年 〜
年

検索結果 46 件

Decay Heat Characterization of SRS Research Reactor Fuels WSRCTR9800116 DE98 054560

Decay Heat Characterization of SRS Research Reactor Fuels WSRCTR9800116 DE98 054560
マイクロ規格・テクニカルリポート類
Sindelar, R. L1998<LS-DE98/054560>
国立国会図書館

Creep Analysis of Aluminum-Based Spent Nuclear Fuel in Repository Storage WSRC-MS-98-00231 DE98 052371 CONF-980708

Creep Analysis of Aluminum-Based Spent Nuclear Fuel in Repository Storage WSRC-MS-98-00231 DE98 052371 CONF-980708
マイクロ規格・テクニカルリポート類
Gong, C, Lam, P. S, Sindelar, R. L1998<LS-DE98/052371>
国立国会図書館

Vacuum Drying Tests for Storage of Aluminum Spent Nuclear Fuel WSRC-MS-97-00769 DE98 051097 CONF-980516

Vacuum Drying Tests for Storage of Aluminum Spent Nuclear Fuel WSRC-MS-97-00769 DE98 051097 CONF-980516
マイクロ規格・テクニカルリポート類
Chen, K. F, Large, W. S, Sindelar, R. L1998<LS-DE98/051097>
国立国会図書館

Vapor Corrosion of Aluminum Cladding Alloys WSRCMS9800333 DE98 054510

Vapor Corrosion of Aluminum Cladding Alloys WSRCMS9800333 DE98 054510
マイクロ規格・テクニカルリポート類
Lam, P. S, Sindelar, R. L, Peacock, H. B1998<LS-DE98/054510>
国立国会図書館

Vapor corrosion of aluminum cladding alloys and aluminum-uranium fuel materials in storage environments WSRC-TR-97-0120 DE97 060228

Vapor corrosion of aluminum cladding alloys and aluminum-uranium fuel materials in storage environments WSRC-TR-97-0120 DE97 060228
マイクロ規格・テクニカルリポート類
Lam, P, Sindelar, R. L, Peacock, H. B1997<LS-DE97/060228>
国立国会図書館

Corrosion performance of alloy G3 and 304L stainless steel in simulated high level waste solutions and assessment of service life of evaporator tubes WSRC-MS-95-0470 DE96 009641 CONF-96038912

Corrosion performance of alloy G3 and 304L stainless steel in simulated high level waste solutions and assessment of service life of evaporator tubes WSRC-MS-95-0470 DE96 009641 CONF-96038912
マイクロ規格・テクニカルリポート類
Chandler, G. T, Sindelar, R. L, Gupta, N. K, Mickalonis, J. I1996<LS-DE96/009641>
国立国会図書館

Corrosion of aluminum alloys in simulated dry storage environments WSRC-MS-95-0447 DE96 006492 CONF-9603898

Corrosion of aluminum alloys in simulated dry storage environments WSRC-MS-95-0447 DE96 006492 CONF-9603898
マイクロ規格・テクニカルリポート類
Peacock, H. B., Jr, Sindelar, R. L, Lam, P. S1996<LS-DE96/006492>
国立国会図書館

Temperature and humidity effects on the corrosion of aluminum-base reactor fuel cladding materials during dry storage WSRC-MS-95-0354 DE96 003361 CONF-95092537

Temperature and humidity effects on the corrosion of aluminum-base reactor fuel cladding materials during dry storage WSRC-MS-95-0354 DE96 003361 CONF-95092537
マイクロ規格・テクニカルリポート類
Peacock, H. B, Sindelar, R. L, Lam, P. S1995<LS-DE96/003361>
国立国会図書館

Experiments for evaluation of corrosion to develop storage criteria for interim dry storage of aluminum-alloy clad spent nuclear fuel WSRC-MS-94-0564 DE95 002691 CONF-94120712

Experiments for evaluation of corrosion to develop storage criteria for interim dry storage of aluminum-alloy clad spent nuclear fuel WSRC-MS-94-0564 DE95 002691 CONF-94120712
マイクロ規格・テクニカルリポート類
Peacock, H. B, Sindelar, R. L, Lam, P. S, Murphy, T. H1994<LS-DE95/002691>
国立国会図書館

Transitioning aluminum clad spent fuels from wet to interim dry storage WSRC-MS-94-0617 DE95 006455 CONF-950570-12

Transitioning aluminum clad spent fuels from wet to interim dry storage WSRC-MS-94-0617 DE95 006455 CONF-950570-12
マイクロ規格・テクニカルリポート類
Louthan, M. R. Jr, Iyer, N. C, Sindelar, R. L, Peacock, H. B. Jr1994<LS-DE95/006455>
国立国会図書館

Evaluation of degradation during interim dry storage of aluminum-clad fuels WSRC-MS-94-0619 DE95 006456 CONF-95057011

Evaluation of degradation during interim dry storage of aluminum-clad fuels WSRC-MS-94-0619 DE95 006456 CONF-95057011
マイクロ規格・テクニカルリポート類
Sindelar, R. L, Caskey, G. R. Jr, Peacock, H. B. Jr, Lam, P. S1994<LS-DE95/006456>
国立国会図書館

Acceptance criteria for interim dry storage of aluminum-clad fuels WSRC-MS-94-0618 DE95 006454 CONF-95057010

Acceptance criteria for interim dry storage of aluminum-clad fuels WSRC-MS-94-0618 DE95 006454 CONF-95057010
マイクロ規格・テクニカルリポート類
Sindelar, R. L, Peacock, H. B. Jr, Iyer, N. C, Louthan, M. R. Jr1994<LS-DE95/006454>
国立国会図書館

