-
1
-
-
4944226178
-
Effect of high-density fuel loading on criticality of low enriched uranium fueled material test research reactors
-
R. Ahmed, and N. Aslam and Ahmad Effect of high-density fuel loading on criticality of low enriched uranium fueled material test research reactors Annals of Nuclear Energy 32 2005 29 62
-
(2005)
Annals of Nuclear Energy
, vol.32
, pp. 29-62
-
-
Ahmed, R.1
Aslam2
Ahmad, N.3
-
2
-
-
13444292480
-
Effect of updated WIMSD Libraries on Neutron Energy Spectrum at Irradiation Site of Pakistan Research Reactor-1 using 3D Modeling
-
S.I. Ahmad, and N. Ahmad Effect of updated WIMSD Libraries on Neutron Energy Spectrum at Irradiation Site of Pakistan Research Reactor-1 using 3D Modeling Annals of Nuclear Energy 32 2005 1521 1548
-
(2005)
Annals of Nuclear Energy
, vol.32
, pp. 1521-1548
-
-
Ahmad, S.I.1
Ahmad, N.2
-
3
-
-
4444250263
-
Effect of New Cross section Evaluations on Criticality and Neutron Energy Spectrum of a Typical Material Test Reactor
-
S.I. Ahmad, N. Ahmad, and Aslam Effect of New Cross section Evaluations on Criticality and Neutron Energy Spectrum of a Typical Material Test Reactor Annals of Nuclear Energy 31 2004 1867 1881
-
(2004)
Annals of Nuclear Energy
, vol.31
, pp. 1867-1881
-
-
Ahmad, S.I.1
Ahmad, N.2
Aslam3
-
4
-
-
0039032400
-
Criticality calculations for the spent fuel storage pools for Etrr_1 and Etrr_2 reactors
-
M. Aziz, and K. Andrzejewski Criticality calculations for the spent fuel storage pools for Etrr_1 and Etrr_2 reactors NUKLEONIKA 45 2000 141 144
-
(2000)
NUKLEONIKA
, vol.45
, pp. 141-144
-
-
Aziz, M.1
Andrzejewski, K.2
-
5
-
-
31144458105
-
-
ORNL/TM-2003/252, Nuclear Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-6283
-
Basher, H. and Neal, J.S., 2003. Autonomous Control of Nuclear Power Plants, ORNL/TM-2003/252, Nuclear Science and Technology Division, Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831-6283.
-
(2003)
Autonomous Control of Nuclear Power Plants
-
-
Basher, H.1
Neal, J.S.2
-
6
-
-
0033873316
-
Criticality and safety parameter studies of a 3-MW TRIGA MARK-II research reactor and validation of the generated cross-section library and computational method
-
S.I. Bhuiyan, M.A.W. Mondal, M.M. Sarker, M. Rahman, M.S. Shahdatullah, and M.Q. Huda Criticality and safety parameter studies of a 3-MW TRIGA MARK-II research reactor and validation of the generated cross-section library and computational method Nuclear Technology 130 2000 111 131
-
(2000)
Nuclear Technology
, vol.130
, pp. 111-131
-
-
Bhuiyan, S.I.1
Mondal, M.A.W.2
Sarker, M.M.3
Rahman, M.4
Shahdatullah, M.S.5
Huda, M.Q.6
-
7
-
-
0001615459
-
Current status of Russian evaluated neutron data libraries
-
Gatlingburg, Tennessee, May 9-13, American Nuclear Society
-
Blokhin, A.I., 1994, Current Status of Russian Evaluated Neutron Data Libraries, Proc. Int. Conf. Nuclear Data for Science and Technology, Gatlingburg, Tennessee, May 9-13, American Nuclear Society.
