Analysis of BWR Cores

$117,990 9/1/81-8/31/83.

The Development of Mechanistic BWR Hydraulics and Structural Component Failure Models for the MARCH Code

$46,000 9/1/82-8/31/83.

Development of Improved Models for BWR Thermal-Hydraulics and Core Degradation Phenomena

$170,748 9/1/83-8/31/85.

Perform Bubble Fusion Analysis and Experiments at RPI and ORNL

$95,000 4/3/98-9/30/99.

Analysis of Sonoluminescence/Sonofusion Phenomena to Support ORNL Experiments

$164,784, 7/28/99-7/27/2003.

Westinghouse The Analysis of Thermal-Hydraulic Instabilities in Quad-Plus Fuel

$97,445 9/1/81-8/31/82.

EPRI The Development of Analytical Modules for Nuclear Reactor Simulators

$49,085 6/1/81-5/31/82.

Workshop on Two-Phase Flow Fundamentals

$15,000 9/1/86-6/30/87.

ESEERCO An Analysis of BWR/4 and BWR/5 Pressure Boundary Failure Modes During Core Meltdown and Its Impact on Mark-Il Containment

$304,667 2/1/84-1/31/86.

The Propagation and Failure Modes in Severely Degraded BWR Cores

$210, 568 9/1/85-8/31/86.

Degraded BWR Code Modeling: Radionuclide Transport and Additional Thermal Hydraulics Models for the APRIL Code

$399,608 6/1/87-5/31/88.

Modeling and Analysis of Severe Accidents in BWRs Using the APRIL http://www.rpi.edu/-laheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 56 of 61 Computer Code

$356,712 1/1/90-12/31/90.

Degraded BWR Code Modeling: The Upgrading and Validation of APRIL as an Interactive Computer Code for BWR Severe Accident Analysis

$428,862 1/1/92-12/31/92.

USDOE An Analysis of the Closure Conditions for Two-Fluid Models of Two-Phase Flow

$115,000 4/1/86-3/31/87.

Workshop on Two-Phase Flow Fundamentals

$98.000 9/1/86-6/30/87.

An Investigation of the Closure Conditions for Two-Fluid Models of Two-Phase Flow

$120,000 4/1/87-3/31/88.

An Analysis of the Closure Conditions for Two-Fluid Models of Two-Phase Flow

$120,000 4/1/88-3/31/89.

The Continuum Modeling of Two-Phase Systems

$532,088 4/1/89-3/31/93.

A Nonintrusive Measurement System for Multiphase Flows

$134,549 6/30/89-6/29/90.

Analysis of Nuclear Reactor Instability Phenomena

$83,278 6/1/91-5/31/92.

The Continuum Modeling of Two-Phase Systems

$128,000 4/1/92-3/31/93.

Analysis of Nuclear Reactor Instability Phenomena

$88,384 4/15/93-4/14/94.

The Development of Multidimensional Two-Fluid Modeling Capabilities

$129,551 4/1/94-3/31/97.

Multidimensional Analysis of Bubble Dynamics Associated with Bubble Fusion Phenoma

$404,203 7/1/99-6/30/2002.

KAPL The Development of Improved Models for BWR Thermal-Hydraulics and Core Degradation Phenomena httpl://www.rpi-.edu/-'Iaheyr/laheyvita.htmi //01 9/8/2010

Dr. Richard T. Lahey Page 57 of 61

$50,000 9/1/85-8/31/85.

Turbulent Phenomena in Two-Phase Flows

$32,000 4/15/86-4/14/87.

The Development of Improved Models for BWR Thermal-Hydraulics and Core Degradation Phenomena

$14,997 9/1/86-8/31/87.

A Review of KAPL Methodology in the Area of Multiphase Flow and Heat Transfer

$30,163 7/8/91-7/7/92.

The Mechanistic Analysis of Critical Heat Flux Using Two-Fluid Models

$73,796 4/1/93-9/30/93.

The Mechanistic Analysis of Critical Heat Flux Using Two-Fluid Models

$184,529 10/1/93-9/30/94.

The Mechanistic Analysis of CritiCal Heat-Flux Using Two-Fluid Models

$149,080. 10/1/94-9/30/95.

The Mechanistic Analysis of Critical Heat Flux Using Two-Fluid Models

$80,300 12/1/95-4/30/96.

