Y 3.N 88:25/0713/V.19
OCCUPATIONAL RADIATION EXPOSURE AT COMMERCIAL NUCLEAR POWER REACTORS AND OTHER FACILITIES 1997 ... NUREG-0713, VOL. 19... U.S. NUCLEAR REGUL
1051-H-11
990408M
990430
Y 3.N 88:25/4219/V.14/NO.1
HEAVY-SECTION STEEL TECHNOLOGY PROGRAM... SEMIANNUAL PROGRESS REPORT FOR OCT. 1996-MAR. 1997 ... NUREG/CR-4219, VOL. 14, NO. 1... U.S. NUCLE
Y 3.N 88:25/4667/V.25
ENVIRONMENTALLY ASSISTED CRACKING IN LIGHT-WATER REACTORS... SEMIANNUAL REPORT JULY 1997-DEC. 1997 ... NUREG/CR-4667, VOL. 25... U.S. NUCLEA
Y 3.N 88:25/5372
EXPERIMENTS ON INTERACTIONS BETWEEN ZIRCONIUM- CONTAINING MELT AND WATER.... NUREG/CR-5372... U.S. NUCLEAR REGULATORY COMMISSION
Y 3.N 88:25/5392
ELEMENTS OF AN APPROACH TO PERFORMANCE-BASED REGULATORY OVERSIGHT... NUREG/CR-5392... U.S. NUCLEAR REGULATORY COMMISSION
Y 3.N 88:25/5485
GUIDELINES ON MODELING COMMON-CAUSE FAILURES IN PROBABILISTIC RISK ASSESSMENT... NUREG/CR-5485... U.S. NUCLEAR REGULATORY COMMISSION
Y 3.N 88:25/5496
EVALUATION OF LOSS OF OFFSITE POWER EVENTS AT NUCLEAR POWER PLANTS:  1980-1996... NUREG/CR-5496... U.S. NUCLEAR REGULATORY COMMISSION
Y 3.N 88:25/5497
COMMON-CAUSE FAILURE PARAMETER ESTIMATIONS... NUREG/CR-5497... U.S. NUCLEAR REGULATORY COMMISSION
Y 3.N 88:25/5501
ADVANCED INSTRUMENTATION AND MAINTENANCE TECHNOLOGIES FOR NUCLEAR POWER PLANTS... NUREG/CR-5501... U.S. NUCLEAR REGULATORY COMMISSION
Y 3.N 88:25/5504
TECHNICAL BASIS FOR AN ASTM STANDARD ON DETERMINING THE REFERENCE TEMPERATURE, To, FOR FERRITIC STEELS IN THE TRANSITION... NUREG/CR-5504 ..
Y 3.N 88:25/5505
RR-PRODIGAL - A MODEL FOR ESTIMATING THE PROBABILITIES OF DEFECTS IN REACTOR PRESSURE VESSEL WELDS... NUREG/CR-5505... U.S. NUCLEAR REGULATO
Y 3.N 88:25/5534
CRITICAL HEAT FLUX (CHF) PHENOMENON ON A DOWNWARD FACING CURVED SURFACE: EFFECTS OF THERMAL INSULATION... NUREG/CR-5534... U.S. NUCLEAR REGU
Y 3.N 88:25/5549
ENVIRONMENTAL ASSESSMENT RENEWAL OF MATERIALS LICENSES FOR ALARON CORP. NORTHEAST REGIONAL SERVICE FACILITY, WAMPUM, PA... NUREG/CR-5549...
Y 3.N 88:25/5559
SINGLE- AND CROSS-HOLE PNEUMATIC TESTS IN UNSATURATED FRACTURED TUFFS AT THE APACHE LEAP RESEARCH SITE: PHENOMENOLOGY..., NUREG/CR-5559 ...
Y 3.N 88:25/5570
APPLICATION OF THE NCSA HABANERO TOOL FOR COLLABORATION ON STRUCTURAL INTEGRITY ASSESSMENTS ... NUREG/CR-5570... U.S. NUCLEAR REGULATORY COM
Y 3.N 88:25/5621
GROUNDWATER MODELS IN SUPPORT OF NUREG/CR-5512 ... NUREG/CR-5621... U.S. NUCLEAR REGULATORY COMMISSION
Y 3.N 88:25/6131
VICTORIA 2.0: A MECHANISTIC MODEL FOR RADIONUCLIDE BEHAVIOR IN A NUCLEAR REACTOR COOLANT SYSTEM UNDER SEVERE ACCIDENT CONDITIONS... NUREG/CR
Y 3.N 88:25/6210/SUPP.1
COMPUTER CODES FOR EVALUATION OF CONTROL ROOM HABITABILITY (HABIT V1.1)... NUREG/CR-6210, SUPP. 1... U.S. NUCLEAR REGULATORY COMMISSION
Y 3.N 88:25/6274
PALEOSEISMIC STUDIES IN THE SOUTHEASTERN UNITED STATES AND NEW ENGLAND... NUREG/CR-6274... U.S. NUCLEAR REGULATORY COMMISSION
Y 3.N 88:25/6408
TECHNICAL ASSISTANCE IN REVIEW OF SOURCE TERM- RELATED ISSUES OF ADVANCED REACTORS... NUREG/CR-6408... U.S. NUCLEAR REGULATORY COMMISSION
Y 3.N 88:25/6418
RISK IMPORTANCE OF CONTAINMENT AND RELATED ESF SYSTEM PERFORMANCE REQUIREMENTS... NUREG/CR-6418... U.S. NUCLEAR REGULATORY COMMISSION
Y 3.N 88:25/6417/V.1
CHARACTERIZATION OF FLAWS IN U.S. REACTOR PRESSURE VESSELS... DENSITY AND DISTRIBUTION OF FLAW INDICATIONS IN PVRUF... NUREG/CR-6471, VOL. 1
Y 3.N 88:25/6475
RESOLUTION OF THE DIRECT CONTAINMENT HEATING ISSUE FOR COMBUSTION ENGINEERING PLANTS AND BABCOCK & WILCOX PLANTS... NUREG/CR-6475... U.S. NU
Y 3.N 88:25/6511/V.4
STEAM GENERATOR TUBE INTEGRITY PROGRAM... ANNUAL REPORT OCTOBER 1996 - SEPTEMBER 1997... NUREG/CR-6511, VOL. 4... U.S. NUCLEAR REGULATORY CO
Y 3.N 88:25/6512
DYNAMIC FRACTURE INITIATION TOUGHNESS OF ASTM A533, GRADE B STEEL PLATE... NUREG/CR-6512... U.S. NUCLEAR REGULATORY COMMISSION
Y 3.N 88:25/6516
PRETEST ANALYSES OF THE STEEL CONTAINMENT VESSEL MODEL... NUREG/CR-6516... U.S. NUCLEAR REGULATORY COMMISSION
Y 3.N 88:25/6524
THE EFFECT OF LATERAL VENTING IN DEFLAGRATION-TO- DETONATION TRANSITION IN HYDROGEN-AIR-STEAM MIXTURES AT VARIOUS INITIAL..., NUREG/CR-6524.
Y 3.N 88:25/6545/V.1&V.2/ERRATA
PROBABILISTIC ACCIDENT CONSEQUENCE UNCERTAINTY ANALYSIS EARLY HEALTH EFFECTS UNCERTAINTY..., ERRATA JULY 1998... NUREG/CR-6545, VOL. 1, VOL.