-
(1994)
Proc. Int. Conf. Nuclear Data for Science and Technology
-
-
Blokhin, A.I.1
-
9
-
-
0036567992
-
Neutronic calculation to the TRIGA Ipr-R1 reactor using the WIMSD4 and CITATION codes
-
H.M. Dalle, C. Pereira, and R.G.P. Souza Neutronic calculation to the TRIGA Ipr-R1 reactor using the WIMSD4 and CITATION codes Annals of Nuclear Energy 29 2002 901 912
-
(2002)
Annals of Nuclear Energy
, vol.29
, pp. 901-912
-
-
Dalle, H.M.1
Pereira, C.2
Souza, R.G.P.3
-
10
-
-
0142149070
-
Use of Sensitivity and Uncertainty Analysis to select Benchmark Experiments for the validation of Computer Codes and data
-
K.R. Elam, and B.T. Rearden Use of Sensitivity and Uncertainty Analysis to select Benchmark Experiments for the validation of Computer Codes and data Nuclear Science and Engineering 145 2003 196 212
-
(2003)
Nuclear Science and Engineering
, vol.145
, pp. 196-212
-
-
Elam, K.R.1
Rearden, B.T.2
-
11
-
-
0003734974
-
-
ENDF-201 P.F. Rose National Nuclear Data Center, Brookhaven National Laboratory
-
ENDF-201 P.F. Rose ENDF/B-VI Summary Documentation, BNL-NCS-17541 1991 National Nuclear Data Center, Brookhaven National Laboratory
-
(1991)
ENDF/B-VI Summary Documentation, BNL-NCS-17541
-
-
-
13
-
-
0041693772
-
Use of international criticality safety benchmark evaluation project data to benchmark a JEF2.2 based library for MONK
-
D. Hanlon, and N. Smith Use of international criticality safety benchmark evaluation project data to benchmark a JEF2.2 based library for MONK Nuclear Science and Engineering 145 2003 120 131
-
(2003)
Nuclear Science and Engineering
, vol.145
, pp. 120-131
-
-
Hanlon, D.1
Smith, N.2
-
16
-
-
2542428281
-
Neutronics analysis of natural uranium fueled, light water cooled, heavy water moderated and graphite reflected nuclear reactors
-
M.J. Khan, and N. Aslam and Ahmad Neutronics analysis of natural uranium fueled, light water cooled, heavy water moderated and graphite reflected nuclear reactors Annals of Nuclear Energy 31 2004 1331 1356
-
(2004)
Annals of Nuclear Energy
, vol.31
, pp. 1331-1356
-
-
Khan, M.J.1
Aslam2
Ahmad, N.3
-
17
-
-
38349026764
-
WIMS-D library update
-
Leszczynski, F., Aldama, D.L., Trkov, A., 2003, WIMS-D Library Update, Final Report of a Co-ordinated Research Project.
-
(2003)
Final Report of A Co-ordinated Research Project
-
-
Leszczynski, F.1
Aldama, D.L.2
Trkov, A.3
-
20
-
-
4444347973
-
Integral test of JENDL-3.3 for thermal reactors
-
Tokai, Japan, Nov. 21-22, JAERI-Conf, 2003-006 15-21
-
Okumura, K., Mori, T., 2003. Integral Test of JENDL-3.3 for Thermal Reactors, Proc. of the 2002 Symposium on Nuclear Data, Tokai, Japan, Nov. 21-22, JAERI-Conf, 2003-006 15-21
-
(2003)
Proc. of the 2002 Symposium on Nuclear Data
-
-
Okumura, K.1
Mori, T.2
-
22
-
-
0011970192
-
-
AEEW-R538
-
Roth, M.J., Macdougall, J.D. and Kemshell, P.B., 1967, The preparation of Input Data for WIMS, AEEW-R538.
-
(1967)
The Preparation of Input Data for WIMS
-
-
Roth, M.J.1
MacDougall, J.D.2
Kemshell, P.B.3
-
23
-
-
0035157147
-
A proposal for benchmarking 235U nuclear data
-
A.D. Santos, R. Fuga, R. Jerez, A.Y. Abe, and E.A. Filho A proposal for benchmarking 235U nuclear data Nuclear Science and Engineering 137 2001 52 69
-
(2001)
Nuclear Science and Engineering
, vol.137
, pp. 52-69
-
-
Santos, A.D.1
Fuga, R.2
Jerez, R.3
Abe, A.Y.4
Filho, E.A.5
-
24
-
-
0040948939
-
-
ANL/RERTR/TM-11
-
Snelgrove, J.L., Domagala, R.F., Hofman, G.L., Weincek, T.C., Copeland, G.L., Hobbs, R.W. and Senn, R.L., 1987, The Use of U3Si2 Dispersed in Aluminum in Plate-Type Fuel Elements for Research and Test Reactors, ANL/RERTR/TM-11.
-
(1987)
The Use of U3Si2 Dispersed in Aluminum in Plate-type Fuel Elements for Research and Test Reactors
-
-
Snelgrove, J.L.1
Domagala, R.F.2
Hofman, G.L.3
Weincek, T.C.4
Copeland, G.L.5
Hobbs, R.W.6
Senn, R.L.7
-
25
-
-
31144463080
-
-
WLUP, 2001. The updated WIMS-D libraries derived from the basic evaluated data files and related documents are available at the web-site http://www-rcp.ijs.si/_wlup.
-
(2001)
-
-
-
26
-
-
0042695594
-
Validating JENDL-3.3 for water reflected low enriched uranium solution systems using STACY ICSBEP benchmark models
-
T. Yamamoto, Y. Miyoshi, and T. Kiyosumi Validating JENDL-3.3 for water reflected low enriched uranium solution systems using STACY ICSBEP benchmark models Nuclear Science and Engineering 145 2003 132 144
-
(2003)
Nuclear Science and Engineering
, vol.145
, pp. 132-144
-
-
Yamamoto, T.1
Miyoshi, Y.2
Kiyosumi, T.3
-
27
-
-
0037671482
-
Effective delayed neutron fraction and prompt neutron lifetime of tehran research reactor
-
M. Zaker Effective delayed neutron fraction and prompt neutron lifetime of tehran research reactor Annals of Nuclear Energy 30 2003 1591 1596
-
(2003)
Annals of Nuclear Energy
, vol.30
, pp. 1591-1596
-
-
Zaker, M.1
|