The Analysis of Annular Two-Phase Flows

$227,049 7/1/03-6/30/06 CAAPS Enabling Technology for Multiphase Flow Food Processing

$48,927 9/1/92-8/31/93.

Enabling Technology for Multiphase Flow Food Processing

$51,305 9/1/93-8/31/94.

Enabling Technology for Multiphase Flow Food Processing

$54,333 9/1/94-8/31/95.

NASA The Analysis of Phase Distribution Phenomena in Microgravity Environments

$119,438 5/1/92-4/30/93.

The Analysis of Phase Distribution Phenomena in. Microgravity Environments http://www.rpi.edu/-laheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 58 of 61

$120,000 12/1/93-11/30/95.

The Analysis of the Effect of Gravity on Multiphase Flows

$396,544 7/26/04 - 9/30/07 GE Two-Phase Flow Analysis

$10,152 7/15/92-11/1/92.

Two-Phase Flow Analysis

$24,180 12/14/92-3/1/93.

The Development of Multidimensional Modeling Capabilities for Annular Flows in Heated Assemblies

$203,756 8/1/96-9/1/98.

Master's Degrees Completed

" Vea, Henry W., "An Exact Analytical Solution of Pool Swell Dynamics During Depressurization by the Method of Characteristics" (1977)

" Kamath, Pradeep, "A Turbine Meter Evaluation Model for Two-Phase Transients" (1977)

Sim, Suk Ku, "An Analysis of Phase Distribution Mechanisms in Turbulent Two-Phase Pipe Flow" (1977)

" Cheng, Lap-Yan, "Virtual Mass Effects in Two-Phase Flow" (1977)

" Saba, Nematollah, "An Experimental Technique for the Determination of Steam/Air Fraction" (1977)

Ohkawa, Katsu, "The Analysis of BWR Inlet Flow Blockage" (1978)

Schell, Susan, "The Development of A Sid-Scatter Gamma Ray Technique for the Measurement of Void Fraction" (1978)

Lombardo, Nicholas, "The Instrumentation and Data Processing of a Large Freon Loop (1978)

Honan, Timothy J., "Phase Separation in Wyes and Tees" (1978)

Shum, Feibiu, "The Development of a 4-Equation Drift-Flux Computer Code (DRIFT-4)" (1978)

Drozd, Andrew, "NUFREQ-S: A Frequency Domain Drift-Flux Technique for the Evaluation of the Thermal-Hydraulic Stability of Boiling Systems" (1980)

Ostrogorsky, Alexander ,"The Analysis of Countercurrent Two-Phase Flow Pressure Drop and CCFL Breakdown in Diabatic and Adiabatic Conduits" (1980)

Nissley, Mitchell ,"The Analysis of Proposed BWR Inlet Blockage Experiments Using MAYU-4b" (1981)

" Antal, Steven, "An Evaluation of Boiling Water Nuclear Reactor Stability Using Systems Pressure Perturbation (1982)

" Balaram, J., "Stability Margins for Boiling Water Nuclear Reactors: A Multi-Input Multi-Output Analysis" (1982) http://www.rpi.edu/-laheyr/laheyvita.htm I 9/8/2010

Dr. Richard T. Lahey .Page 59 of 61

Shatas, Jr., Joseph F.., "A Streak Photography Method for Use in Two-Phase Flow" (1982)

Lee, Sung Jin, "The Development of a Digital Data Processing. System for Two-Phase Turbulence Data" .(1982)

Sterner, R.W., "Air/Water Subchannel Measurements of the Equilibrium Quality and Mass Flux Distribution in a Rod Bundle" (1983)

Petzold, J.F., "Mathematical Modeling of U-Tube Steam Generator Dynamics for Slow Transients and Small Break for Loss-of-Coolant Accidents (1983)

Koh, Byung R., "The Model of Emergency Core Cooling Systems for Severe Accident Analysis of Boiling Water Reactors (BWRs)" (1984)

Bryam, Morris, "Modification of Brookhaven National Lab BWR Plant Analyzer to Accommodate BWR-2 Design of Nine Mile Point-1 Nuclear Power Station" (1987)

Campanella, Rick, "Wave Propagation Phenomena in Bubbly Two-Component Two-Phase Flows" (1988)

Kalkach-Navarro, Susana, "A Mechanistic Analysis of Phase Separation in Branching Conduits Using Three-Dimensional Two-Fluid Models" (1988)

. Kimpland, Robert, "A Phenomenological Model for the Prediction of Phase Separation in Branching Conduits" (1990)

