1. Name of Experiment:
 ------------------
 Transmission of Quasi-Monoenergetic Neutrons Generated by 43 MeV and 68 MeV
 Protons Through Iron, Concrete(1996) and Polyethylene(1997) Shields

2. Purpose and Phenomena Tested:
 ----------------------------
 Intermediate-energy neutron spectra and reaction rates behind and inside up to
 130 cm thick iron shield, up to 200 cm thick concrete shield, and up to 180 cm
 thick polyethylene were measured for 43 and 68 MeV p-Li7 quasi-monoenergetic
 neutron source at the 90-MV AVF cyclotron of the TIARA facility in JAERI.
 The energy between 1E-10(MeV) and the peak energy of the neutrons generated by
 the Li7(p,n) reaction was measured.

3. Description of Source and Experimental Configuration:
 ----------------------------------------------------
 Figure 1 shows a cross sectional view of the Takasaki Ion Accelerator for
 Advanced Radiation Application (TIARA) facility with the experimental
 arrangement.
 Quasi-monoenergetic source neutrons were generated by 43- and 68-MeV protons
 bombarding 3.6 mm and 5.2 mm thick 99.9 % enriched Li-7 targets, respectively.
 The protons penetrating the target with a 2-MeV energy loss were bent down
 toward the beam dump by a clearing magnet. The neutrons produced in the
 forward angle reached the experimental room through a 10.9 cm diameter and
 225 cm long iron collimator embedded in the concrete wall. The intensity of
 source neutrons was monitored with a proton beam Faraday cup and two fission
 counters placed near the Li-7-target and the collimator. An iron test shield
 of 10 to 130 cm thickness was assembled [1, 2, 5] with 10 cm thick iron slabs
 of 120 cm x 120 cm rectangular surface on a movable stand. A concrete test
 shield of 25 to 200 cm thickness was also assembled [3, 6] with 120 x 120
 x 25 cm3 slabs on the movable stand. A polyethylene test shield of 30.5 to
 183.0 cm thickness was also assembled [4, 7] with 118.5 x 118.0 x 30.5 cm3 slabs
 on the movable stand. Experimental setup for the iron and concrete test shield
 is shown in Fig. 2 and Fig. 3, and for the polyethylene shield in Fig. 4 and
 Fig. 5. An additional iron collimator shown in Fig. 3 and Fig. 5 was used for
 measurements of thinner test shields and off axis measurements in order to
 depress the neutron leakage through the collimator wall and rotary shutter
 shown in Fig. 1. The additional collimator of 40 to 80 cm thickness was
 assembled with 120 x 120 x 10 cm3 slabs with a 10.9 cm diameter cylindrical
 hole on the movable stand. Thicknesses of the test shields and the additional
 collimator, peak flux of source neutrons per proton beam charge (microcoulombs-
 microC) are given in Table 1. Atom densities of the iron, concrete and
 polyethylene test shields and the additional collimator are given in Table 2.

 Absolute fluxes of source neutrons in the monoenergetic peak per proton beam
 charge (microcoulombs), shown in Table 1, have been measured with a proton-
 recoil-counter-telescope (PRT) set at the position of 5.54 m from the Li target.
 The spectra of quasi-monoenergetic source neutrons were measured by the time
 of flight (TOF) method with the BC501A liquid scintillation detector placed
 about 14 m away from the target. Normalized measured source neutron energy
 spectra are given in Tables 3 and 4, presented as flux per proton beam charge,
 and shown in Fig. 6.

4. Measurement System:
 ------------------
 Five kinds of detectors were used: the BC501A organic liquid scintillation
 detector, the Bonner ball counter, 238U and 232Th fission counters, Li7F and
 Li(nat)F thermoluminescent dosimeters (TLD) and solid state nuclear track
 detectors (SSNTD).

