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Conceptual design report for a transportable DUCRETE spent fuel storage cask system INEL-95/0167 DE95 017516

Conceptual design report for a transportable DUCRETE spent fuel storage cask system INEL-95/0167 DE95 017516
Microform規格・テクニカルリポート類
Hopf, J. E1995<LS-DE95/017516>
National Diet Library

Rev 2 to calculation PGE01.10.02.01.03, "Radiation Source Strengths & Matl Densities for Spent Fuel Basket Analysis."

Rev 2 to calculation PGE01.10.02.01.03, "Radiation Source Strengths & Matl Densities for Spent Fuel Basket Analysis."
Paper図書
HOPF, J. E.SIERRA NUCLEAR, INC.1998/10/29.
Other Libraries in Japan

Redacted rev 0 to "Sensitivity Studies for TranStor Storage Cask Shielding Analyses."

Redacted rev 0 to "Sensitivity Studies for TranStor Storage Cask Shielding Analyses."
Paper図書
HOPF, J. E.SIERRA NUCLEAR, INC.1997/11/19.
Other Libraries in Japan

Conceptual design report for a transportable DUCRETE spent fuel storage cask system (INEL ; INEL-95/0167; DE95017516)

Conceptual design report for a transportable DUCRETE spent fuel storage cask system (INEL ; INEL-95/0167; DE95017516)
Paper図書
Hopf, J.E.Lockheed Idaho Technologies Co.1995.8.
Other Libraries in Japan
  • Author HeadingHopf, J.E.

Redacted rev 2 to "TranStor Mox Fuel Criticality Analysis."

Redacted rev 2 to "TranStor Mox Fuel Criticality Analysis."
Paper図書
CHECHELNITSKY, //HOPF, J. E.SIERRA NUCLEAR, INC.1998/11/23.
Other Libraries in Japan

Redacted rev 3 to "TranStor BWR Criticality Analysis."

Redacted rev 3 to "TranStor BWR Criticality Analysis."
Paper図書
HOPF, J. E.//PFEIFER, H.SIERRA NUCLEAR, INC.1998/11/23.
Other Libraries in Japan

Redacted rev 4 to "TranStor PWR Criticality Analysis."

Redacted rev 4 to "TranStor PWR Criticality Analysis."
Paper図書
CHECHELNITSKY, //HOPF, J. E.//PFEIFER, H.SIERRA NUCLEAR, INC.1998/11/23.
Other Libraries in Japan

Rev 1 to calculation PGE01-10.02.01-10, "Greater Than Class C Waste Design Basis Radiation Source Strength & Matl Densities."

Rev 1 to calculation PGE01-10.02.01-10, "Greater Than Class C Waste Design Basis Radiation Source Strength & Matl Densities."
Paper図書
HOPF, J. E.//STEVENS, R. J.SIERRA NUCLEAR, INC.1997/11/20.
Other Libraries in Japan

Redacted rev 0 to "Stainless Steel Clad Fuel Thermal Analysis."

Redacted rev 0 to "Stainless Steel Clad Fuel Thermal Analysis."
Paper図書
CHECHELNITSKY, //HOPF, J. E.SIERRA NUCLEAR, INC.1996/09/13.
Other Libraries in Japan

Rev 1 to calculation PGE01.10.02.01.03, "Radiation Source Strengths & Matl Densities for Spent Fuel Basket Analyses."

Rev 1 to calculation PGE01.10.02.01.03, "Radiation Source Strengths & Matl Densities for Spent Fuel Basket Analyses."
Paper図書
CHECHELNITSKY, //HOPF, J. E.//PFEIFER, H.SIERRA NUCLEAR, INC.1997/09/21.
Other Libraries in Japan

"TranStor PWR Sys Dose Versus Distance for Single Cask."