Haley, Thomas C., "A Characteristic Analysis of Mathematical Models of Two-Phase Flow in One Space Dimension" (1990)

Mayo, Stephen, "Void-Fraction and Velocity Measurements in Three-Phase Flow Using a Hot-Film Anemometer" (1994)

Potterf, Samuel, "Modeling of Heat Transfer Through Stratified Multiphase Flow in a Horizontal Pipe Using Drift-Flux Techniques, with Special Applications to Aseptic Food Processing" (1995)

" Bolotnov, I., "A Non-Linear Spectral Model for Bubble-Induced Turbolent Viscosity in Bubbly Two-Phase Flow" (2003)

"Saglime, Frank, "Experimental Results for the RPI Bubble Fusion Project" (2004) e Trofimova , Alisa, "The Direct Numerical Simulation of Turbulent Channel Flows" (2007)

In Progress

None Doctoral Completed

Vince, Mark A., "Flow Regime Identification and Void Fraction Measurement Techniques in Two-Phase Flow" (1980)

. Kamath, Pradeep, "The Transient Analysis of DDT Rakes" (1981)

" Saba, Nematollah, "Phase Separation Phenomena in Branching Conduits (1981)

Perez-Griffo, Maria, "Analysis of the Pulsed Neutron Activation Technique (1981)

Conlon, William M., "An Experimental Investigation of Boiling Water Nuclear Reactor parallel Channel Effects during a Postulate Loss-of-Coolant Accident (1982)

Taleyarkhan, Rusi P., "An Analysis of Density-Wave Oscillations in Ventilated Channels (1982)

Ohkawa, Katsuhiro, "The Development of a Gamma-Ray Scattering Densitometer and its Application to the Measurement of Two-Phase Density Distribution in an Annular Test Section" (1983)

Cheng, Lap-Yan, "An Analysis of Wave Dispersion, Sonic Velocity and Critical Flow in Two-Phase Mixtures" (1983) http://www.rpi.edu/-laheyr/laheyvita.html 9/8/2010

Dr. Richard T. Lahey Page 60 of 61

Park, Goon C., "The Development of NUFREQ-N, an Analytical Model for the Stability of Nuclear Coupled Density-Wave Oscillations in Boiling Water Nuclear Reactors" (1983)

Fakory, Mohammad,, "Parallel Channel Effects and Long-Term Cooling During Emergency Core Cooling in a BWR/4" (1984)

Peng, Shie-Jeng, "NUFREQ-NP - A Digital Computer Code for the Linear Stability Analysis of Boiling Water Nuclear Reactors" (1984)

Lin, Thomas Fu Yuan, "An Application of Pulsed Photon Activation Technique in Single-and Two-Phase Flow Measurements (1984)

.. Bukhari, Khalid M., "Phase Separation and Distribution Phenomena in a Two-Dimensional Test Section" (1985)

Wang, Shou-Kong, "Three-Dimensional Turbulence Structure Measurements in Air/Water Two-Phase Flow" (1985)

Koh, Byung R., "The Modeling of BWR Thermal-Hydraulics for Severe Accident Analysis (1986)

Sim, Suk K., "Phase Distribution Phenomena in Triangular Conduits (1986)

Hwang, Sun-Tack, "A Study on Phase Separation in Branching Conduits" (1986)

Lee, Sung-Jin,"Turbulence Modeling in Bubbly Two-Phase Flows" (1986) e Ruggles, Arthur E., "The Propagation of Pressure Perturbations in Bubbly Air/Water Flows" (1987)

Kim, Seok H. ,"The Modeling and Analysis of BWR Severe Accidents (1987)

Arnold, Gary S., "Entropy and Objectivity as Constraints Upon Constitutive Equations for Two-Fluid Modeling of Multiphase Flows" (1988)

SiAhmed, El-Khider, "An Experimental and Theoretical Investigation of Melt Propagation in a Rubble Bed with Applications to Degraded Nuclear Reactor Cores" (1988)

Kim, Dong-Ha, "An Analysis of Corium/Structure Interaction during Severe Accidents in Boiling Water Nuclear Reactors" (1990)

Lopez de Bertodano, Martin, "Turbulent Bubbly Two-Phase Flow in a Triangular Duct" (1992)

Park, Jee-WonI"Void Wave Propagation in Two-Phase Flow" (1992)

Cho, Chang-Sok, "Modeling and Analysis of Radionuclide Transport during Severe Accidents in Boiling Water Nuclear Reactors" (1992)