 To measure the neutron energy spectra, a 12.7 cm diameter x 12.7 cm long
 BC501A liquid scintillation detector was placed behind the test shields.
 The pulse height distributions of the detector were converted to neutron
 energy spectra by the FERDOU unfolding code [8] and a measured response
 matrix [9].

 A Bonner sphere spectrometer with four polyethylene moderators of thicknesses
 1.5, 3.0, 5.0, 9.0 cm, and without moderator, shown in Fig. 7, was placed
 behind the test shields for measurements of energy dependent neutrons. The
 central part is a 5.08 cm diameter spherical proportional counter filled with
 10 atm (at 22 degree) He-3 gas. Reaction rates above gamma-ray discrimination
 level were measured for five different moderator thicknesses. These five
 reaction rates were unfolded with the SAND-2 code [10] and the response
 functions given by Uwamino et al [11]. The response functions are given in
 Table 26.

 U-238 and Th-232 fission counters (Centronic FC480/1000) with a 10.1 cm long
 x 3.81 cm diameter active volume were used to measure fission rates behind the
 test shields. Absolute efficiencies of U-238 and Th-232 fission counters were
 (1.05 +- 0.04) x 1.E+3 and (9.86 +- 0.34) x 1.E+2 barn/cm^2/counts,
 respectively, which were measured with a Cf-252 neutron source.

 Neutron reaction rates were measured on the beam axis in the test shield using
 Li7F and Li(nat)F thermoluminescent dosimeters (TLD) (Harshaw Co. Ltd.) of
 1 x 1 x 6 mm3. Thermoluminescence was converted to the absolute dose in TLD
 using a calibration factor determined with a Co60 gamma-ray source within the
 uncertainty less than 3 %. The neutron energy responses, calculated by a
 code developed by Hashikura et al., are tabulated in Table 46.

 The neutron reaction rates in the test shield were also measured using a solid
 state nuclear track detectors. The composition of the detector is Allyl
 diglycol carbonate which is the same as that of CR-39. The detector is a
 rectangular solid of 10 mm x 5 mm and 1 mm thick attached with a 1 mm thick
 polyethylene radiator. The exposed detectors were etched chemically, the etch
 pits on the detectors were counted through an optical microscope of 400 times
 magnifications. The detector response, calculated by a Monte Carlo code system,
 is given in Table 49.

5. Description of Results and Analysis:
 -----------------------------------
 The main source of information were references [1, 2, 3, 4].

 Transmitted neutron energy spectra behind the iron test shields measured
 with the BC501A scintillation detector are given in Tables 5-13. Tables 5
 and 10 present the spectra on the beam axis behind the iron test shields.
 Tables 6-9 and Tables 11-13 show the spectra at the off beam positions. The
 error bars consist of errors of spectrum unfolding and counting statistics.
 Other errors in the source neutron flux are estimated to be less than 6.6%
 (errors of PRT (3-5%), conversion factor of fluence monitor to total charges
 of proton beam (3%), neutron penetration factor through objects on the beam
 line (3%) and the fluence monitor counting statistics (less than 1%)).
 Transmitted neutron energy spectra behind the concrete and polyethylene test
 shields measured with the BC501A scintillation detector are given
 in Tables 14-19 and Tables 20-25, respectively.

 The reaction rates of the Bonner sphere spectrometer behind the iron, concrete
 and polyethylene test shields are given in Tables 27-28, Tables 29-30 and
 Tables 31-32, respectively. Neutron spectra behind the iron, concrete and
 polyethylene test shields obtained from the reaction rates using the SAND-2
 unfolding code and the response functions are given in Tables 33-34, Tables 35-36,
 and Tables 37-38, respectively. The experimental errors of the Bonner sphere
 spectrometer could not be estimated by the SAND-2 unfolding code.

 The fission rates measured behind the iron, concrete and polyethylene test
 shields using fission counters are given in Tables 39-40, Tables 41-42 and
 Tables 43-44, respectively. The uncertainties of the measured data given
 in the tables include the counting statistics of the fission counters and
 neutron fluence monitors. The U-238 and Th-232 fission counters measure the
 neutron flux above the threshold energy of about 1 MeV.