Decay Heat Characterization of SRS Research Reactor Fuels (WSRC ; WSRC-TR-98-00116)

Decay Heat Characterization of SRS Research Reactor Fuels (WSRC ; WSRC-TR-98-00116)
紙図書
Sindelar, R.L.Westinghouse Savannah River Company1998.1.31.
全国の図書館

LIMITS ON ANNULUS AIR OUTAGES IN TYPES 1, 2, AND 3 WASTE TANKS (WSRC ; WSRC-TR-95-0178)

LIMITS ON ANNULUS AIR OUTAGES IN TYPES 1, 2, AND 3 WASTE TANKS (WSRC ; WSRC-TR-95-0178)
紙図書
WIERSMA, B.J.// SINDELAR, R. L. (WESTINGHOUSE SAVANNAH RIVER CO., AIKEN, SC (UNITED STATES))Washington Savannah River Company(Washington Savannah River Company)1995.
全国の図書館

CORROSION OF ALUMINUM ALLOYS IN SIMULATED DRY STORAGE ENVIRONMENTS (WSRC ; WSRC-MS-95-0447)

CORROSION OF ALUMINUM ALLOYS IN SIMULATED DRY STORAGE ENVIRONMENTS (WSRC ; WSRC-MS-95-0447)
紙図書
PEACOCK, H.B. JR.// SINDELAR, R.L.// LAM. P.S. (WESTINGHOUSE SAVANNAH RIVER CO., AIKEN, SC (UNITED STATES))Washington Savannah River Company(Washington Savannah River Company)1996.
全国の図書館

TEMPERATURE AND HUMIDITY EFFECTS ON THE CORROSION OF ALUMINUMBASE REACTOR FUEL CLADDING MATERIALS DURING DRY STORAGE (WSRC ; WSRC-MS-95-0354)

TEMPERATURE AND HUMIDITY EFFECTS ON THE CORROSION OF ALUMINUMBASE REACTOR FUEL CLADDING MATERIALS DURING DRY STORAGE (WSRC ; WSRC-MS-95-0354)
紙図書
PEACOCK, H.B.// SINDELAR, R.L.// LAM, P.S. (WESTINGHOUSE SAVANNAH RIVER CO., AIKEN, SC (UNITED STATES))Washington Savannah River Company(Washington Savannah River Company)1995.
全国の図書館

CORROSION PERFORMANCE OF ALLOY G3 AND 304L STAINLESS STEEL IN SIMULATED HIGH LEVEL WASTE SOLUTIONS AND ASSESSMENT OF SERVICE LIFE OF EVAPORATOR TUBES (WSRC ; WSRC-MS-95-0470)

CORROSION PERFORMANCE OF ALLOY G3 AND 304L STAINLESS STEEL IN SIMULATED HIGH LEVEL WASTE SOLUTIONS AND ASSESSMENT OF SERVICE LIFE OF EVAPORATOR TUBES (WSRC ; WSRC-MS-95-0470)
紙図書
CHANDLER, G.T.// SINDELAR, R.L.// GUPTA, N.K.// MICKALONIS, J.I. (WESTINGHOUSE SAVANNAH RIVER CO., AIKEN, SC (UNITED STATES))Washington Savannah River Company(Washington Savannah River Company)1996.
全国の図書館

REACTOR MATERIALS PROGRAM - WELDMENT COMPONENT TOUGHNESS OF SRS PWS PIPING MATERIALS (WSRC ; WSRC-TR-93-007)

REACTOR MATERIALS PROGRAM - WELDMENT COMPONENT TOUGHNESS OF SRS PWS PIPING MATERIALS (WSRC ; WSRC-TR-93-007)
紙図書
SINDELAR, R.L. (WESTINGHOUSE SAVANNAH RIVER CO., AIKEN, SC (UNITED STATES))Washington Savannah River Company(Washington Savannah River Company)1993.
全国の図書館

REFERENCE FLAW SIZE FOR STRUCTURAL AND FRACTURE ANALYSIS OF TYPES 1 AND 2 WASTE TANKS (WSRC ; WSRC-TR-94-041)

REFERENCE FLAW SIZE FOR STRUCTURAL AND FRACTURE ANALYSIS OF TYPES 1 AND 2 WASTE TANKS (WSRC ; WSRC-TR-94-041)
紙図書
WIERSMA, B.J.// SINDELAR, R.L. (WESTINGHOUSE SAVANNAH RIVER CO., AIKEN, SC (UNITED STATES))Washington Savannah River Company(Washington Savannah River Company)1994.
全国の図書館

EXPERIMENTS FOR EVALUATION OF CORROSION TO DEVELOP STORAGE CRITERIA FOR INTERIM DRY STORAGE OF ALUMINUM-ALLOY CLAD SPENT NUCLEAR FUEL (WSRC ; WSRC-MS-94-0564)

EXPERIMENTS FOR EVALUATION OF CORROSION TO DEVELOP STORAGE CRITERIA FOR INTERIM DRY STORAGE OF ALUMINUM-ALLOY CLAD SPENT NUCLEAR FUEL (WSRC ; WSRC-MS-94-0564)
紙図書
PEACOCK, H.B.// SINDELAR, R.L.// LAM, P.S.// MURPHY, T.H. (WESTINGHOUSE SAVANNAH RIVER CO., AIKEN, SC (UNITED STATES))Washington Savannah River Company(Washington Savannah River Company)1994.
全国の図書館