Valenti (Kalkach-Navarro), Susana, "The Mathematical Modeling of. Flow Regime Transition in Bubbly Two-Phase Flows" (1992)

Jia, Hong, "Multidimensional Effects During Corium Spreading and Corium-Concrete Interaction in BWRs" (1992)

Yoon, Juh-Yeon.,"A Streamline Upwinding Finite Element Method for Multiphase Flow and Heat Transfer Analysis" (1993)

Antal, Stephen P., "Phase Distribution in Bubbly Two-Phase Flows" (1994)

Alajbegovic, Ales, "Phase Distribution and Turbulence Structure for Solid/Fluid Upflow in a Pipe (1994)

Chang, Chin-Jang, "The Analysis of Chaotic Instabilities in Boiling Systems" (1994)

Kim., Shin-Whan, "Computer Simulation of Severe Accidents in Boiling Water Nuclear Reactors" (1994)

Assad, Amir, "An Experimental Study of Phase Distribution and Turbulence Structure for Solid/Liquid Flow in Horizontal and Vertical Pipes" (1995)

" Garea, Veronica B., "Nodal Analysis of Two-Phase Flow Instabilities" (1998)

" Moraga, Francisco, "Lateral Forces on Rigid Spheres in a Turbulent Uniform Shear Flow" (1998)

" Nigmatulin, Tagir,."An Experimental and Theoretical Study of Interfacial Area Density for different Two-Phase Flow Regimes" (1999)

Bae, Song H., "A Theoretical Investigation of the Dynamics of Single Bubble http://www.rpi.edu/--laheyr/laheyvita.html //21 9/8/2010

Dr. Richard T. Lahey Page 61 of 61 Sonoluminescence" (1999)

" Delgadino, Gerardo, "The Dynamics of Single Bubble Sonolominescence" (1999)

" Singhal, Maneesh, "The Effect of Dispersed Phase Buoyancy on Phase Distribution" (2004)

Yin, Juan, "Modeling and Analysis of Multiphase Instabilities" (2004)

Cancelos, Silvina, "Effect of Acoustically-Induced Pressures on the Permeability of a Bullfrog Urinary Bladder" (2007)

Galimov ,.Azat, "An Analysis of Interfacial Waves and Air Ingestion Mechanisms" (2007)

Bolotnov, Igor, "Cascade Modeling of Single and Two-Phase Turbulence" (2008)

Ortega-Gomez, Tino, "Stability Analysis for High Performance Light Water Reactor" - U.

Karlsruhe, Germany (2008)

Rodriguez, Joseph M., "Numerical Simulation of Two-Phase Annular Flow" (2009)

Schlichting, William R., " An Analysis of the Effect of Gravity on Interacting DWO/PDO Instability Modes" (2009)

In Progress

Markus Stokmaier (FZK) http://www.rpi.edu/-,aheyr/laheyvita.html 9/8/2010

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD

X In re: Docket Nos. 50-247-LR and 50-286-LR License Renewal Application Submitted by ASLBP No. 07-858-03-LR-BDO1 Entergy Nuclear Indian Point 2, LLC, DPR-26, DPR-64 Entergy Nuclear Indian Point 3, LLC, and Entergy Nuclear Operations, Inc. September 15, 2010 x

CERTIFICATE OF SERVICE I hereby certify that on September^ 2010, copies of(1) the State of New York's Motion for Leave to File Additional Bases For Previously-Admitted Contention NYS-25, (2) the State of New York's Additional Bases For Previously-Admitted Contention NYS-25, and (3) Declaration of Dr. Richard Lahey were served upon the following persons via U.S. Mail and e-mail at the following addresses:

Lawrence G. McDade, Chair Kaye D. Lathrop Administrative Judge Administrative Judge Atomic Safety and Licensing Board Panel Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Mailstop 3 F23 190 Cedar Lane E.