 The differences between neutron reaction rates of Li7F and Li(nat)F TLDs
 measured inside the iron and concrete shields are given in Tables 47 and 48,
 respectively. As the Li7F and Li(nat)F response functions differ significantly
 only below about 1 MeV, these differences are the measure of the neutron flux
 up to 1 MeV. The uncertainties of the measured data given in the tables
 include the counting statistics of each detector and neutron fluence monitor.

 The neutron reaction rates of SSNTD measured inside the iron, concrete and
 polyethylene shields are given in Tables 50, 51 and 52, respectively.
 The detector is sensitive to neutrons below 10 MeV. The uncertainties of
 the measurements include the counting statistics of etch pits and neutron
 fluence monitor.

 Neutron dose-equivalent behind the iron, concrete and polyethylene shields
 measured with a rem counter (Fuji Co. Ltd.) are given in Tables 53 to 58.

 Model for Calculation:
 The calculations of the 43- and 68-MeV p-Li neutron energy spectra using Monte
 Carlo and deterministic transport codes are described in [4, 5, 6] (using MORSE-CG,
 DOT3.5 and HETC-KFA2 codes), [14, 17] (DORT, MCNP4B), [15] (LAHET) and [16, 18]
 (MCNPX). The input data used for the LAHET and HMCNP4A calculations are given
 in [15].

 The authors of the experiment propose [1] to use a three-dimensional (X,Y,Z) or
 two-dimensional (R-Z) calculational models. Calculational geometry used for the
 MORSE and HETC Monte Carlo codes is shown in Fig. 8. In the figure Tc is a
 thickness of additional collimator which are given in Table 1. The 43- and
 68-MeV p-Li neutron beams impinge on the shielding assembly at its center.
 The neutron beam spreading is 5.94 x 1.E-4 sr. As shown in Fig. 8 cylindrical
 flux estimators were placed behind the shield surface on and off beam axes.
 The measured source energy spectra for 43- and 68-MeV p-Li neutrons can be
 taken from the Tables 3-4.
 Atom densities of the test shields and the additional collimator are given in
 Table 2.

 To calculate the fission rate, the U-238 and Th-232 fission cross sections
 given in Table 45 can be used. They include the data from JENDL-3 [12] in the
 neutron energy up to 20 MeV, and those measured by Lisowski et al. [13] in the
 energy region between 20 and 400 MeV.

 Normalization Between Calculation and Measurement:
 Calculated values of the transmitted spectra and count rates should be
 normalized by proton beam charge (microcoulombs). Total source neutrons per
 proton beam charge can be calculated with the peak flux given in Table 1 and
 the energy spectrum given in Tables 3 and 4.

6. Special Features:
 ----------------
 None

7. Author/Organizer:
 ----------------
 Experiment and analysis:

 Hiroshi Nakashima, Yoshihiro Nakane, Yukio Sakamoto, Shun-ichi Tanaka,
 Hiroshi Takada and Shin-ichiro Meigo,
 Neutron Science Center, Japan Atomic Energy Research Institute(JAERI),
 Tokai-mura, Naka-gun, Ibaraki-ken, 319-1195, Japan
 Phone: +81-29-282-6144
 Fax: +81-29-282-5996

 Susumu Tanaka
 Takasaki Establishment, Japan Atomic Energy Research Institute(JAERI),
 Watanuki-cho, Takasaki, Gunma-ken, 370-12, Japan
 Phone: +81-27-346-9610
 Fax: +81-27-346-9690

 Noriaki Nakao
 Radiation Science Center,
 High Energy Accelerator Research Organization(KEK),
 Oho 1-1, Tsukuba, Ibaraki, 305-0801, Japan
 Phone: +81-298-79-6004
 Fax: +81-298-64-4051

 Makoto Nakao
 Kawasaki Heavy Industry Co. Ltd.