"TranStor PWR Sys Dose Versus Distance for Single Cask."
Paper図書
CHECHELNITSKY, B.//HOPF, J. E.SIERRA NUCLEAR, INC.1996/02/28.
Other Libraries in Japan

Rev 1 to calculation PGE01.10.02.01-01, "ISFSI Dose Calculation."

Rev 1 to calculation PGE01.10.02.01-01, "ISFSI Dose Calculation."
Paper図書
CHECHELNITSKY, //HOPF, J. E.//STEVENS, R. J.SIERRA NUCLEAR, INC.1997/11/26.
Other Libraries in Japan

Rev 1 to calculation SNC-213.04.01, "Radiation Exposure of Basket Coating Matl."

Rev 1 to calculation SNC-213.04.01, "Radiation Exposure of Basket Coating Matl."
Paper図書
CHECHELNITSKY, //HOPF, J. E.//STEVENS, R. J.SIERRA NUCLEAR, INC.1997/11/20.
Other Libraries in Japan

Rev 1 to calculation PGE 10.02.01-07, "TranStor PWR Sys Dose Versus Distance for Single Cask."

Rev 1 to calculation PGE 10.02.01-07, "TranStor PWR Sys Dose Versus Distance for Single Cask."
Paper図書
CHECHELNITSKY, //HOPF, J. E.//STEVENS, R. J.SIERRA NUCLEAR, INC.1997/11/26.
Other Libraries in Japan

Redacted rev 1 to "Most Reactive Loose Pellet Configuration."

Redacted rev 1 to "Most Reactive Loose Pellet Configuration."
Paper図書
CHECHELNITSKY, //HOPF, J. E.//LE, T. T.SIERRA NUCLEAR, INC.1997/11/20.
Other Libraries in Japan

Rev 3 to design calculation, "Required Boron Concentrations for Various Assembly Types & Fuel Enrichments in VSC-24 MSB."

Rev 3 to design calculation, "Required Boron Concentrations for Various Assembly Types & Fuel Enrichments in VSC-24 MSB."
Paper図書
HOPF, J. E.//THOMPSON, T. C.SIERRA NUCLEAR, INC.1996/04/19.
Other Libraries in Japan

Rev 0 to PFS01.10.02.03, "Private Fuel Storage Skyshine II ISFSI Dose Rate Calculation (4000 Casks)."

Rev 0 to PFS01.10.02.03, "Private Fuel Storage Skyshine II ISFSI Dose Rate Calculation (4000 Casks)."
Paper図書
CHECHELNITSKY, //HOPF, J. E.//LE, T. T.SIERRA NUCLEAR, INC.1997/04/10.
Other Libraries in Japan

Rev 0, "Benchmark Calculations & Validation of Scale-4.1 Code Package (PC Version) for Analysis of Cask Sys w/Highly Enriched Fresh Fuel,Fixed Poisons & Unborated Water."

Rev 0, "Benchmark Calculations & Validation of Scale-4.1 Code Package (PC Version) for Analysis of Cask Sys w/Highly Enriched Fresh Fuel,Fixed Poisons & Unborated Water."
Paper図書
HOPF, J. E.//THOMPSON, T.SIERRA NUCLEAR, INC.1995/09/06.
Other Libraries in Japan

Rev 1 to design calculation, "VSC-24 Air Scattered Dose at Calculations Using MCNP Computer Code."

Rev 1 to design calculation, "VSC-24 Air Scattered Dose at Calculations Using MCNP Computer Code."
Paper図書
HOPF, J. E.//THOMPSON, T. C.SIERRA NUCLEAR, INC.1996/03/05.
Other Libraries in Japan

Redacted rev 1 to "TranStor PWR Basket Most Reactive Canister Analysis."

Redacted rev 1 to "TranStor PWR Basket Most Reactive Canister Analysis."
Paper図書
HOPF, J. E.//PFEIFER, H.//THOMPSON, T.SIERRA NUCLEAR, INC.1997/03/07.
Other Libraries in Japan
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