Two White Flint North Ridgway, CO 81432 11545 Rockville Pike Kaye.Lathrop@nrc.gov Rockville, MD 20852-2738 Lawrence.McDade@nrc.gov Atomic Safety and Licensing Board Panel U.S. Nuclear Regulatory Commission Richard E. Wardwell Mailstop 3 F23 Administrative Judge Two White Flint North Atomic Safety and Licensing Board Panel 11545 Rockville Pike U.S. Nuclear Regulatory Commission Rockville, MD 20852-2738 Mailstop 3 F23 Two White Flint North Joshua A. Kirstein, Esq., Law Clerk 11545 Rockville Pike Atomic Safety and Licensing Board Panel Rockville, MD 20852-2738 U.S. Nuclear Regulatory Commission Richard.Wardwell@nrc.gov Mailstop 3 F23 Two White Flint North 11545 Rockville Pike Rockville, MD 20852-2738 Josh.Kirstein@nrc.gov 1

Office of Commission Appellate Martin J. O'Neill, Esq.

Adjudication Morgan, Lewis & Bockius LLP U.S. Nuclear Regulatory Commission Suite 4000 Mailstop 16 G4 1000 Louisiana Street One White Flint North Houston, TX 77002 11555 Rockville Pike martin.o'neill@morganlewis.com Rockville, MD 20852-2738 ocaamail@nrc.gov Elise N. Zoli. Esq.

Goodwin Procter, LLP Office of the Secretary Exchange Place Attn: Rulemaking and Adjudications Staff 53 State Street U.S. Nuclear Regulatory Commission Boston, MA 02109 Mailstop 3 F23 ezoli@goodwinprocter.com Two White Flint North 11545 Rockville Pike William C. Dennis, Esq.

Rockville, MD 20852-2738 Assistant General Counsel hearingdocket@nrc. gov Entergy Nuclear Operations, Inc.

440 Hamilton Avenue Sherwin E. Turk, Esq. White Plains, NY 10601 David E. Roth, Esq. wdennis@entergy.com Andrea Z. Jones, Esq.

Beth-N. Mizuno, Esq. Robert D. Snook, Esq.

Brian G. Harris, Esq. Assistant Attorney General Office of the General Counsel Office of the Attorney General U.S. Nuclear Regulatory Commission State of Connecticut Mailstop 15 D21 55 Elm Street One White Flint North P.O. Box 120 11555 Rockville Pike Hartford, CT 06141-0120 Rockville, MD 20852-2738 robert.snook@ct.gov sherwin.turk@nrc.gov andrea.j ones@nrc.gov Gregory Spicer, Esq.

david.roth@nrc.gov Assistant County Attorney beth.mizuno@nrc.gov - Office of the Westchester County Attorney brian.harris@nrc.gov Michaelian Office Building 148 Martine Avenue, 6th Floor Kathryn M. Sutton, Esq. White Plains, NY 10601 Paul M. Bessette, Esq. gss 1@westchestergov.com Mauri T. Lemoncelli, Esq.

Morgan, Lewis & Bockius LLP Daniel E. O'Neill, Mayor 1111 Pennsylvania Avenue, NW James Seirmarco, M.S.

Washington, DC 20004 Village of Buchanan ksutton@morganlewis.com Municipal Building pbessette@morganlewis.com 236 Tate Avenue mlemoncelli@morganlewis.com Buchanan, NY 10511-1298 vob@bestweb.net 2

Daniel Riesel, Esq. Stephen Filler, Esq.

Thomas F. Wood, Esq. Board Member Jessica Steinberg, Esq. Hudson River Sloop Clearwater, Inc.

Sive, Paget & Riesel, P.C. Suite 222 460 Park Avenue 303 South Broadway New York, NY 10022 Tarrytown, NY 10591 driesel@sprlaw.com sfiller@nylawline.com j steinberg@sprlaw.com Ross H. Gould Michael J. Delaney, Esq. Member Vice President - Energy Department Hudson River Sloop Clearwater, Inc.

New York City Economic Development 10 Park Ave, #5L Corporation (NYCEDC) New York, NY 10016 110 William Street rgouldesq@gmail.com New York, NY 10038 mdelaney@nycedc.com Phillip Musegaas, Esq.

Deborah Brancato, Esq.

Manna Jo Greene, Director Riverkeeper, Inc.