 Takashi Nakamura
 Department of Quantum Science and Energy Engineering, Tohoku University,
 Aoba, Aramaki, Aoba-ku, Sendai-shi, Miyagi-ken 980-8579, Japan
 Phone: +81-22-217-7805
 Fax: +81-22-217-7809

 Kazuo Shin
 Department of Nuclear Engineering, Kyoto University
 Yoshidahonmachi, Sakyou-ku, Kyoto, Japan
 Phone: +81-75-753-5825
 Fax: +81-75-753-5845

 Mamoru Baba
 Cyclotron Radioisotope Center(CYRIC), Tohoku University,
 Aoba, Aramaki, Aoba-ku, Sendai-shi, Miyagi-ken 980-8578, Japan
 Phone: +81-22-217-7909
 Fax: +81-22-217-7809

 Compiler of data for Sinbad:
 I. Kodeli
 Institute Jozef Stefan, Jamova 39, 1000 Ljubljana, Slovenia

 Reviewer of compiled data:
 Noriaki Nakao
 Radiation Science Center,
 High Energy Accelerator Research Organization(KEK),
 Oho 1-1, Tsukuba, Ibaraki, 305-0801, Japan
 Phone: +81-298-79-6004
 Fax: +81-298-64-4051


8. Availability:
 ------------
 Unrestricted

9. References:
 ----------
 [1] Y. Nakane, K. Hayashi, Y. Sakamoto, N. Yoshizawa, N. Nakao, S. Ban,
 H. Hirayama, Y. Uwamino, K. Shin and T. Nakamura: "Neutron Transmission
 Benchmark Problems for Iron and Concrete Shields in Low, Intermediate
 and High Energy Proton Accelerator Facilities", JAERI-Data/Code 96-029,
 (1996).
 [2] H. Nakashima, N. Nakao, Sh. Tanaka, T. Nakamura, K. Shin, Su. Tanaka,
 S. Meigo, Y. Nakane, H. Takada, Y. Sakamoto and M. Baba : "Experiments on
 Iron Shield Transmission of Quasi-monoenergetic Neutrons Generated by 43-
 and 68-MeV Protons via the 7Li(p,n) Reaction", JAERI-Data/Code 96-005,
 (1996).
 [3] N. Nakao, H. Nakashima, Y. Sakamoto, Y. Nakane, Sh. Tanaka, Su. Tanaka,
 T. Nakamura, K. Shin and M. Baba: "Experimental Data on Concrete Shield
 Transmission of Quasi-monoenergetic Neutrons Generated by 43- and 68-MeV
 Protons via the 7Li(p,n) Reaction", JAERI-Data/Code 97-020 (1997).
 [4] N. Nakao, H. Nakashima, M. Nakao, Y. Sakamoto, Y. Nakane, Su. Tanaka,
 Sh. Tanaka and T. Nakamura: "Experimental Data on Polyethylene Shield
 Transmission of Quasi-monoenergetic Neutrons Generated by 43- and 68-MeV
 Protons via the 7Li(p,n) Reaction", JAERI-Data/Code 98-013 (1998).
 [5] H. Nakashima, N. Nakao, Sh. Tanaka, T. Nakamura, K. Shin, Su. Tanaka,
 H. Takada, S. Meigo, Y. Nakane, Y. Sakamoto and M. Baba : "Transmission
 through Shields of Quasi-Monoenergetic Neutrons Generated by 43- and
 68-MeV Protons. Part-II: Iron Shielding Experiment and Analysis for
 Investigating Calculation Methods and Cross Section Data",
 Nucl. Sci. Eng. 124, No. 2 (October 1996) 243.
 [6] N. Nakao, H. Nakashima, T. Nakamura, Sh. Tanaka, Su. Tanaka, K. Shin,
 M. Baba, Y. Sakamoto and Y. Nakane : "Transmission through Shields of
 Quasi-Monoenergetic Neutrons Generated by 43- and 68-MeV Protons. Part-I:
 Concrete Shielding Experiment and Calculation for Practical Application",
 Nucl. Sci. Eng. 124, No. 2 (October 1996) 228.
 [7] N. Nakao, M. Nakao, H. Nakashima, Su. Tanaka, Y. Sakamoto, Y. Nakane,
 Sh. Tanaka and T. Nakamura: "Measurements and Calculations of Neutron
 Energy Spectra Behind Polyethylene Shields Bombarded by 40- and 65-MeV
 Quasi-Monoenergetic Neutron Sources", J. Nucl. Sci. Technol., 34(4)
 (1997) pp348-359.
 [8] K. Shin, Y. Uwamino and T. Hyodo : "Propagation of Errors from Response
 Functions to Unfolded Spectrum," Nucl. Technol., 53, 78 (1981).
 [9] N. Nakao, T. Nakamura, M. Baba, Y. Uwamino, N. Nakanishi, H. Nakashima
 and Sh. Tanaka : "Measurements of Response Function of Organic Liquid
 Scintillator for Neutron Energy Range up to 135 MeV", Nucl. Instrum.
 Methods, A362, 454 (1995).
 [10] W. N. McElroy, S. Berg, T. Crokett and R. G. Hawkins : "A Computer
 Automated Iterative Methods for Neutron Flux Spectra Determination by
 Foil Activation", AFWL-TR-67-41, Air Force Weapons Laboratory, Kirtland
 Air Force Base, vol. 1-4 (1967).
 [11] Y. Uwamino, T. Nakamura and A. Hara: "Two Type of Multi-Moderator
 Neutron Spectrometers: Gamma-Ray Insensitive Type and High-Efficiency
 Type", Nucl. Instrum. Methods in Phys. Res., A239, 299 (1985).
 [12] K. Shibata et al.: "Japanese Evaluated Nuclear Data Library, Version-3
 -JENDL-3-", JAERI 1319(1990).
 [13] P. W. Lisowski et al.: "Fission Cross Sections in the Intermediate Energy
 Region", Proc. Spec. Meet. on Neutron Cross Section Standards for the
 Energy Region above 20 MeV, Uppsala, Sweden, 21-23 May, 1991, p.177-186
 (1991).
 [14] C. Konno, F. Maekawa, M. Wada, H. Nakashima, K. Kosako: "DORT Analysis of
 Iron and Concrete Shielding Experiments at JAERI/TIARA", JAERI-Conf 99-002,
 p.164-169 (1999).
 [15] N. E. Hertel, T. M. Evans: "Benchmarking the LAHET Elastic Scattering
 Model for APT Design Applications", ERDA Final Report, Prepared for the
 Westinghouse Savannah River Company under ERDA Task Order 96-081,
 JEFDOC-715 (1997).
 [16] A.J. Koning: "MCNPX analysis of 68 MeV neutron transmission on iron",
 JEFDOC-769 (1998).
 [17] Ch. Konno et al.: "Analyses of the TIARA experiments using the LA-150
 cross-section data library", JEFDOC-808 (1999).
 [18] A. Koning: "Processing and validation of intermediate energy evaluated
 data files", JEFDOC-838 (May 2000).