Hudson River Sloop Clearwater, Inc. 20 Secor Road 112 Little Market St. Ossining, NY 10562 Poughkeepsie, NY 12601 phillip@riverkeeper.org Mannaj o@clearwater.org dbrancato@riverkeeper.org John J. Sipos Dated at Albany, New York this 15th day of September 2010 3

@@ Line 2: / Line 2: @@
 | number = ML103050402
 | issue date = 09/15/2010
-| title = 2010/09/15-State of New York'S Motion for Leave to File Additional Bases for Previously-Admitted Contention NYS-25 in Response to Entergy'S July 14, 2010 Proposed Aging Management Program for Reactor Pressure Vessels & Internal Components
+| title = State of New York'S Motion for Leave to File Additional Bases for Previously-Admitted Contention NYS-25 in Response to Entergy'S July 14, 2010 Proposed Aging Management Program for Reactor Pressure Vessels & Internal Components
 | author name = Sipos J
 | author affiliation = State of NY, Office of the Attorney General
@@ Line 18: / Line 18: @@
 {{#Wiki_filter:DOCKETED September 16, 2010 (8:30am).
 OFFICE OF 'SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF UNITED STATES NUCLEAR REGULATORY COMMISSION ATOMIC SAFETY AND LICENSING BOARD
--- - - - - .- .- .- .- ..- - . - . - . - - .- .- ..- - . - . - . - . - . - . --------..
                                                                                . .. -. . .X In re:                                                                                     Docket Nos. 510-247-LR; 50-286-LR License Renewal Application Submitted by                                                   ASLBP No. 0' 7-858-03-LR-BDO1 Entergy Nuclear Indian Point 2, LLC,                                                       DPR-26, DPR -64 Entergy Nuclear Indian Point 3, LLC, and Entergy Nuclear Operations, Inc.                                                           September 15, 2010
 ------------------------------------------                                               x STATE OF NEW YORK'S MOTION FOR LEAVE TO FILE ADDITIONAL BASES FOR PREVIOUSLY-ADMITTED CONTENTION NYS-25 IN RESPONSE TO ENTERGY'S JULY 14, 2010 PROPOSED AGING MANAGEMENT PROGRAM FOR REACTOR PRESSURE VESSELS AND INTERNAL COMPONENTS A. Introduction Pursuant to 10 C.F.R. &sect; 2.309(f)(2) the State of New York seeks leaveto file the attached Additional Bases for Previously-Admitted Contention NYS-25. The Additional Bases are based on Entergy's filing with the Board of a proposed aging management program concerning the embrittlement of reactor pressure vessels (or RPV) and internal components, which was filed in an attempt to meet its obligations under 10 C.F.R. &sect; 54.51 (c)(1)(iii) with regard to RPV and internal components. 1 Entergy's initial License Renewal Application did not contain an aging management program concerning the embrittlement of reactor pressure vessels and internal components. On July 14, 2010 Entergy provided NRC Staff with the Ninth Amendment to the Indian Point License Renewal Application. That amendment, denominated NL-10-063, contained a description of an entirely new aging management program that did not exist before.
@@ Line 169: / Line 168: @@
           .18. In addition, because of geometric considerations, many PWRs
 .(including IP-2 and IP-3) can not meet the USNRC's required minimum coverage for the non-destructive testing (NDT) of these important J-groove welds [Walpole, 20091, and thus the integrity of these stub tube welds can not be confirmed.. It
--appears-tha-t-to helpadd ress-this-chroniczproblem-Entergy has ordered two new RPV heads [Telecon-USNRC/Entergy Report, March 18, 2008], but they have not yet been scheduled for installation at Indian Point [Telecon-USNRC/Entergy, March 18, 2008]]. In any event, unlike the rather superficial treatment given this important safety concern by Entergy [ NL-10-063], I believe that a tangible, enforceable, and viable aging management program must developed and implemented before re-licensing the Indian Point reactor plants for extended operations since the integrity of these welds must be assured. If not, due to the leakage of borated primary coolant through cracked welds, there can be aggressive corrosion and wasting of the unclad outer surface of the upper head of the RPV 14                        September 15, 2010 Lahey Declaration
+-appears-tha-t-to helpadd ress-this-chroniczproblem-Entergy has ordered two new RPV heads [Telecon-USNRC/Entergy Report, March 18, 2008], but they have not yet been scheduled for installation at Indian Point [Telecon-USNRC/Entergy, March 18, 2008)). In any event, unlike the rather superficial treatment given this important safety concern by Entergy [ NL-10-063], I believe that a tangible, enforceable, and viable aging management program must developed and implemented before re-licensing the Indian Point reactor plants for extended operations since the integrity of these welds must be assured. If not, due to the leakage of borated primary coolant through cracked welds, there can be aggressive corrosion and wasting of the unclad outer surface of the upper head of the RPV 14                        September 15, 2010 Lahey Declaration
 (such as the serious event that occurred at Davis-Besse and was identified in 2002).

ML103050402: Difference between revisions

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