10. Data and Format:
 ---------------

 FILE  bytes  Description NAME
 ----  -----  -------------------------------------------------------
 1     26.373 This information file tia-abs htm
 2    121.918 Description of Experiment and Results tia-exp htm
 3     87.572 Fig. 1: Cross sectional view of TIARA facility tia-f1 jpg
 4     82.344 Fig. 2: Experimental setup for iron and concrete test shield (top view) tia-f2 jpg
 5     73.495 Fig. 3: Experimental setup with additional iron collimator for iron and concrete test shield (top view) tia-f3 jpg
 6     84.284 Fig. 4: Experimental setup for polyethylene test shield tia-f4 jpg
 7     72.311 Fig. 5: Experimental setup with additional collimator for polyethylene test shield (top view) tia-f5 jpg
 8     80.335 Fig. 6: Source neutron energy spectra tia-f6 jpg
 9    127.957 Fig. 7: Bonner sphere spectrometer tia-f7 jpg
 10   131.529 Fig. 8: Calculational geometry for MORSE and HETC tia-f8 jpg
 11 3.535.219 Reference j96-029.pdf
 12 2.395.389 Reference j96-005.pdf
 13 2.460.312 Reference j97-020.pdf
 14 2.266.883 Reference j98-013.pdf
 15 1.203.715 Reference nse96243.pdf
 16 1.145.416 Reference nse96228.pdf
 17 1.056.667 Reference nse97.pdf
 18 1.102.247 Reference jef-715.pdf
 19   326.267 Reference jef-769.pdf
 20 1.442.180 Reference jef-808.pdf
 21   151.530 Reference jef-838.pdf
 22   515.505 Reference j99-002.pdf

 The file tia-exp.htm contains the following tables:

 Tab. 1: Test shield dimensions and characteristics
 Tab. 2: Iron, concrete and polyethylene atom densities
 Tab. 3, 4: 43-MeV and 68-MeV p-7Li source neutron spectrum
 Tab. 5 - 9: BC501A detector spectra in iron for 43-MeV p-Li neutrons
 Tab. 10 - 13: BC501A detector spectra in iron for 68-MeV p-Li neutrons
 Tab. 14 - 16: BC501A detector spectra in concrete for 43-MeV p-Li neutrons
 Tab. 17 - 19: BC501A detector spectra in concrete for 68-MeV p-Li neutrons
 Tab. 20 - 22: BC501A detector spectra in polyethylene for 43-MeV p-Li neutrons
 Tab. 23 - 25: BC501A detector spectra in polyethylene for 68-MeV p-Li neutrons
 Tab. 26: Response function of Bonner sphere spectrometer
 Tab. 27, 28: Bonner sphere reaction rates in iron for 43 and 68 MeV p-Li neutrons
 Tab. 29, 30: Bonner sphere reaction rates in concrete for 43 and 68 MeV p-Li neutrons
 Tab. 31, 32: Bonner sphere reaction rates in polyethylene for 43 and 68 MeV p-Li neutrons
 Tab. 33, 34: Bonner sphere spectra in iron for 43 and 68 MeV p-Li neutrons
 Tab. 35, 36: Bonner sphere spectra in concrete for 43 and 68 MeV p-Li neutrons
 Tab. 37, 38: Bonner sphere spectra in polyethylene for 43 and 68 MeV p-Li neutrons
 Tab. 39, 40: Fission rates in iron for 43 and 68 MeV p-Li neutrons
 Tab. 41, 42: Fission rates in concrete for 43 and 68 MeV p-Li neutrons
 Tab. 43, 44: Fission rates in polyethylene for 43 and 68 MeV p-Li neutrons
 Tab. 45: Th-232 and U-238 fission cross sections
 Tab. 46: Li7F and Li(nat)F TLDs response functions
 Tab. 47: Li7F - Li(nat)F reaction rates in iron for 43 and 68 MeV p-Li neutrons
 Tab. 48: Li7F - Li(nat)F reaction rates in concrete for 43 and 68 MeV p-Li neutrons
 Tab. 49: SSNTD response functions
 Tab. 50: SSNTD reaction rates in iron for 43 and 68 MeV p-Li neutrons
 Tab. 51: SSNTD reaction rates in concrete for 43 and 68 MeV p-Li neutrons
 Tab. 52: SSNTD reaction rates in polyethylene for 43 and 68 MeV p-Li neutrons
 Tab. 53-58: Neutron dose-equivalent measured with a rem counter (Fuji Co. Ltd.).

 Figures are included in JPG format.

SINBAD Benchmark Generation Date: 11/2000
SINBAD Benchmark Last Update: 04/2006